Advisory Material for the Application of the IAEA Transport Regulations

Transcription

1 Advisory Material for the Application of the IAEA Transport Regulations INTERNATIONAL A TO M IC EN ER G Y A G EN C Y, VIENNA,

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3 ADVISORY MATERIAL FOR THE APPLICATION OF THE IAEA TRANSPORT REGULATIONS

4 The follow ing States are M embers of the International A tom ic Energy Agency: AFGHANISTAN GUATEMALA PANAMA ALBANIA HAITI PARAGUAY ALGERIA HOLY SEE PERU ARGENTINA HUNGARY PHILIPPINES AUSTRALIA ICELAND POLAND AUSTRIA INDIA PORTUGAL BANGLADESH INDONESIA ROMANIA BELGIUM IRAN SAUDI ARABIA BOLIVIA IRAQ SENEGAL BRAZIL IRELAND SIERRA LEONE BULGARIA ISRAEL SINGAPORE BURMA ITALY SOUTH AFRICA BYELORUSSIAN SOVIET IVORY COAST SPAIN SOCIALIST REPUBLIC JAMAICA SRI LANKA CAMEROON JAPAN SUDAN CANADA JORDAN SWEDEN CHILE KENYA SWITZERLAND CHINA KHMER REPUBLIC SYRIAN ARAB REPUBLIC COLOMBIA KOREA, REPUBLIC OF THAILAND COSTA RICA KUWAIT TUNISIA CUBA LEBANON TURKEY CYPRUS LIBERIA UGANDA CZECHOSLOVAK SOCIALIST LIBYAN ARAB REPUBLIC UKRAINIAN SOVIET SOCIALIST REPUBLIC LIECHTENSTEIN REPUBLIC DENMARK LUXEMBOURG UNION OF SOVIET SOCIALIST DOMINICAN REPUBLIC MADAGASCAR REPUBLICS ECUADOR MALAYSIA UNITED KINGDOM OF GREAT EGYPT, ARAB REPUBLIC OF MALI BRITAIN AND NORTHERN EL SALVADOR MEXICO IRELAND ETHIOPIA MONACO UNITED STATES OF AMERICA FINLAND MOROCCO URUGUAY FRANCE NETHERLANDS VENEZUELA GABON NEW ZEALAND VIET-NAM GERMANY, FEDERAL REPUBLIC OF NIGER YUGOSLAVIA GHANA NIGERIA ZAIRE, REPUBLIC OF GREECE NORWAY ZAMBIA PAKISTAN The Agency s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July The Headquarters of the Agency are situated in Vienna. Its principal objective is "to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world. (C) IAEA, 1973 Permission to reproduce or translate the information contained in this publication may be obtained by writing to the International Atomic Energy Agency, Karntner Ring 11, P.O. Box 590, A-1011 Vienna, Austria, Printed by the IAEA in Austria June 1973

5 SAFETY SERIES No. 37 ADVISORY MATERIAL FOR THE APPLICATION OF THE IAEA TRANSPORT REGULATIONS INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1973

6 THIS ADVISORY MATERIAL IS ALSO PUBLISHED IN FRENCH, RUSSIAN AND SPANISH ADVISORY MATERIAL FOR THE APPLICATION OF THE IAEA TRANSPORT REGULATIONS IAEA, VIENNA, 1973 STI/PUB/324

7 FOREWORD The Regulations for the Safe Transport of Radioactive M aterials (Safety Series No. 6, 1973 Revised Edition, IAEA, Vienna (1973)) were developed toprotect the public, transport workers and property from radiation in the shipment of radioactive m aterials. Protection is achieved by a combination of limitations on the contents of a package according to the quantity and type of radioactivity, the package design, and certain simple handling, storage, and stowage precautions which are to be followed during transport. The Regulations include provisions concerning containment of the radioactive m aterial, protection against radiation emitted by the m aterial, safe dissipation of heat generatedin the process of absorbing the radiation, and prevention of criticality when the m aterial is fissile. While some provisions concern controlby the c a rrie r, for example seg regation to lim it the radiation level in occupied areas, reliance is placed in the main on provisions relating to the package design. The Regulations in general and the packaging standards in p articular define "what" has to be achieved, i. e. performance, rather than "how" to achieve the desired degree of protection in term s of detailed constructional requirements. Adequate protection depends on the Regulations being: (a) safe, i.e. reduction of hazard to transport workers and the general public to an acceptably low level; (b) practical, i. e. in relation to what all parties concerned (designers, applicants for approval, manufacturers, consignors, competent authorities, ca rrie rs, customs, emergency teams) are required to do, taking into account feasibility, cost, and degree of risk; (c) clear and concise, readilyunderstandable and free of detail which does not significantly add to safety. Discussions at the Seminar organized by the Agency, Vienna, 8-12 February 1971, on T ests on Transport Packaging for Radioactive M aterials, indicated the need, in respect of the technical requirements of the Regulations, for an advisory document to be issued as a companion to the regulatory document.

8 During the period 1-5 November 1971, immediately following the second meeting of the Panel that revised the Regulations, the Agency organized an additional Panel on the preparation of advisory m aterial relevant to the application of its revised Regulations. This advisory document sets forth supplementary information to the Regulations which m aybe useful in deciding"how" to achieve the necessary level of protection. Some practical recommendations in term s of constructional details based on experience of certain Member States are given. Wherever possible, the specific inform a tion is directed towards the users concerned. These include: designers, manufacturers, competent authorities, applicants for approval, consignors, ca rrie rs, customs authorities, and emergency teams. To enable ready cro ss-refere n ce between the regulatory document (IAEA Safety Series No.6 (1973)) and this companion advisory document, the latter is set out on the following basis: Left-hand margin giving Section, main and sub-headings of the regulatory document, together with their inclusive paragraph numbers, in the same sequence as in that document. Main column containing advisory m aterial numbered 101 -» in respect of m aterial relating to Section I of the regulatory document, 201 -» in respect of Section II, etc. Advisory m aterial of a general nature is given in the main column beginning opposite the regulatory section heading of the left-hand margin. Regulatory main and sub-headings are omitted when no specific advisory m aterial is included. Regulatory document s e c tion and paragraph references are given in brackets in the main column. References are given at the end of each Section and a bibliography is included at the end of the document. It is hoped that this layout will also promote the continued development of the Advisory Document. The present intention is that the Regulations for the Safe T ran s port of Radioactive M aterials should undergo a comprehensive review at intervals of ten years. Member States would, however, be invited at intervals of five years to indicate whether, in their opinion, an e a rlier review were called for. There exists a provision for making minor amendments to the Regulations the so-called ''90-day rule". Under this procedure, such changes of detail can be introduced as are necessary to keep the Regulations up to date provided Member States are given not less than 90 days notice of proposed changes and any comments they may wish to make on the proposed changes are taken into consideration.

9 So that the Advisory Document will adequately reflect current developments in procedures and techniques, it will be reviewed, if necessary, by consultants or panels of experts at intervals of about two and a half years. The up-dating of the advisory m aterial will be carefully co-ordinated with the review of the Regulations. Readers are invited to send any comments they may wish to make on the Advisory Document, including proposals for modifications, additions and deletions, to the D irector, Division of Nuclear Safety and Environmental Protection, International Atomic Energy Agency, 11 Karntner Ring, Vienna 1010, Austria. The Agency gratefully acknowledges the valuable assistance of Mr. Alan Fairbairn, United Kingdom Atomic Energy Authority, who, having served as Chairman of the Panel of Experts on the Advisory Material, collated the contributions of the experts and was always available for advice during the preparation of this document for publication.

10 CONTENTS S E C T IO N I - IN T R O D U C T IO N... 1 Purpose and scope... 1 Definitions for the purpose of these Regulations... 4 Competent au th o rity Limitation of exposure of persons to radiation General accident provisions References SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREM ENTS A d d i t i o n a l r e q u i r e m e n t s f o r T y p e A p a c k a g e s B asic additional requirements for Type B(U) packages Specific additional requirem ents for Type B(U) packages Additional requirements for Type B(M) packages References SECTION III - ITEMS EXEM PT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LO W -LEVEL SOLID RADIO ACTIVE MATERIAL Items exempt from the p re scrip tio n s Alternative transport arrangem ents for low specific activity m aterial (LSA) Alternative transport arrangem ents for low-level solid radioactive m aterial (LLS) References... 71

11 S E C T IO N IV - A C T IV IT Y L IM IT S Activity lim its for Type A and Type B packages Determination of Aj^ and A R e fe re n c e s SECTION V - CONTROLS FOR TRANSPORT.AND STORAGE IN TRANSIT T ra n s p o rt General requirements Leaking packages and contaminated conveyances Customs R e fe re n c e s ANNEX TO SECTION V: Derivation of safe working lim it, in term s of external radiation, for "fixed" and "non-fixed" contamination on surfaces of ra il v e h ic le s SECTION VI - FISSILE MATERIALS SECTION VII - TEST AND INSPECTION PROCEDURES Tests for packaging Target for the drop tests T ests for demonstrating ability to withstand normal conditions of transport T ests for demonstrating ability to withstand accident conditions of transport Tests for integrity of containment and shielding Tests for special form radioactive m aterial References ANNEX TO SECTION VII: Examples of vibration t e s t s SECTION VIII - ADMINISTRATIVE REQUIREMENTS Approval of special form radioactive m a te ria l Approval of package designs

12 Approval of transport by special arran g em en t Consignor's responsibilities Quality control in fabrication and maintenance of packaging References ANNEX TO SECTION VIII: Examples of approval req u irem e n ts BIBLIOGRAPHY LIST OF PANEL MEMBERS

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14 SECTION I S E C T IO N X - IN T R O D U C T IO N ( ) PURPOSE AND SCOPE ( ) 101. Radioactive m aterials can be tran s ported by land (rail and road), water and a ir. The transport of such m aterials includes loading, conveyance, unloading and tem porary storage The prescriptions embodied in the Regulations are aimed essentially at ensuring during transport: containment of the radioactive m aterial; protection against radiation emitted by the m aterial; dissipation of heat generated in the process of absorbing the radiation; and prevention of criticality when the m aterial is fissile During transport, radiation hazards affecting persons and radiosensitive objects in the environment may arise from the causes listed in (a) to (c) below. (a) The emission of ionizing radiation from packages of radioactive m aterials. Compliance with the Regulations should ensure that no person receives a radiation dose in excess of the permissible dose lim its [1] and that there is no unacceptable damage to undeveloped photographic film. (b) The accumulation during transport of radioactive substances in dangerous amounts on the surfaces of vehicles, storage facilities and other objects and areas regularly used for the sole purpose of tran s porting and storing radioactive m aterials. The amounts of radioactive substances on surrounding objects should not exceed the 1

15 2 S E C T IO N I S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid PURPOSE AND SCOPE ( ) regulatory maximum perm issible contamination lev els. (c) Accidents resulting in the escape of radioactive substances into the environment in large amounts. The design of Type B packaging1 should ensure that dangerous amounts of activity do not escape as a result of an accident The safe transport of radioactive m aterials can be ensured if: (a) appropriate, mechanically sound and technically sound packages are used; (b) the quantity of radioactive m aterial placed in each package does not exceed the regulatory activity limit for that package type; (c) the number of packages containing radioactive m aterials that are carried by vehicles is within the regulatory lim its; (d) wherever practicable, vehicles are assigned exclusively for the transport of radioactive m aterials and provided with radiation shielding, m oisture-proof internal surfaces, and, as necessary, lifting gear, anchoring devices and other special features; (e) packages containing radioactive m aterials are stowed in vehicles and stored at a safe distance from persons and photosensitive m aterials (use may be made of the shielding effect of other packages); (f) only those transport and lifting appliances which have been tested for technical reliability and carrying capacity are used in loading, conveying and unloading packages with radioactive m aterials; 1 S e e S e c tio n II o f t h e R e g u la tio n s, p a ra s

16 SECTIO N I 3 S E C T IO N I - IN T R O D U C T IO N ( ) PURPOSE AND SCOPE ( ) (g) packages containing radioactive m aterials are properly secured before tra n s port and periodic checks are made during transport; (h) periodic or continuous environmental monitoring is carried out during transport if required by the competent authority; (i) continuous personnel monitoring is carried out during transport if the dose rate in any normally occupied part of the vehicle is likely to exceed 2 mrem/h; (j ) appropriate administrative and organizational m easures are taken, esp ecially in the case of notifiable packages Loss or theft of packages of radioactive m aterials in transport must be reported to the appropriate authorities and to the consignor as soon as possible. All necessary information must be provided to facilitate the recovery of the lost or stolen packages. In some countries, special regulations exist to safeguard shipments of strategic radioactive m aterials It is important for ca rrie r employees regularly engaged in radioactive m aterials transport to be instructed in the regulatory provisions involved in the storage and carriage of radioactive m aterials. Additionally, employees should receive some instruction in radiation hazards, radiation protection procedures, and procedures in the event of an accident involving radioactive m aterials. Wall charts are useful references to make employees aware of regulatory requirements and radiation hazards and protection m easures. Some consignors and regulatory authorities may be able to provide lectu rers, films, e tc., to a ssist with the instruction of c a rrie r personnel.

17 4 S E C T IO N I S E C T IO N I - IN T R O D U C T IO N ( ) PURPOSE AND SCOPE ( ) DEFINITIONS FOR THE PURPOSE OF THESE REGULATIONS ( ) Competent authority (112) 107. C arriers should check with their legal advisers and insurance underwriters concerning insurance requirements relating to the carriage of packages of radioactive m aterials before undertaking the carriage of such packages. Existing national leg islation and international conventions2 relating to nuclear liability in the transport of radioactive m aterials should also be considered The following information is offered for the assistance and guidance of "competent authorities" in respect of their role and responsibilities in the safe transport of radioactive m aterials The IAEA Regulations define "com petent authority" and assign to him the responsibility for receiving applications for approval, evaluating compliance, and issuing c e rtificates of compliance for special form m aterial, Type B(U) packages, Type B(M) packages and shipments, fissile packages and (in some cases) fissile shipments, and special arrangement shipments. In actual fact, the competent authority's responsibility may be much broader than this, including providing information and advice to packaging designers, shippers, carrie rs, etc., assisting in the preparation of national regulations for the transportation of radioactive m aterials, r e ceiving shipment notifications, organizing and administering emergency procedures, and administering regulations, approvals, 2 P a ris a n d V ie n n a C o n v e n tio n s.

18 S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid S E C T IO N I 5 DEFINITIONS FOR THE PURPOSE OF THESE REGULATIONS ( ) Competent authority (112) a n d i n f o r m a t i o n s e r v i c e s. T h e r o l e o f t h e c o m p e t e n t a u t h o r i t y i s f u r t h e r d i s c u s s e d e l s e w h e r e N a t i o n a l c o m p e t e n t a u t h o r i t i e s f o r a l l I A E A M e m b e r S t a t e s a r e l i s t e d i n a b o o k l e t e n t i t l e d " N a t i o n a l C o m p e t e n t A u t h o r i t i e s " [ 2 ]. T h i s b o o k l e t i s u p d a t e d a n n u a l l y. I t i s m o s t i m p o r t a n t t h a t c o m p e t e n t a u t h o r i t i e s k e e p t h e A g e n c y i n f o r m e d o f a n y c h a n g e s S o m e c o m p e t e n t a u t h o r i t i e s a n d / o r t h e i r t e c h n i c a l a d v i s e r s h a v e f o r m e d a n i n f o r m a l g r o u p, k n o w n a s t h e " R a d i o a c t i v e T r a n s p o r t S t u d y G r o u p ", w h i c h m e e t s a n n u a l l y t o d i s c u s s p r o b l e m s o f m u t u a l i n t e r e s t i n t h e n a t i o n a l a n d i n t e r n a t i o n a l a d m i n i s t r a t i o n o f t h e I A E A R e g u l a t i o n s. M e m b e r s h i p i n t h e g r o u p i n c l u d e s r e p r e s e n t a t i v e s o f C a n a d a, t h e F e d e r a l R e p u b l i c o f G e r m a n y, F r a n c e, I t a l y, P o l a n d, t h e S c a n d i n a v i a n c o u n t r i e s ( r o t a t i n g m e m b e r s h i p ), t h e U n i t e d K i n g d o m a n d t h e U n i t e d S t a t e s o f A m e r i c a. I t i s h o p e d t h a t o t h e r c o u n t r i e s i n v o l v e d i n t h e t r a n s p o r t o f r a d i o a c t i v e m a t e r i a l s w i l l i n t i m e j o i n t h i s g r o u p. I t s h o u l d b e e m p h a s i z e d t h a t t h e g r o u p h a s n o e x e c u t i v e p o w e r s, b u t d i s c u s s e s p r o b l e m s f r e e l y w i t h o u t c o m m i t m e n t t o p a r t i c u l a r s o l u t i o n s I n s o m e c o u n t r i e s, i t h a s b e e n f o u n d t o b e a d v a n t a g e o u s t o p r o v i d e a g u i d a n c e d o c u m e n t, s u c h a s a c h e c k l i s t, t o a s s i s t a p p l i c a n t s f o r s p e c i a l f o r m, p a c k a g e, a n d s h i p m e n t a p p r o v a l s i n s u b m i t t i n g t h e n e c e s s a r y i n f o r m a t i o n i n a c o n v e n i e n t f o r m. S u c h a g u i d a n c e d o c u m e n t i s a l s o o f v a l u e t o t h e 3 S e c tio n V III o f th is p u b l ic a ti o n.

19 6 S E C T IO N I S E C T IO N I - IN T R O D U C T IO N ( ) DEFINITIONS FOR THE PURPOSE OF THESE REGULATIONS ( ) Competent authority (112) c o m p e t e n t a u t h o r i t y i n t h a t i t a s s i s t s h i m i n e v a l u a t i n g t h e c o m p l e t e n e s s a n d a c c u r a c y o f s u b m i s s i o n s. E x a m p l e s o f s u c h c h e c k l i s t s a r e a v a i l a b l e f r o m t h e c o m p e t e n t a u t h o r i t i e s o f C a n a d a a n d t h e U n i t e d K i n g d o m T h e r e l a t i o n s h i p b e t w e e n t h e c o m p e t e n t a u t h o r i t y a n d t h e a p p l i c a n t m u s t b e c l e a r l y u n d e r s t o o d. I t i s t h e a p p l i c a n t ' s r e s p o n s i b i l i t y t o " m a k e t h e c a s e " t o d e m o n s t r a t e c o m p l i a n c e w i t h t h e R e g u l a t i o n s. T h e c o m p e t e n t a u t h o r i t y ' s r e s p o n s i b i l i t y i s t o ju d g e w h e t h e r o r n o t t h e s u b m i t t e d c a s e a d e q u a t e l y d e m o n s t r a t e s s u c h c o m p l i a n c e. H e m u s t b e f r e e t o c h e c k s t a t e m e n t s b y t h e a p p l i c a n t, e v e n, i f n e c e s s a r y, b y p e r f o r m a n c e o f c a l c u l a t i o n s o r t e s t s. H o w e v e r, t h e c o m p e t e n t a u t h o r i t y m u s t n o t " m a k e t h e c a s e " f o r t h e a p p l i c a n t, b e c a u s e t h i s w o u ld p u t t h e c o m p e t e n t a u t h o r i t y i n t h e d i f f i c u l t p o s i t i o n o f b e i n g b o t h " a d v o c a t e " a n d " j u d g e ". N e v e r t h e l e s s, t h i s d o e s n o t p r o h i b i t h i m f r o m p r o v i d i n g i n f o r m a l a d v i c e, w i t h o u t c o m m i t m e n t, a s t o w h a t i s l i k e l y t o b e a c c e p t a b l e E x p e r i e n c e h a s s h o w n t h a t m a n y a p p l i c a n t s m a k e t h e i r f i r s t s u b m i s s i o n i n t e r m s o f a s p e c i f i c a n d i m m e d i a t e n e e d, w h i c h i s r a t h e r n a r r o w i n s c o p e, a n d t h e n l a t e r m a k e s e v e r a l r e q u e s t s f o r a m e n d m e n t s t o t h e a p p r o v e d c e r t i f i c a t e a s t h e y a t t e m p t t o e x p a n d i t s s c o p e t o a p p l y i t t o o t h e r t y p e s o f m a t e r i a l a n d / o r s h i p m e n t. W h e n e v e r p o s s i b l e, a p p l i c a n t s s h o u l d b e e n c o u r a g e d t o m a k e t h e i r f i r s t s u b m i s s i o n a g e n e r a l c a s e, w h i c h w i l l a n t i c i p a t e a n d c o v e r t h e i r f u t u r e n e e d s. T h i s w i l l m a k e t h e " a p p l i c a t i o n a p p r o v a l " s y s t e m o p e r a t e m o r e e f f i c i e n t l y a n d w i l l r e s u l t i n m u c h l o w e r a p p r o v a l c o s t s t o t h e a p p l i c a n t. A d d i t i o n a l l y, i n s o m e

20 S E C T IO N I - IN T R O D U C T IO N ( ) S E C T IO N I 7 DEFINITIONS FOR THE PURPOSE OF THESE REGULATIONS ( ) Competent authority (112) c a s e s, i t i s m u t u a l l y a d v a n t a g e o u s f o r t h e p r o s p e c t i v e a p p l i c a n t a n d t h e c o m p e t e n t a u t h o r i t y t o d i s c u s s a p r o p o s e d a p p l i c a t i o n i n o u t l i n e b e f o r e i t i s f o r m a l l y s u b m i t t e d i n d e t a i l W h e r e a c o m p e t e n t a u t h o r i t y i s r e s p o n s i b l e f o r p r e p a r i n g n a t i o n a l r e g u l a t i o n s f o r t h e t r a n s p o r t a t i o n o f r a d i o a c t i v e m a t e r i a l s, h e s h o u l d a t t e m p t, t o t h e g r e a t e s t e x t e n t p o s s i b l e, t o m a k e t h o s e r e g u l a t i o n s u n i f o r m w i t h t h e I A E A - r e c o m m e n d e d s t a n d a r d. H e s h o u l d a l s o a t t e m p t t o a c h i e v e t h e m a x i m u m p o s s i b l e u n i f o r m i t y b e t w e e n t h e n a t i o n a l r e g u l a t i o n s f o r t h e d i f f e r e n t m o d e s o f t r a n s p o r t T h e I A E A R e g u l a t i o n s p r e s c r i b e t h e b a s i c i n f o r m a t i o n w h i c h m u s t a p p e a r o n c e r t i f i c a t e s o f a p p r o v a l a n d a c o m p e t e n t a u t h o r i t y i d e n t i f i c a t i o n m a r k s y s t e m. C o m p e t e n t a u t h o r i t i e s s h o u l d f o l l o w t h e s e p r e s c r i p t i o n s a s c l o s e l y a s p o s s i b l e t o a c h i e v e a n i n t e r n a t i o n a l u n i f o r m i t y o f c e r t i f i c a t i o n. I n a d d i t i o n t o t h e a p p l i c a b l e n a t i o n a l r e g u l a t i o n s a n d a n y r e l e v a n t i n t e r n a t i o n a l r e g u l a t i o n s s u c h a s t h o s e o f I M C O, I A T A, R I D, A D R o r A D N, e a c h c e r t i f i c a t e s h o u l d m a k e r e f e r e n c e t o t h e I A E A R e g u l a t i o n s o f t h e a p p r o p r i a t e e d i t i o n, b e c a u s e t h i s i s t h e i n t e r n a t i o n a l l y r e c o g n i z e d a n d k n o w n s t a n d a r d. T h e i n t e r n a t i o n a l v e h i c l e r e g i s t r a t i o n c o d e, w h i c h i s u s e d i n c o m p e t e n t a u t h o r i t y i d e n t i f i c a t i o n m a r k s, i s g i v e n i n t h e l i s t o f C o m p e t e n t N a t i o n a l A u t h o r i t i e s a l r e a d y m e n t i o n e d, w h i c h i s i s s u e d a n n u a l l y b y t h e I A E A M a n y o f t h e t y p e s o f p a c k a g i n g a n d s h i p m e n t w h i c h c o m e u n d e r t h e R e g u l a t i o n s d o n o t r e q u i r e a n y c o m p e t e n t a u t h o r i t y a p p r o v a l b e c a u s e o f t h e i r l o w h a z a r d

21 8 S E C T IO N I S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid DEFINITIONS FOR THE PURPOSE OF THESE REGULATIONS ( ) Competent authority (112) p o t e n t i a l. H o w e v e r, i t i s s t i l l t h e r e s p o n s i b i l i t y o f t h e c o m p e t e n t a u t h o r i t y t o e n s u r e t h a t a l l s u c h p a c k a g i n g s a n d s h i p m e n t s a r e i n c o m p l i a n c e w i t h t h e R e g u l a t i o n s. T h e b e s t w a y o f e n s u r i n g s u c h c o m p l i a n c e i s t o r e q u i r e t h e c o n s i g n o r t o k e e p r e c o r d s o f e v i d e n c e o f c o m p l i a n c e ( f o r e x a m p l e T y p e A p a c k a g e t e s t r e p o r t s, l o w s p e c i f i c a c t i v i t y m a t e r i a l a n d e x e m p t s h i p m e n t r e p o r t s ) s o t h a t t h e s e m a y b e s u b m i t t e d t o t h e c o m p e t e n t a u t h o r i t y o n r e q u e s t o r m a y b e i n s p e c t e d b y t h e c o m p e t e n t a u t h o r i t y A s i g n i f i c a n t p a r t ( i n s o m e c a s e s, m o r e t h a n h a l f ) o f t h e c o m p e t e n t a u t h o r i t y ' s t i m e m a y b e s p e n t i n p r o v i d i n g i n f o r m a t i o n t o p a c k a g i n g d e s i g n e r s, a p p l i c a n t s, c o n s i g n o r s, c a r r i e r s, t r a n s p o r t f a c i l i t y o p e r a t o r s, e t c. I t i s t h e r e f o r e i m p o r t a n t f o r t h e c o m p e t e n t a u t h o r i t y t o h a v e a n i n f o r m a t i o n s y s t e m t o f u l f i l s u c h i n f o r m a t i o n r e q u e s t s e f f i c i e n t l y a n d e f f e c t i v e l y. P a p e r s a n d i n f o r m a t i o n s h e e t s w h i c h o u t l i n e t h e b a s e s f o r t h e R e g u l a t i o n s, r e g u l a t o r y r e q u i r e m e n t s f o r t h e v a r i o u s t y p e s o f p a c k a g i n g s a n d s h i p m e n t s, a p p l i c a t i o n - f o r - a p p r o v a l c h e c k l i s t s, n o t i f i c a t i o n r e q u i r e m e n t s, e m e r g e n c y p r o c e d u r e s, e t c., w i l l b e u s e f u l. T h e c o m p e t e n t a u t h o r i t y s h o u l d a l s o m a k e a n e f f o r t t o d i s s e m i n a t e i n f o r m a t i o n b y s p e a k i n g t o i n d u s t r i a l a n d t r a d e a s s o c i a t i o n s a n d b y p r e p a r i n g a r t i c l e s f o r p u b l i c a t i o n i n t e c h n i c a l j o u r n a l s. T h e c o m p e t e n t a u t h o r i t y s h o u l d a l s o b e a w a r e o f, a n d h a v e r e f e r e n c e c o p i e s o f, o t h e r i n t e r n a t i o n a l r e g u l a t i o n s ( i. e. t h o s e o f I A T A, I M C O, R I D, A D R, A D N, e t c. ) a n d, i f p o s s i b l e, n a t i o n a l r e g u l a t i o n s T h e c o m p e t e n t a u t h o r i t y m a y a l s o b e r e s p o n s i b l e f o r o r g a n i z i n g a n d a d m i n i s t e r

22 S E C T IO N I 9 S E C T IO N I - IN T R O D U C T IO N ( ) DEFINITIONS FOR THE PURPOSE OF THESE REGULATIONS ( ) Competent authority (112) i n g e m e r g e n c y p r o c e d u r e s f o r a c c i d e n t s i n v o l v i n g t h e t r a n s p o r t a t i o n o f r a d i o a c t i v e m a t e r i a l s. S u c h p r o c e d u r e s a l r e a d y e x i s t i n m o s t m a j o r n u c l e a r s t a t e s a n d t h e c o m p e t e n t a u t h o r i t i e s o f t h o s e s t a t e s s h o u l d b e c o n t a c t e d f o r i n f o r m a t i o n T h e r e p o r t i n g o f s u c h a c c i d e n t s i s p a r t i c u l a r l y i m p o r t a n t o n b o t h t h e n a t i o n a l a n d i n t e r n a t i o n a l l e v e l s t o a c q u i r e r e l i a b l e i n f o r m a t i o n o n t h e e f f e c t i v e n e s s o f t h e I A E A R e g u l a t i o n s. F o r e x a m p l e, w h i l e t h e t e s t s r e q u i r e d b y S e c t i o n V I I o f t h e R e g u l a t i o n s p r o v i d e a r e a s o n a b l e r e p r e s e n t a t i o n o f t h e w o r s t c o n d i t i o n s t o w h i c h t h e p a c k a g e w i l l b e s u b j e c t e d d u r i n g t r a n s p o r t, t h e y d o n o t n e c e s s a r i l y c o v e r a l l t h e c o n d i t i o n s e n c o u n t e r e d i n n o r m a l h a n d l i n g o r i n e v e r y t y p e o f a c c i d e n t. H e n c e, t h e e x t e n t t o w h i c h r i p p i n g, c u t t i n g, s k i d d i n g, a b r a s i o n o r r o u g h h a n d l i n g h a s b e e n t a k e n i n t o a c c o u n t i n t h e d e s i g n, p a r t i c u l a r l y a s r e g a r d s a n y t h e r m a l p r o t e c t i o n p r o v i d e d, s h o u l d b e c o n s i d e r e d d u r i n g a p p r o v a l o f p a c k a g e d e s i g n T h e c o m p e t e n t a u t h o r i t y m u s t b e a w a r e o f o t h e r p r o v i s i o n s w h i c h m a y b e a s s o c i a t e d w i t h t h e R e g u l a t i o n s f o r t h e S a f e T r a n s p o r t o f R a d i o a c t i v e M a t e r i a l s. T h e s e r e l a t e d p r o v i s i o n s m a y i n c l u d e t h e i t e m s l i s t e d b e l o w. ( a ) T h e n a t i o n a l s y s t e m f o r l i c e n s i n g t h e d i s t r i b u t i o n, t r a n s f e r, a n d o w n e r s h i p o f r a d i o a c t i v e m a t e r i a l s. I n s o m e c o u n t r i e s a " r a d i o i s o t o p e l i c e n c e " i s u s e d t o r e q u i r e c o m p l i a n c e w i t h t h e r e g u l a t o r y r e q u i r e m e n t s f o r t h e p a c k a g i n g a n d s h i p m e n t o f r a d i o a c t i v e m a t e r i a l s. ( b ) T h e s y s t e m f o r c o n t r o l l i n g t h e i m p o r t a n d e x p o r t o f r a d i o a c t i v e m a t e r i a l s

23 10 SECTIO N I S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid DEFINITIONS FOR THE PURPOSE OF THESE REGULATIONS ( ) Competent authority (112) a s w e l l a s t h e p r o c e d u r e f o r c u s t o m s c l e a r a n c e o f s u c h m a t e r i a l s. ( c ) T h e r e q u i r e m e n t s f o r s a f e g u a r d i n g s t r a t e g i c r a d i o a c t i v e m a t e r i a l s w h i l e t h e y a r e i n t r a n s p o r t a n d s t o r a g e. (d ) R e l a t e d s a f e t y r e q u i r e m e n t s s u c h a s i n d u s t r i a l h e a l t h a n d s a f e t y c o d e s ( i n c l u d i n g r a d i a t i o n s a f e t y ), t r a n s p o r t v e h i c l e a n d o p e r a t o r s a f e t y s t a n d a r d s, e t c. LIMITATION OF EXPOSURE OF PERSONS TO RADIATION ( ) D u r i n g t r a n s p o r t o f r a d i o a c t i v e m a t e r i a l, t h e h u m a n i r r a d i a t i o n h a z a r d i s r e l a t e d t o t h e d o s e e q u i v a l e n t r a t e o f i o n i z i n g r a d i a t i o n, w h i c h m a y e i t h e r b e m e a s u r e d b y d o s i m e t r i c i n s t r u m e n t s o r c a l c u l a t e d T h e d o s e e q u i v a l e n t o f g a m m a, b e t a, a l p h a a n d n e u t r o n r a d i a t i o n o r a n y c o m b i n a t i o n o f t h e s e t y p e s o f i o n i z i n g r a d i a t i o n i s d e t e r m i n e d a s t h e s u m o f t h e a b s o r b e d d o s e s, D j, o f t h e d i f f e r e n t k i n d s o f r a d i a t i o n, m u l t i p l i e d b y t h e c o r r e s p o n d i n g q u a l i t y f a c t o r s, ( Q F ) j, a n d t h e d i s t r i b u t i o n f a c t o r s, ( D F ) ;, i. e w h e r e : ( Q F ) ;, t h e q u a l i t y f a c t o r, i s t h e v a l u e f o r t r a n s l a t i n g t h e a b s o r b e d d o s e D ; o f t h e d i f f e r e n t t y p e s o f i o n i z i n g r a d i a t i o n i n t o t h e d o s e e q u i v a l e n t. T h e v a l u e s ( Q F ) ; a r e g i v e n i n B a s i c S a f e t y S t a n d a r d s f o r R a d i a t i o n P r o t e c t i o n [ 1 ] ; a n d ( D F ) ;, t h e d i s t r i b u t i o n f a c t o r, i s t h e v a l u e a l l o w i n g f o r u n e v e n d i s t r i b u t i o n o f r a d i o a c t i v e i s o t o p e s i n t h e h u m a n

24 S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid SECTIO N I 11 LIMITATION OF EXPOSURE OF PERSONS TO RADIATION ( ) o r g a n i s m. T h i s f a c t o r i s n o t t a k e n i n t o a c c o u n t w h e n d e t e r m i n i n g t h e e x t e r n a l r a d i a t i o n l e v e l I n p r i n c i p l e, t h e r a d i a t i o n l e v e l i n t h e o c c u p i e d s p a c e s i n a v e h i c l e s h o u l d n o t e x c e e d 2 m r e m / h. I n t h e s p e c i a l c a s e w h e n t h e t r a n s p o r t i s c a r r i e d o u t i n " f u l l l o a d " c o n d i t i o n s, t h e r a d i a t i o n l e v e l, a f t e r a c c e p t a n c e b y t h e q u a l i f i e d p e r s o n, m a y e x c e e d 2 m r e m / h. T r a n s p o r t w o r k e r s s h o u l d b e p r o v i d e d w i t h p e r s o n a l d o s i m e t e r s w h e n t h e r e i s a p o s s i b i l i t y t h a t t h e d o s e t h e y r e c e i v e w i l l e x c e e d t h r e e t e n t h s o f t h e m a x i m u m p e r m i s s i b l e a n n u a l d o s e f o r r a d i a t i o n w o r k e r s a n d w h e n t h e r a d i a t i o n l e v e l i n a n o c c u p i e d s p a c e d o e s n o t e x c e e d 2 m r e m / h b u t t h e w e e k l y e x p o s u r e t i m e o f a p e r s o n a v e r a g e d o v e r a c a l e n d a r q u a r t e r e x c e e d s 1 5 h o u r s I n s u c h c a s e s p e r s o n s o c c u p y i n g t h e s e s p a c e s s h a l l b e p r o v i d e d w i t h s p e c i a l h e a l t h s u p e r v i s i o n a n d m o n i t o r i n g d e v i c e s. M o n i t o r i n g d e v i c e s m a y b e u n n e c e s s a r y w h e n t h e c a r r i e r o p e r a t e s a s c h e m e o f w o r k f o r w h i c h r e c o r d s a r e k e p t o f t h e m a x i m u m r e c o r d e d d o s e r a t e s i n t h e o c c u p i e d s p a c e o f a v e h i c l e a n d o f t h e d r i v e r ' s o c c u p a n c y t i m e. I n s u c h c a s e s, i t w o u ld b e n e c e s s a r y t o k n o w t h e r a d i a t i o n d o s e r e c e i v e d b y t h e d r i v e r i n t h e c o u r s e o f h i s e m p l o y m e n t o t h e r t h a n t h a t r e c e i v e d w h e n d r i v i n g. GENERAL ACCIDENT PROVISIONS (149) G E N E R A L B e f o r e u n d e r t a k i n g t h e c a r r i a g e o f r a d i o a c t i v e m a t e r i a l s, c a r r i e r s s h o u l d b e a w a r e o f p r o c e d u r e s t o b e f o l l o w e d i n t h e e v e n t o f a t r a n s p o r t a c c i d e n t i n v o l v i n g s u c h m a t e r i a l s.

25 12 S E C T IO N I S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid GENERAL ACCIDENT PROVISIONS (149) M o s t c o u n t r i e s h a v e p r e p a r e d e m e r g e n c y p r o c e d u r e s t o c o p e w i t h t r a n s p o r t a t i o n a c c i d e n t s i n v o l v i n g r a d i o a c t i v e m a t e r i a l s. I n t h e s e p r o c e d u r e s, o r g a n i z a t i o n s s u c h a s p o l i c e a n d f i r e d e p a r t m e n t s a r e i n f o r m e d o f t h e b a s i c a c t i o n s r e q u i r e d a n d h a v e a c c e s s t o r a d i a t i o n e x p e r t s e q u i p p e d t o a s s i s t a t t h e s c e n e o f t h e a c c i d e n t. M o s t n a t i o n a l e m e r g e n c y p r o c e d u r e s a r e o r g a n i z e d o n a t w o - s t a g e b a s i s : t h e f i r s t s t a g e b e i n g t o h a v e t h e p l a c e o f t h e a c c i d e n t i n v e s t i g a t e d b y a r a d i a t i o n e x p e r t e q u i p p e d w i t h r a d i a t i o n s u r v e y i n s t r u m e n t s c a p a b l e o f i d e n t i f y i n g a n y h a z a r d p r e s e n t, a n d t h e s e c o n d s t a g e t o p r o v i d e t r a i n e d p e r s o n n e l a n d e q u i p m e n t t o r e m o v e u n s h i e l d e d r a d i a t i o n s o u r c e s a n d c o n t a m i n a t i o n s h o u l d t h e s e b e p r e s e n t T h e c a r r i e r s h o u l d b e a w a r e o f t h e n a m e s a n d t e l e p h o n e n u m b e r s o f t h e e m e r g e n c y r a d i a t i o n e x p e r t s i n h i s a r e a o f o p e r a t i o n o r o f a p r o c e d u r e f o r o b t a i n i n g t h e i r a s s i s t a n c e F o r a c a r r i e r w h o m a y b e t e m p o r a r i l y w i t h o u t e x p e r t a d v i c e a n d / o r a s s i s t a n c e, b a s i c a c t i o n s t o b e t a k e n i n c l u d e t h o s e l i s t e d b e l o w. ( a ) R e s c u i n g i n j u r e d ( a n d a d v i s i n g a m b u l a n c e a n d h o s p i t a l p e r s o n n e l o f p o s s i b l e r a d i o a c t i v e c o n t a m i n a t i o n ). ( b ) E v a c u a t i n g t h e a r e a ( s t a y i n g u p w in d a n d a t l e a s t 1 5 m d i s t a n t ) a n d i s o l a t i n g i t b y e r e c t i n g b a r r i e r s o r o t h e r w i s e p r e v e n t i n g t h e e n t r y o f u n a u t h o r i z e d p e r s o n s. ( c ) C a l l i n g p o l i c e a n d r e q u e s t i n g t h e i r a s s i s t a n c e i n s e c u r i n g e x p e r t h e l p, f o r e x a m p l e a s p r o v i d e d b y a n a t i o n a l s c h e m e. (d ) C a l l i n g e m e r g e n c y c o n t a c t a n d / o r d e s i g n a t e d r a d i a t i o n e x p e r t a n d r e p o r t i n g

26 S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid S E C T IO N I 13 GENERAL ACCIDENT PROVISIONS (149) d e t a i l s o f a c c i d e n t a n d p a r t i c u l a r s o f r a d i o a c t i v e c o n s i g n m e n t. R e q u e s t i n g a d v i c e a n d a s s i s t a n c e. ( e ) I d e n t i f y i n g p e r s o n s w h o m a y h a v e b e e n i n t h e i m m e d i a t e a r e a a t t h e t i m e o f t h e a c c i d e n t a n d r e q u e s t i n g t h e m t o r e m a i n i n a d e s i g n a t e d a r e a f o r c o n t a m i n a t i o n c h e c k s. R e m o v i n g a n d p l a c i n g i n p l a s t i c b a g s c l o t h i n g k n o w n t o b e o r s u s p e c t e d o f b e i n g c o n t a m i n a t e d. ( f ) S t a n d i n g b y u n t i l a r r i v a l o f r a d i a t i o n e x p e r t. A d v i s i n g c o n s i g n o r a n d g o v e r n m e n t a l r a d i a t i o n p r o t e c t i o n a u t h o r i t i e s o f a c c i d e n t. P r o v i d i n g e x p e r t w i t h a l l a v a i l a b l e i n f o r m a t i o n a n d f o l l o w i n g h i s i n s t r u c t i o n s. E M E R G E N C I E S A c c i d e n t s r e s u l t i n g i n t h e e s c a p e o f r a d i o a c t i v e s u b s t a n c e s i n t o t h e e n v i r o n m e n t o r i n t h e i r r a d i a t i o n o f p e o p l e a n d o t h e r l i v i n g b e i n g s m a y o c c u r d u e t o b r e a k a g e o f p a c k a g e s o f r a d i o a c t i v e m a t e r i a l s i n v o l v e d i n a c r a s h, w r e c k o r f i r e, o r d u e t o l e a k a g e f r o m v a r i o u s c a u s e s. E m e r g e n c y p l a n s s h o u l d b e p r e p a r e d i n a d v a n c e a n d b e s u f f i c i e n t l y b r o a d t o c o v e r u n f o r e s e e n o r i m p r o b a b l e a c c i d e n t s a s w e l l a s t h o s e t h a t a r e c o n s i d e r e d c r e d i b l e A p p r o p r i a t e o r g a n i z a t i o n s h o u l d b e a t h a n d t o u n d e r t a k e t h e a d m i n i s t r a t i v e a n d t e c h n i c a l m e a s u r e s n e c e s s a r y t o a s s e s s t h e r a d i a t i o n a n d o t h e r h a z a r d s r e s u l t i n g f r o m t h e a c c i d e n t a n d e n s u r e t h a t a p p r o p r i a t e m e a s u r e s a r e u n d e r t a k e n t o o v e r c o m e a n d m i n i m i z e i t s c o n s e q u e n c e s. T h e s e m e a s u r e s s h o u l d i n c l u d e t h o s e l i s t e d b e l o w. ( a ) I s o l a t i o n o f t h e p l a c e o f a c c i d e n t s u c h a s b y f e n c i n g t h e a f f e c t e d p l a c e t o

27 14 S E C T IO N I S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid GENERAL ACCIDENT PROVISIONS (149) p r e v e n t a l l c o n t a c t o f p e r s o n s w i t h a n y l o o s e r a d i o a c t i v e m a t e r i a l. N o - o n e s h a l l b e a l l o w e d t o e n t e r o r t o r e m a i n w i t h i n t h e i s o l a t e d p l a c e u n t i l q u a l i f i e d p e r s o n s a r e a v a i l a b l e t o c h e c k r a d i a t i o n h a z a r d s a n d s u p e r v i s e t h e h a n d l i n g o r s a l v a g e. T h e c o n s i g n o r a n d a p p r o p r i a t e a u t h o r i t i e s s h a l l b e n o t i f i e d i m m e d i a t e l y. ( b ) A l l p e r s o n s w h o m a y h a v e b e c o m e c o n t a m i n a t e d w i t h r a d i o a c t i v e m a t e r i a l s s h a l l b e s u b j e c t t o a p p r o p r i a t e c o n t r o l a n d e x a m i n a t i o n m e a s u r e s. ( c ) R e s c u e o p e r a t i o n s o r f i r e f i g h t i n g s h o u l d b e c a r r i e d o u t b y q u a l i f i e d p e r s o n s a n d w i t h a p p r o p r i a t e e q u i p m e n t. ( d ) A n y c o n v e y a n c e, b u i l d i n g, p l a c e, e q u i p m e n t o r p a r t t h e r e o f w h i c h h a s b e c o m e c o n t a m i n a t e d a s a r e s u l t o f a n a c c i d e n t i n t h e c o u r s e o f t r a n s p o r t o f r a d i o a c t i v e m a t e r i a l s s h a l l b e d e c o n t a m i n a t e d b y q u a l i f i e d p e r s o n s a s s o o n a s p o s s i b l e a n d b e f o r e i t i s p u t b a c k i n t o s e r v i c e. ( e ) W h e n n e c e s s a r y, a d d i t i o n a l s t e p s s u c h a s p e r i o d i c m o n i t o r i n g o f t h e a f f e c t e d a r e a s h o u l d b e u n d e r t a k e n t o p r o v i d e g u i d e l i n e s f o r a d d i t i o n a l a c t i o n s t o o v e r c o m e r a d i a t i o n h a z a r d s. ( f ) A n a c c i d e n t r e p o r t s h o u l d b e p r e p a r e d a n d s u b m i t t e d t o t h e c o m p e t e n t a u t h o r i t y b y t h e r e s p o n s i b l e p a r t y o n t h e c a u s e s o f t h e a c c i d e n t, t h e e f f e c t i v e n e s s o f t h e m e a s u r e s u n d e r t a k e n t o o v e r c o m e i t s c o n s e q u e n c e s, a n d o t h e r r e l e v a n t d a t a w h i c h m a y b e u s e f u l t o e v a l u a t e t h e f a c t s c o n c e r n i n g t h e a c c i d e n t o r h e l p f u l i n i m p r o v i n g a c c i d e n t p r e v e n t i o n o r m e a s u r e s t o d e a l w i t h a c c i d e n t s. ( g ) W h e n t h e c o n s e q u e n c e s o f a n a c c i d e n t a r e e x t e n s i v e, s u c h a s w h e n a p e r s o n o r p e r s o n s r e c e i v e r a d i a t i o n d o s e s i n e x c e s s

28 S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid S E C T IO N I 15 GENERAL ACCIDENT PROVISIONS (149) o f a c c e p t e d s t a n d a r d s, o r w h e n m a n y p e o p l e a r e i n v o l v e d, p r o v i s i o n s s h o u l d b e m a d e f o r r e v i e w o f t h e r e l e v a n t f a c t s o f t h e a c c i d e n t b y t h e c o m p e t e n t a u t h o r i t y. ( h ) T h e r e s h o u l d b e p e r i o d i c r e v i e w o f a c c i d e n t h i s t o r i e s b y t h e c o m p e t e n t a u t h o r i t y t o a s c e r t a i n w h e t h e r a c c e p t e d p r o c e d u r e s a n d m e a s u r e s u n d e r t a k e n i n t h e e v e n t o f a c c i d e n t s a r e p r o v i d i n g a c c e p t a b l e p r o t e c t i o n o f t h e p u b l i c. E M E R G E N C Y T E A M S W h e n a c o u n t r y i s u s i n g r a d i o a c t i v e m a t e r i a l s f o r a v a r i e t y o f p u r p o s e s, e x p e r i e n c e h a s s h o w n t h e n e e d t o i n t r o d u c e, o n a n a t i o n a l b a s i s, a s c h e m e f o r p r o v i s i o n o f a s s i s t a n c e i n t h e e v e n t o f e m e r g e n c y. F o r a n y s u c h s c h e m e, t h e c o u n t r y i s u s u a l l y d i v i d e d i n t o z o n e s a n d f o r e a c h z o n e a s o u r c e o f a s s i s t a n c e, f o r e x a m p l e a h e a l t h p h y s i c i s t a t a h o s p i t a l, a h e a l t h p h y s i c s a n d c l e a n - u p t e a m f r o m a n u c l e a r e s t a b l i s h m e n t, i s s p e c i f i e d. W h e n s u c h a n a t i o n a l s c h e m e e x i s t s, i t i s d e s i r a b l e, w h e n d e a l i n g w i t h s h i p m e n t s o f t h e t y p e s r e f e r r e d t o i n p a r a o f t h e R e g u l a t i o n s, t h a t c o n s i d e r a t i o n b e g i v e n t o t h e p r e p a r a t i o n o f a l e a f l e t g i v i n g b a s i c i n f o r m a t i o n o n t h e p a c k a g e a n d i t s c o n t e n t s a n d a n y s p e c i a l f e a t u r e s s u c h a s v e n t i n g v a l v e s. C o p i e s s h o u l d b e s e n t i n a d v a n c e t o t h o s e r e s p o n s i b l e f o r e m e r g e n c y a s s i s t a n c e i n e a c h z o n e t h r o u g h w h i c h t h e c o n s i g n m e n t i s t o p a s s W h e n t h e e m e r g e n c y t e a m s a r r i v e a t t h e s i t e o f a n a c c i d e n t, t h e y m a y f i n d a n y o f t h r e e p o s s i b l e s i t u a t i o n s, w h i c h a r e d e s c r i b e d b e l o w. ( a ) T h e a c c i d e n t h a s n o t a f f e c t e d t h e r a d i o a c t i v e m a t e r i a l, i n w h i c h c a s e i t i s

29 16 S E C T IO N I S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid GENERAL ACCIDENT PROVISIONS (149) s u f f i c i e n t t o c o n f i r m t h i s a n d t o a l l o w t h e t r a n s p o r t t o p r o c e e d. ( b ) T h e a c c i d e n t i s s t i l l d e v e l o p i n g ( e. g. i n t h e c a s e o f a f i r e ). ( i ) t h e r e i s s t i l l a p o s s i b i l i t y o f i s o l a t i n g t h e p a c k a g e o r t h e l o a d f r o m t h e f i r e ; t h i s s h o u l d b e d o n e a n d i t s h o u l d t h e n b e a s c e r t a i n e d w h e t h e r t h e p a c k a g e s o r l o a d h a v e b e e n d a m a g e d ; ( i i ) t h e p a c k a g e s o r l o a d a r e d i r e c t l y i n v o l v e d i n t h e f i r e. I n t h i s c a s e i t i s n e c e s s a r y t o d o e v e r y t h i n g p o s s i b l e t o e x t i n g u i s h t h e f i r e a n d l a t e r t o c o n f i r m t h a t t h e p a c k a g e s o r l o a d h a v e n o t b e e n d a m a g e d. ( c ) T h e a c c i d e n t i s o v e r a n d i t h a s a f f e c t e d t h e r a d i o a c t i v e m a t e r i a l. I n t h i s c a s e i t i s p o s s i b l e t o m a k e s o m e s u g g e s t i o n s b a s e d o n a w h o l e - b o d y r e f e r e n c e d o s e T w o d i f f e r e n t p o p u l a t i o n g r o u p s a r e l i k e l y t o b e i n v o l v e d i n t h e a c c i d e n t : o n e w h i c h i s o c c a s i o n a l l y i n t h e a r e a, i n c l u d i n g p e r s o n s w h o w o r k t h e r e ; t h e o t h e r i n c l u d i n g p e r s o n s l i v i n g i n t h e a r e a A s r e g a r d s t h e f o r m e r g r o u p, e v a c u a t i o n s h o u l d b e e f f e c t e d t o a s g r e a t a d i s t a n c e a s p o s s i b l e f r o m t h e a c c i d e n t a r e a ; t h e r e f e r e n c e v a l u e r e g a r d i n g i n d i v i d u a l a b s o r b e d d o s e m a y b e 3 r e m, t h a t i s, a p p r o x i m a t e l y h a l f t h e m a x i m u m p e r m i s s i b l e a n n u a l d o s e f o r w o r k e r s, a n d, c o n s e q u e n t l y, e v a c u a t i o n d i s t a n c e s s h o u l d b e w o r k e d o u t o n t h e b a s i s o f t h a t v a l u e, t a k i n g i n t o a c c o u n t c o n t a m i n a t i o n d u e t o i n h a l e d a i r a n d e x t e r n a l i r r a d i a t i o n.

30 S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid S E C T IO N I 17 GENERAL ACCIDENT PROVISIONS (149) R e g a r d i n g t h e l a t t e r g r o u p, t h r e e d i f f e r e n t k i n d s o f r i s k s h o u l d b e c o n s i d e r e d a n d a r e d e s c r i b e d b e l o w. ( 1 ) E x t e r n a l r a d i a t i o n. T h i s k i n d o f r i s k i s i m p o r t a n t i n c l o s e v i c i n i t y t o t h e a c c i d e n t. ( 2 ) I n t e r n a l c o n t a m i n a t i o n d u e t o i n h a l a t i o n o f a i r b o r n e r a d i o a c t i v e c o n t a m i n a n t s r e l e a s e d f r o m t h e p a c k a g e. T h i s k i n d o f r i s k m i g h t e x t e n d t o a r e a s w e l l a w a y f r o m t h e a c c i d e n t a r e a. ( 3 ) I n t e r n a l c o n t a m i n a t i o n f o l l o w i n g i n g e s t i o n o f c o n t a m i n a t e d w a t e r o r f o o d s t u f f T h e f i r s t t w o r i s k s m a y r e q u i r e e v a c u a t i o n o f t h e a r e a ; h o w e v e r, a s t h i s e n t a i l s o t h e r r i s k s, b o t h a d v a n t a g e s a n d d i s a d v a n t a g e s s h o u l d b e w e i g h e d b e f o r e d e c i s i o n s a r e t a k e n I t s h o u l d b e r e m e m b e r e d t h a t o t h e r s t e p s m a y b e t a k e n t o l o w e r t h e r a d i a t i o n d o s e r i s k w h e r e e v a c u a t i o n i s n o t a d v i s a b l e, f o r e x a m p l e : c o n f i n e m e n t t o t h e h o m e w i t h d o o r s a n d w i n d o w s c l o s e d ; a d m i n i s t r a t i o n o f s p e c i a l s u b s t a n c e s s u c h a s s t a b l e i o d i d e s ; c u t t i n g o f f d r i n k i n g w a t e r a n d f o o d s t u f f s. C O N T A M I N A T I O N O F T H E A I R W I T H O U T S I G N I F I C A N T E X T E R N A L R A D I A T I O N I f s i g n i f i c a n t c o n t a m i n a t i o n o f t h e a i r c a n b e p r e s u m e d a f t e r a n a c c i d e n t, a l l p e r s o n s w h o a r e n o t a c t i v e l y e n g a g e d i n t h e r e m e d i a l a c t i o n s s h a l l b e e v a c u a t e d f r o m t h e a r e a a s s o o n a s p o s s i b l e. T h e p e r s o n s e n g a g e d i n t h e r e m e d i a l a c t i o n s s h o u l d,

31 18 SECTIO N I S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid GENERAL ACCIDENT PROVISIONS (149) w h e r e p o s s i b l e, b e e q u i p p e d w i t h r e s p i r a t o r s a n d p r o t e c t i v e c l o t h i n g. A m a x i m u m a l l o w a b l e e x p o s u r e t i m e f o r p e r s o n s n o t p r o v i d e d w i t h p r o t e c t i v e d e v i c e s c a n b e c a l c u l a t e d f r o m t h e f o l l o w i n g f o r m u l a w h i c h i s b a s e d o n t h e p r e m i s e t h a t t h e i n t a k e d u r i n g t h a t t i m e s h o u l d n o t e x c e e d o n e h a l f o f t h e m a x i m u m p e r m i s s i b l e a n n u a l i n t a k e f o r r a d i a t i o n w o r k e r s : M P I X 1 0 3, max C X 2. 5 X r S w h e r e : M P I i s t h e m a x i m u m p e r m i s s i b l e a n n u a l i n t a k e i n m i c r o c u r i e s ; C i s t h e e s t i m a t e d c o n c e n t r a t i o n i n m i c r o c u r i e s p e r c m 3. T h e M P I v a l u e s f o r s i n g l e r a d i o n u c l i d e s a n d f o r u n k n o w n o r p a r t l y k n o w n m i x t u r e s a r e g i v e n i n t h e I A E A B a s i c S a f e t y S t a n d a r d s f o r R a d i a t i o n P r o t e c t i o n. C O N T A M I N A T I O N O F T H E A I R W I T H S I G N I F I C A N T E X T E R N A L R A D I A T I O N A m a x i m u m a l l o w a b l e e x p o s u r e t i m e f o r p e r s o n s n o t p r o v i d e d w i t h p r o t e c t i v e d e v i c e s c a n b e c a l c u l a t e d f r o m t h e f o l l o w i n g f o r m u l a w h i c h i s b a s e d o n t h e p r e m i s e t h a t t h e i n t a k e s h o u l d n o t e x c e e d o n e h a l f o f t h e m a x i m u m p e r m i s s i b l e a n n u a l i n t a k e f o r r a d i a t i o n w o r k e r s a n d t h a t t h e w h o l e - b o d y r a d i a t i o n d o s e e q u i v a l e n t f r o m e x t e r n a l r a d i a t i o n s h o u l d n o t e x c e e d 3 r e m : Vax = x + Y hours

32 S E C T IO N I - IN T R O D U C T IO N ( ) S E C T IO N I 19 GENERAL ACCIDENT PROVISIONS (149) w h e r e : X i s t h e e s t i m a t e d d o s e - e q u i v a l e n t r a t e f r o m e x t e r n a l r a d i a t i o n ; C O N T A M I N A T I O N O F P E R S O N S I f t h e r e i s r e a s o n t o b e l i e v e t h a t p e r s o n s a r e c o n t a m i n a t e d, t h e y s h o u l d b e i s o l a t e d a n d d e c o n t a m i n a t e d, w i t h t h e h e l p, i f p o s s i b l e, o f a m e d i c a l o f f i c e r w h o i s e x p e r i e n c e d w i t h w o r k i n v o l v i n g r a d i o a c t i v e m a t e r i a l s. C a r e m u s t b e t a k e n d u r i n g t h e d e c o n t a m i n a t i o n o p e r a t i o n s n o t t o s p r e a d t h e c o n t a m i n a t i o n. F o r e x a m p l e, c o n t a m i n a t e d c l o t h i n g s h o u l d b e p l a c e d i n s e a l e d b a g s. C O N T A M I N A T I O N O F O B J E C T S A N D A R E A S I f t h e r e i s r e a s o n t o b e l i e v e t h a t o b j e c t s o r a r e a s a r e c o n t a m i n a t e d, t h e y s h o u l d b e c o l l e c t e d a n d / o r i s o l a t e d, r e s p e c t i v e l y, t o p r e v e n t a n y b o d y f r o m a p p r o a c h i n g t h e m. A p p r o p r i a t e a c t i o n s h o u l d b e t a k e n t o i m p o u n d c o n t a m i n a t e d f o o d s t u f f s. S P E C I A L F O R M R A D I O A C T I V E M A T E R I A L I n t h e e v e n t o f a s e v e r e a c c i d e n t, s p e c i a l f o r m r a d i o a c t i v e m a t e r i a l o f a c t i v i t y A j m a y e s c a p e f r o m a T y p e A p a c k a g e a n d h a v e t o b e p u t i n t o o t h e r p a c k a g i n g d u r i n g t h e s u b s e q u e n t e m e r g e n c y o p e r a t i o n. T o m o v e t h e g a m m a s o u r c e i n s u c h a c a s e, o n e w o u l d u s e a r e m o t e h a n d l i n g d e v i c e a t l e a s t 1 m l o n g.

33 20 S E C T IO N I S E C T IO N I - IN T R O D U C T IO N ( ) This publication is no longer valid GENERAL ACCIDENT PROVISIONS (149) T h e r a d i a t i o n l e v e l a t a n y p o i n t o n t h e s u r f a c e o f a s p h e r e o f r a d i u s 1 m s u r r o u n d i n g a n a p p r o x i m a t e l y p o i n t s o u r c e o f a c t i v i t y A i C i i s 9 r e m / h. T h i s f o l l o w s f r o m t h e d e f i n i t i o n o f A w h i c h, f o r g a m m a r a y e m i t t e r s, c o r r e s p o n d s t o a r a d i a t i o n l e v e l o f 1 r e m / h ' a t a d i s t a n c e o f 3 m E x p e r i e n c e h a s s h o w n t h a t t h e t i m e t a k e n t o m o v e a s o u r c e o f e x t e r n a l r a d i a t i o n w i t h r e m o t e h a n d l i n g e q u i p m e n t o f 1 - m l e n g t h s h o u l d n o t e x c e e d 1 m i n. A h i g h f a c t o r o f s a f e t y m a y b e i n t r o d u c e d b y i n c r e a s i n g t h i s e s t i m a t e d t i m e t o 5 m i n T h e d o s e r e c e i v e d b y a p e r s o n a t a d i s t a n c e o f 1 m i n m o v i n g a g a m m a - r a y - e m i t t i n g s o u r c e o f a c t i v i t y A -l c u r i e s m a y t h e r e f o r e b e t a k e n t o b e 5 D = 9 X 777 = r e m T h u s, w h e n m o v i n g o n e r a d i a t i o n s o u r c e t h a t h a s b e e n r e l e a s e d f r o m a T y p e A p a c k a g e u n d e r a c c i d e n t c o n d i t i o n s, t h e d o s e r e c e i v e d b y t h e w o r k e r n e e d n o t e x c e e d o n e q u a r t e r o f t h e m a x i m u m a l l o w a b l e s i n g l e d o s e o f 3 r e m I f, d u r i n g a n a c c i d e n t, m o r e t h a n o n e T y p e A p a c k a g e i s d a m a g e d, t h e t i m e f o r r e m o v i n g e a c h s o u r c e s h o u l d b e r e s t r i c t e d i n s u c h a w a y t h a t t h e i n d i v i d u a l r a d i a t i o n d o s e d o e s n o t e x c e e d 3 r e m. F o r e x a m p l e, i f t w e n t y u n s h i e l d e d s o u r c e s h a v e t o b e r e m o v e d, t h e p e r s o n w h o d o e s t h e w o r k s h o u l d n o t b e e n g a g e d w i t h e a c h s o u r c e l o n g e r t h a n o n e m i n.

34 S E C T IO N I 21 SECTION I - INTRODUCTION ( ) R E F E R E N C E S [1] INTERNATIONAL ATOMIC ENERGY AGENCY, Basic Safety Standards for Radiation Protection 1967 Edition, Safety Series N o.9, IAEA, Vienna (1967) STI/PUB/147. [21 INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for the Safe Transport o f Radioactive Materials National Competent Authorities List No. 5 (September 1972).

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36 SECTION II SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) G E N E R A L S A F E T Y P R I N C I P L E S T h e f o l l o w i n g S e c t i o n e x a m i n e s s o m e o f t h e b a s i c p r i n c i p l e s r e l a t i v e t o T y p e A a n d B p a c k a g i n g s a n d p a c k a g e s a n d m a y b e o f i n t e r e s t p r i m a r i l y t o t h e d e s i g n e r, a p p l i c a n t f o r a p p r o v a l, c o m p e t e n t a u t h o r i t y a n d c o n s i g n o r P r o v i s i o n o f s a f e t y, w h a t e v e r t h e f i e l d o f i n t e r e s t, m a y b e e x p r e s s e d a s f o l l o w s : o v e r a l l s a f e t y = s a f e t y p r o v i d e d b y d e s i g n + s a f e t y p r o v i d e d b y o p e r a t i o n a l c o n t r o l. I n m a n y w a y s d e s i g n s a f e t y i s p r e f e r a b l e t o o p e r a t i o n a l s a f e t y, b e c a u s e t h e f o r m e r r e l i e s t o a m u c h l e s s e r d e g r e e o n h u m a n i n t e r v e n t i o n a n d i s l e s s i n f l u e n c e d b y t h e a s s o c i a t e d h u m a n e r r o r s a n d o m i s s i o n s. H e n c e, a s f a r a s p r a c t i c a l, t h e I A E A R e g u l a t i o n s a i m t o a c h i e v e t h e r e q u i s i t e s a f e t y s t a n d a r d t h r o u g h d e s i g n, t h u s r e d u c i n g t h e o p e r a t i o n a l c o n t r o l r e q u i r e m e n t s t o a m i n i m u m D e s i g n s a f e t y i s l a r g e l y p r o v i d e d b y t h e p a c k a g i n g ; t h e R e g u l a t i o n s p u t t h e p r i m a r y e m p h a s i s o n t h i s a r e a. T h o r o u g h i m p l e m e n t a t i o n o f p a c k a g i n g d e s i g n p r i n c i p l e s a n d p a c k a g e p e r f o r m a n c e c r i t e r i a i s n e c e s s a r y t o a c h i e v e d e s i g n s a f e t y. T h e d e s i g n e r s h o u l d d o e v e r y t h i n g p r a c t i c a b l e t o e n s u r e t h a t s a f e t y f e a t u r e s ( e. g. f a s t e n e r s, a n e u t r o n 23

37 24 SEC TIO N II SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) p o i s o n ) a r e d e s i g n e d t o p r e v e n t o r r e d u c e o p e r a t i o n a l e r r o r s, a n d h e s h o u l d p r o v i d e o p e r a t i n g a n d m a i n t e n a n c e i n s t r u c t i o n s r e l e v a n t t o s u c h f e a t u r e s w h e r e v e r p r a c t i c a b l e O p e r a t i o n a l s a f e t y i s p r o v i d e d b y t h e a c t i o n s p e r f o r m e d b y c o n s i g n o r a n d c a r r i e r. F o r e x a m p l e, t h e c o n s i g n o r p r e p a r e s t h e p a c k a g e f o r t r a n s p o r t i n t h e p r e s c r i b e d m a n n e r ( i n c l u d i n g l i m i t a t i o n o f c o n t e n t s, s h i e l d i n g a n d c o n t a i n m e n t p e r f o r m a n c e c h e c k s, m a r k i n g a n d l a b e l l i n g, c o n s i g n o r c e r t i f i c a t i o n, e t c. ) a n d t h e c a r r i e r o b s e r v e s r e q u i r e m e n t s r e l a t i n g t o t r a n s p o r t i n d e x l i m i t a t i o n, s e g r e g a t i o n, p l a c a r d i n g, e t c T h e d e g r e e o f r e l i a n c e o n t h e d e s i g n s a f e t y a n d o p e r a t i o n a l s a f e t y c o m p o n e n t s m a y v a r y f o r d i f f e r e n t t y p e s o f s h i p m e n t. F o r e x a m p l e, t o e n s u r e c r i t i c a l i t y s a f e t y i n t h e s h i p m e n t o f» f i s s i l e m a t e r i a l s, F i s s i l e C l a s s I p a c k a g e s r e l y c o m p l e t e l y o n d e s i g n s a f e t y, F i s s i l e C l a s s I I p a c k a g e s r e l y o n b o t h d e s i g n a n d o p e r a t i o n a l c o n t r o l s a f e t y, a n d F i s s i l e C l a s s I I I p a c k a g e s m a y r e l y a l m o s t c o m p l e t e l y o n o p e r a t i o n a l c o n t r o l s a f e t y. T R A N S P O R T E N V I R O N M E N T T h e R e g u l a t i o n s d e f i n e t h e t r a n s p o r t e n v i r o n m e n t i n t e r m s o f c l i m a t i c c o n d i t i o n s a n d o f t e s t s t o s i m u l a t e t h e d a m a g e t o a p a c k a g e w h i c h m a y o c c u r j i n d e r n o r m a l a n d a c c i d e n t c o n d i t i o n s o f t r a n s p o r t T h e c l i m a t i c c o n d i t i o n s s p e c i f i e d i n c l u d e t e m p e r a t u r e, p r e s s u r e, i n s o l a t i o n ^ a n d p r e c i p i t a t i o n. E x a m p l e s a r e g i v e n b e l o w.

38 SEC TIO N II 25 SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) ( a ) T e m p e r a t u r e T h e R e g u l a t i o n s r e q u i r e t h a t e x t r e m e s o f C a n d C b e t a k e n i n t o a c c o u n t in t h e s e l e c t i o n o f p a c k a g i n g m a t e r i a l s, s p e c i a l a t t e n t i o n b e i n g g i v e n t o b r i t t l e f r a c t u r e o v e r t h i s t e m p e r a t u r e r a n g e. I n c a s e s w h e r e t h e p a c k a g i n g i s r e s t r i c t e d t o t e m p e r a t u r e s o t h e r t h a n t h o s e s p e c i f i e d a b o v e, t h e p e r m i t t e d t e m p e r a t u r e r a n g e s h o u l d b e s p e c i f i e d o n t h e p a c k a g e d e s i g n c e r t i f i c a t e, t h u s e n a b l i n g a n y c o m p e t e n t a u t h o r i t y t o t a k e t h i s i n t o a c c o u n t w h e n a p p r o v i n g a s u b s e q u e n t s h i p m e n t ( S e c t i o n V I I I o f t h e R e g u l a t i o n s, p a r a ( e ) ). ( b ) P r e s s u r e E x t r e m e s o f k g / c m 2 ( a b s o l u t e ) ( S e c t i o n I I, p a r a ) a n d 1. 5 k g / c m 2 ( g a u g e ) ( S e c t i o n V I I, p a r a ) m u s t b e c o n s i d e r e d i n p a c k a g e d e s i g n. T h e f o r m e r c o n d i t i o n r e l a t e s t o h i g h - a l t i t u d e, n o n - p r e s s u r i z e d a i r t r a n s p o r t a n d t h e l a t t e r t o a c c i d e n t a l w a t e r i m m e r s i o n, f o r e x a m p l e b e i n g d r o p p e d i n t o a h a r b o u r d u r i n g m a r i t i m e h a n d l i n g. I n a d d i t i o n, f o r T y p e B p a c k a g e s, i t i s n e c e s s a r y t o e s t i m a t e t h e m a x i m u m n o r m a l o p e r a t i o n p r e s s u r e ( S e c t i o n I, p a r a ' ). ( c ) I n s o l a t i o n I n s o l a t i o n d a t a a r e p r e s e n t e d i n T a b l e I I I o f S e c t i o n I I o f t h e R e g u l a t i o n s. T h e s e d a t a a r e a p p l i c a b l e f o r s h i p m e n t s t o a l l p a r t s o f t h e w o r l d. H o w e v e r, f o r p a c k a g e s t o b e t r a n s p o r t e d e x c l u s i v e l y b e t w e e n c e r t a i n

39 26 SEC TIO N II SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) s p e c i f i e d c o u n t r i e s, c o n d i t i o n s o t h e r t h a n t h o s e g i v e n m a y b e a s s u m e d w i t h t h e a g r e e m e n t o f t h e c o m p e t e n t a u t h o r i t i e s o f t h o s e c o u n t r i e s. D A M A G E S I M U L A T I O N T E S T S F O R P A C K A G E S I t m u s t b e e m p h a s i z e d t h a t p a c k a g e t e s t s d o n o t i n t h e m s e l v e s r e p r e s e n t t h e a c t u a l n o r m a l a n d a c c i d e n t c o n d i t i o n s o f t r a n s p o r t ; t h e r e s u l t s o f t h e t e s t s a r e i n t e n d e d t o s i m u l a t e t h e d a m a g e t o t h e p a c k a g e u n d e r s u c h c o n d i t i o n s S i n c e i t i s l i k e l y t h a t r a d i o a c t i v e m a t e r i a l p a c k a g e s w i l l b e e x p o s e d t o r a i n d u r i n g t h e i r t r a n s p o r t a t i o n, a w a t e r s p r a y ( r a i n ) t e s t i s r e q u i r e d t o b e a p p l i e d t o t h e p a c k a g e p r i o r t o e a c h t e s t s i m u l a t i n g p a c k a g e d a m a g e u n d e r n o r m a l c o n d i t i o n s o f t r a n s p o r t. T h e w a t e r s p r a y t e s t i s i n t e n d e d t o s i m u l a t e a h e a v y, d r i v i n g r a i n s u c h a s m i g h t b e e x p e r i e n c e d o n a r a i l w a y p l a t f o r m, q u a y s i d e o r i n a v e h i c l e t r a v e l l i n g a t s p e e d T h e o t h e r t e s t s s i m u l a t i n g d a m a g e t o t h e p a c k a g e u n d e r n o r m a l c o n d i t i o n s o f t r a n s p o r t i n c l u d e a f r e e d r o p t e s t ( a s d u r i n g h a n d l i n g ), a c o m p r e s s i o n t e s t ( a s p e r s t a c k i n g o f o t h e r c a r g o o n t h e t o p o f t h e p a c k a g e ), a n d a p e n e t r a t i o n t e s t ( a s b y a p e n e t r a t i n g o b j e c t i n a d j a c e n t c a r g o ) T e s t s s i m u l a t i n g d a m a g e t o t h e p a c k a g e u n d e r a c c i d e n t c o n d i t i o n s o f t r a n s p o r t i n c l u d e a 1 - m d r o p o n t o a p e n e t r a t o r, a 9 - m d r o p o n t o a f l a t, v e r y h a r d t a r g e t, a n d a m i n.

40 SECTIO N II 27 SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) e x p o s u r e t o a n C f i r e. T h e s e t e s t s a r e a p p l i e d c o n s e c u t i v e l y t o t h e s a m e p a c k a g e s p e c i m e n, t h e t w o m e c h a n i c a l t e s t s i n t h e m o s t d a m a g i n g o r d e r, f o l l o w e d b y t h e t h e r m a l t e s t. A d d i t i o n a l l y, a m w a t e r i m m e r s i o n t e s t i s r e q u i r e d t o b e a p p l i e d s e p a r a t e l y t o a n u n d a m a g e d p a c k a g e. T h e s e t e s t s a r e i n t e n d e d t o s i m u l a t e t h e d a m a g e t o t h e p a c k a g e w h i c h w o u l d r e s u l t f r o m a v e r y s e v e r e a c c i d e n t. T r a n s p o r t e x p e r i e n c e t o d a t e i n d i c a t e s t h a t t h e s e t e s t s a r e r e a s o n a b l e. I n r e s p e c t o f t h e d e s i g n o f t h e r m a l i n s u l a t i o n, h o w e v e r, i t i s i m p o r t a n t t o t a k e i n t o a c c o u n t t h e e f f e c t o f r i p p i n g, c u t t i n g, s k i d d i n g a n d a b r a s i o n t o w h i c h t h e p a c k a g e m a y b e s u b j e c t e d d u r i n g t r a n s p o r t b e f o r e b e i n g i n v o l v e d i n a f i r e. P A C K A G I N G A N D P A C K A G E S IN G E N E R A L S i n c e t h e R e g u l a t i o n s d e f i n e a n d p r e s c r i b e r e q u i r e m e n t s f o r b o t h p a c k a g i n g a n d p a c k a g e s, i t i s i m p o r t a n t t o d i s t i n g u i s h c l e a r l y b e t w e e n t h e s e t e r m s. P a c k a g e = p a c k a g i n g + r a d i o a c t i v e c o n t e n t s S o m e r e g u l a t o r y p r o v i s i o n s r e l a t e t o p a c k a g e, p a r t i c u l a r l y t h o s e p e r f o r m a n c e c r i t e r i a s u c h a s s h i e l d i n g, c o n t a i n m e n t, a n d h e a t t r a n s f e r. T h e r a d i o a c t i v e c o n t e n t s m u s t b e d e f i n e d b e f o r e t h e s e p e r f o r m a n c e c r i t e r i a c a n b e a s s e s s e d. I t s h o u l d b e a p p r e c i a t e d t h a t t h e p r i m a r y h e a t t r a n s f e r m e d i u m a n d t h e a t m o s p h e r e w i t h i n a p a c k a g e c o n s t i t u t e p a r t o f t h e p a c k a g i n g a n d n o t o f t h e c o n t e n t s.

41 28 S E C T IO N n SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) This publication is no longer valid O t h e r r e g u l a t o r y p r o v i s i o n s r e l a t e d i r e c t l y t o p a c k a g i n g. F o r e x a m p l e, r e g u l a t o r y r e q u i r e m e n t s s u c h a s m i n i m u m s i z e o f p a c k a g i n g, m a t e r i a l s e l e c t i o n a n d e a s e o f s u r f a c e d e c o n t a m i n a t i o n a r e i n d e p e n d e n t o f r a d i o a c t i v e c o n t e n t s a n d t h u s a r e c l e a r l y p a c k a g i n g p r o v i s i o n s W h e n s t r u c t u r a l c o m p o n e n t s t o e n s u r e s h i e l d i n g b y d i s t a n c e a r e u s e d, t h e i n t e g r i t y o f t h e o u t e r p a r t o f t h e p a c k a g e s h o u l d b e s u c h a s t o p r e v e n t a n y l o s s o f d i s t a n c e s h i e l d i n g b y p e n e t r a t i o n o f t h e c o m p o n e n t s t h r o u g h i t. S l 6. W h e n t h e s h i e l d i n g r e s u l t s f r o m a c o m b i n a t i o n o f m a t e r i a l a n d d i s t a n c e, t h e d i s t a n c e s h i e l d i n g c o m p o n e n t s s h o u l d b e s o c o m b i n e d w i t h t h e o u t e r s h e l l o f t h e p a c k a g i n g t h a t t h e i n n e r s h i e l d i n g m a t e r i a l d o e s n o t b r e a k t h r o u g h t h e p a c k a g e s u r f a c e d u r i n g t r a n s p o r t C a r e s h o u l d b e t a k e n t o e n s u r e t h a t, w h e r e a f i x t u r e f o r a n i n n e r c o n t a i n e r p a s s e s t h r o u g h t o t h e o u t s i d e o f t h e p a c k a g i n g, a c c i d e n t a l d a m a g e w i l l n o t r e s u l t i n l o o s e n i n g o f t h e f i x t u r e w i t h r e s u l t a n t m o v e m e n t o f a n d p o s s i b l e d a m a g e t o t h e i n n e r c o n t a i n e r. ADDITIONAL REQUIREMENTS FOR TYPE A PACKAGES ( ) T Y P E A - G E N E R A L T y p e A p a c k a g i n g s a r e, b y d e f i n i t i o n, l i a b l e t o b e s e r i o u s l y d a m a g e d o r e v e n d e s t r o y e d i n s e v e r e a c c i d e n t s. S u c h e v e n t s w o u l d i n e v i t a b l y f o c u s t h e a t t e n t i o n o f o f f i c i a l s a n d t h e p u b l i c o n t h e i r a d e q u a c y i n r e s p e c t o f r e g u l a t o r y r e q u i r e m e n t s. H e n c e,

42 SEC TIO N II 29 SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) ADDITIONAL REQUIREMENTS FOR TYPE A PACKAGES ( ) a l t h o u g h T y p e A p a c k a g i n g d e s i g n s d o n o t r e q u i r e c o m p e t e n t a u t h o r i t y a p p r o v a l, i t i s s t r o n g l y r e c o m m e n d e d t h a t t h e d e s i g n e r d o c u m e n t t h e d e m o n s t r a t i o n o f c o m p l i a n c e o f t h e d e s i g n w i t h t h e r e g u l a t o r y r e q u i r e m e n t s a n d k e e p a r e c o r d o f t h i s d o c u m e n t a t i o n i n c a s e i t i s r e q u e s t e d b y t h e c o m p e t e n t a u t h o r i t y. I t i s a l s o e s s e n t i a l t h a t - s u c h a d o c u m e n t c l e a r l y d e f i n e t h e r a d i o a c t i v e c o n t e n t s l i m i t a t i o n s f o r t h e d e s i g n a n d a l s o t h e i n s t r u c t i o n s f o r u s e o f p a c k a g i n g s m a d e t o t h a t d e s i g n F o r s o m e d e s i g n s, e s p e c i a l l y f o r T y p e A p a c k a g i n g f o r f i s s i l e m a t e r i a l w i t h " b u i l t - i n " d i s t a n c e s e p a r a t i o n, i t m a y b e a d v i s a b l e t o s u b m i t a p r o t o t y p e t o a v i b r a t i o n t e s t s o a s t o e n s u r e t h a t t h e r e q u i r e m e n t i n S e c t i o n I I o f t h e R e g u l a t i o n s, p a r a , i s m e t. A n e x a m p l e o f a s u i t a b l e t e s t i s g i v e n i n t h e A n n e x t o S e c t i o n V I I o f t h i s d o c u m e n t W h e r e a s t h e E d i t i o n o f t h e R e g u l a t i o n s d e f i n e d " c o n t a i n m e n t v e s s e l " a n d r e l a t e d d e s i g n a n d p e r f o r m a n c e c r i t e r i a f o r t h a t d e f i n e d t e r m, t h e E d i t i o n o f t h e R e g u l a t i o n s d e f i n e s a " c o n t a i n m e n t s y s t e m " a n d r e l a t e s t h a t t e r m t o t h e d e s i g n a n d p e r f o r m a n c e c r i t e r i a. F o r e x a m p l e, t h e n e w d e f i n i t i o n p e r m i t s t h e u s e o f a s y s t e m w h i c h m a y c o n s i s t o f a n u m b e r o f n e s t e d o r m u l t i - w a l l v e s s e l s. I n f a c t, t h e n e w R e g u l a t i o n s g i v e t h e d e s i g n e r c o m p l e t e f r e e d o m i n t h i s r e s p e c t, p r o v i d e d t h a t h e d e c l a r e s w h a t c o n s t i t u t e s h i s " c o n t a i n m e n t s y s t e m " a n d i s a b l e t o d e m o n s t r a t e c o m p l i a n c e o f t h a t s y s t e m w i t h t h e a p p r o p r i a t e d e s i g n a n d p e r f o r m a n c e c r i t e r i a. A d d i t i o n a l l y, s p e c i a l

43 30 SECTIO N II SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) ADDITIONAL REQUIREMENTS FOR TYPE A PACKAGES ( ) f o r m m a t e r i a l, w h e n i n c l u d e d i n a p a c k a g e, m a y a l s o b e u t i l i z e d a s o n e c o m p o n e n t o f t h e c o n t a i n m e n t s y s t e m T h e R e g u l a t i o n s ( S e c t i o n I I, p a r a ) r e q u i r e t h a t t h e r e s h o u l d b e " n o l o s s o r d i s p e r s a l o f r a d i o a c t i v e c o n t e n t s " a f t e r t h e T y p e A p a c k a g i n g h a s b e e n s u b j e c t e d t o t h e t e s t s o u t l i n e d i n S e c t i o n V I I. T h i s q u a l i t a t i v e p e r f o r m a n c e c r i t e r i o n w a s c h o s e n b y t h e O c t o b e r, , P a n e l o f E x p e r t s a s t h e o n e b e s t s a t i s f y i n g t h e v a r i o u s c o n s i d e r a t i o n s r e l a t i n g t o t h e c o n t a i n m e n t p e r f o r m a n c e o f T y p e A p a c k a g e s T w o b a s i c a p p r o a c h e s h a v e b e e n i d e n t i f i e d a s q u a n t i t a t i v e m e t h o d s o f e v a l u a t - i n g T y p e A c o n t a i n m e n t : t h e a c t i v i t y l e a k a g e c r i t e r i a a n d t h e e n g i n e e r i n g l e a k t i g h t - n e s s ( v o l u m e t r i c l e a k r a t e ) c r i t e r i a. E a c h m e t h o d h a s i t s a d v a n t a g e s a n d d i s a d v a n t a g e s a s o u t l i n e d b e l o w. I t i s r e c o g n i z e d t h a t t h e r e i s n o g e n e r a l c o r r e l a t i o n b e t w e e n t h e t w o m e t h o d s. A C T I V I T Y L E A K A G E C R I T E R I A T h e s e c r i t e r i a h a v e t h e a d v a n t a g e o f e x p r e s s i n g t h e d e s i r e d p e r f o r m a n c e i n t e r m s o f t h e p a r a m e t e r o f p r i m a r y i n t e r e s t : a c t i v i t y l e a k a g e e x p r e s s e d a s a f u n c t i o n o f A 2. T h e d i s a d v a n t a g e s o f t h i s m e t h o d a r e t h a t i t c a n n o t b e d i r e c t l y m e a s u r e d a n d t h a t i t m u s t b e a p p l i e d t o e a c h i n d i v i d u a l ( o r, a l t e r n a t i v e l y, t h e m o s t t o x i c ) r a d i o n u c l i d e w h i c h i s t o b e s h i p p e d i n t h e p a c k a g i n g. I t a l s o d e p e n d s o n t h e p h y s i c a l s t a t e o f t h e m a t e r i a l.

44 S E C T IO N II 31 SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) ADDITIONAL REQUIREMENTS FOR TYPE A PACKAGES ( ) T h e b a s i c m e t h o d i n v o l v e s t h e m e a s u r e m e n t o f t w o p a r a m e t e r s : t h e a c t i v i t y c o n c e n t r a t i o n o f t h e l e a k a b l e m a t e r i a l a n d t h e v o l u m e t r i c r a t e l e a k t i g h t n e s s o f t h e p a c k a g i n g. T h e p r o d u c t o f t h e s e t w o p a r a m e t e r s m u s t b e l e s s t h a n t h e m a x i m u m p e r m i s s i b l e a c t i v i t y l e a k r a t e e x p r e s s e d a s a f u n c t i o n o f A 2 p e r u n i t t i m e. E N G I N E E R I N G L E A K T I G H T N E S S C R I T E R I A E n g i n e e r i n g l e a k t i g h t n e s s o r v o l u m e t r i c l e a k r a t e c r i t e r i a h a v e t h e a d v a n t a g e o f a p p l y i n g w e l l e s t a b l i s h e d l e a k t e s t m e t h o d s d i r e c t l y t o p a c k a g i n g s. T h e i r d i s a d v a n t a g e i s t h a t, a s t h e y c o v e r t h e w h o l e r a n g e o f A 2 v a l u e s ( c u r r e n t l y t o t o u n l i m i t e d c u r i e s ) w i t h a s i n g l e l e a k t i g h t n e s s v a l u e, t h e r e s u l t i n g c o n s e r v a t i s m a p p l i e s i n v a r y i n g d e g r e e s t o a b o u t 9 0 % o f t h e l i s t e d r a d i o n u c l i d e s F o r T y p e A p a c k a g e s, a l l o w a b l e m a x i m u m l e a k a g e r a t e s i n n o r m a l t r a n s p o r t h a v e n o t b e e n e s t a b l i s h e d a n d l e a k t i g h t n e s s i s r e q u i r e d i n a p r a c t i c a l s e n s e. S o m e t e s t o r c r i t e r i o n f o r a d e q u a t e l e a k t i g h t n e s s i s n e e d e d b y d e s i g n e r s, c o n s i g n o r s, a n d a p p l i c a n t s s e e k i n g c o m p e t e n t a u t h o r i t y a p p r o v a l. A l e a k a g e r a t e o f l e s s t h a n T o r r - l i t r e / s o f g a s ( b a s e d o n 1 a t m. d i f f e r e n t i a l p r e s s u r e a s t h e d r i v i n g f o r c e ) i s s e l d o m f o u n d i n p r a c t i c e, b e c a u s e t h i s l e a k a g e r a t e c o r r e s p o n d s t o a p a t h o f o n l y a b o u t 1 p m d i a m e t e r a n d s u c h s m a l l o p e n i n g s a r e r e a d i l y p l u g g e d b y e i t h e r s o l i d p a r t i c l e s

45 32 SEC TIO N II SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) ADDITIONAL REQUIREMENTS FOR TYPE A PACKAGES ( ) o r b y l i q u i d. T h r o u g h s u c h a n o p e n i n g t h e l e a k a g e r a t e o f w a t e r, i n t h e a b s e n c e o f p l u g g i n g a n d i f s u f f i c i e n t d r i v i n g f o r c e t o o v e r c o m e s u r f a c e t e n s i o n i s a s s u m e d, w o u l d b e o f t h e o r d e r o f 10 ~9 c m f s ; h o w e v e r, t h e s u r f a c e t e n s i o n o f w a t e r i n a 1 - p m o p e n i n g c o r r e s p o n d s t o a p r e s s u r e o f a b o u t 3 k g / c m 2. P a r t i c l e s c o n s i d e r a b l y s m a l l e r t h a n 1 / jm w o u l d r e a d i l y p l u g t h e o p e n i n g. F o r t h e s e r e a s o n s, i t a p p e a r s t h a t, f r o m a p r a c t i c a l s t a n d p o i n t, t h e r e i s s e l d o m i f e v e r a n e e d f o r u s i n g t e s t m e t h o d s o r p r o c e d u r e s h a v i n g a s e n s i t i v i t y g r e a t e r t h a n t h a t c o r r e s p o n d i n g t o t h e l e a k a g e o f 1 0 "7 T o r r - l i t r e / s o f g a s a d j u s t e d t o t h e b a s i s o f o n e a t m o s p h e r e a b s o l u t e p r e s s u r e d o w n s t r e a m a n d t w o a t m o s p h e r e s a b s o l u t e u p s t r e a m. L e s s s e n s i t i v e t e s t s, s u c h a s b u b b l e t e s t s, m a y o f t e n b e a d e q u a t e f o r l i q u i d s o r s o l i d s o f m o d e r a t e l y l o w s p e c i f i c a c t i v i t y, o r f o r o t h e r s o l i d s n o t f i n e l y d i v i d e d. BASIC ADDITIONAL REQUIREMENTS FOR TYPE B (U)PACKAGES ( ) SPECIFIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) ADDITIONAL REQUIREMENTS FOR TYPE B (M) PACKAGES ( ) T Y P E B P A C K A G I N G S A N D P A C K A G E S T y p e B p a c k a g e d e s i g n s r e q u i r e c o m p e t e n t a u t h o r i t y a p p r o v a l, b e c a u s e t h e y : m a y c o n t a i n u n l i m i t e d r a d i o a c t i v e c o n t e n t s w h i c h m a y h a v e a v e r y s i g n i f i c a n t h a z a r d p o t e n t i a l ; a r e t h e r e f o r e r e q u i r e d t o w i t h s t a n d a c c i d e n t c o n d i t i o n s o f t r a n s p o r t w i t h o n l y a v e r y l i m i t e d r e d u c t i o n i n c o n t a i n m e n t a n d s h i e l d i n g e f f i c i e n c y ; m a y b e r e q u i r e d t o d i s s i p a t e a s i g n i f i c a n t q u a n t i t y o f d e c a y h e a t w h i c h m a y b e

46 S E C T IO N n 33 SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) BASIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) SPECIFIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) ADDITIONAL REQUIREMENTS FOR TYPE B (M) PACKAGES ( ) c a p a b l e o f s e l f - d e s t r u c t i o n o f t h e p a c k a g e, i n j u r y t o p e r s o n s o r d a m a g e t o o t h e r g o o d s T h e c o m p e t e n t a u t h o r i t y a p p r o v e s t h e p a c k a g e d e s i g n. T o a s s u r e h i m s e l f t h a t t h e a c t u a l p a c k a g i n g s a r e p r o d u c e d i n a c c o r d a n c e w i t h t h e d e s i g n, t h e c o m p e t e n t a u t h o r i t y m a y i n s p e c t t h e p a c k a g i n g s d u r i n g f a b r i c a t i o n a n d m a y r e q u i r e c e r t i f i c a t i o n b y t h e m a n u f a c t u r e r t h a t t h e p a c k a g i n g s h a v e b e e n m a d e i n a c c o r d a n c e w i t h t h e a p p r o v e d d e s i g n. A d d i t i o n a l l y, p r i o r - t o - f i r s t - s h i p m e n t t e s t s a r e r e q u i r e d t o c o n f i r m t h e s h i e l d i n g, c o n t a i n m e n t, h e a t t r a n s f e r, a n d, i f a p p l i c a b l e, n u c l e a r s a f e t y c a p a b i l i t i e s o f t h e d e s i g n. A l t h o u g h t h e s e t e s t s a r e s o l e l y t h e r e s p o n s i b i l i t y o f t h e c o n s i g n o r, t h e c o m p e t e n t a u t h o r i t y m a y w i s h t o s c r u t i n i z e t h e i r r e s u l t s o r e v e n t o r e q u e s t t h a t t h e y b e r e p e a t e d i n t h e e v e n t o f d o u b t, m i s h a p o r f a i l u r e T w o k i n d s o f T y p e B p a c k a g e a r e i n c l u d e d i n t h e R e g u l a t i o n s : T y p e B ( U ) a n d T y p e B ( M ). F o r T y p e B ( U ) p a c k a g e s, t h e p e r f o r m a n c e c r i t e r i a a r e a l l d e f i n e d a n d a c c e p t e d a s b e i n g s u f f i c i e n t l y c o n s e r v a t i v e s o t h a t a p p r o v a l o f t h e d e s i g n s o l e l y b y t h e c o m p e t e n t a u t h o r i t y o f t h e c o u n t r y o f o r i g i n i s n e c e s s a r y ( u n i l a t e r a l a p p r o v a l ). A l t h o u g h T y p e B ( M ) p a c k a g e s a r e e x p e c t e d t o c o m p l y w i t h t h e T y p e B ( U ) r e q u i r e m e n t s a s f a r a s p r a c t i c a b l e, d e p a r t u r e s f r o m s p e c i f i c a d d i t i o n a l r e q u i r e m e n t s f o r T y p e B ( U ) a r e p e r m i t t e d, s i n c e o p e r a t i o n a l c o n t r o l s s p e c i f i e d b y t h e

47 34 SEC TIO N II SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) BASIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) SPECIFIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) ADDITIONAL REQUIREMENTS FOR TYPE B (M) PACKAGES ( ) c o n s i g n o r a r e a p p l i e d s u b j e c t t o t h e a p p r o v a l o f t h e c o m p e t e n t a u t h o r i t i e s o f a l l c o u n t r i e s t h r o u g h w h i c h t h e p a c k a g e w i l l b e t r a n s p o r t e d ( m u l t i l a t e r a l a p p r o v a l ) W h e n t h e p r i n c i p l e s i n S e c t i o n I I o f t h e R e g u l a t i o n s a r e a p p l i e d t o t h e d e s i g n, a c c o u n t s h o u l d b e t a k e n o f t h e f o l l o w i n g : ( a ) g a l v a n i c r e a c t i o n s b e t w e e n d i s s i m i l a r m a t e r i a l s, p a r t i c u l a r l y m e t a l s ; ( b ) c h e m i c a l r e a c t i o n s b e t w e e n t h e f u e l a n d t h e p r i m a r y h e a t t r a n s f e r m e d i u m ; ( c ) r a d i o l y t i c d e c o m p o s i t i o n o f t h e p r i m a r y h e a t t r a n s f e r m e d i u m ; (d ) t h e e f f e c t o f r a d i a t i o n o n a n y p o l y m e r i z a t i o n o f a d d i t i v e s t o t h e p r i m a r y h e a t t r a n s f e r m e d i u m ; ( e ) r a d i a t i o n d a m a g e t o p a c k a g i n g m a t e r i a l s ; a n d ( f ) p o s s i b l e g e n e r a t i o n o f c o r r o s i v e p r o d u c t s a s a r e s u l t o f n e u t r o n i r r a d i a t i o n ; f o r e x a m p l e, w o o d, a s u s e d i n s o m e d e s i g n s f o r F i s s i l e C l a s s I p a c k a g e s, m a y e v o l v e o r g a n i c v a p o u r s w h i c h a r e c o r r o s i v e t o c a d m i u m A c c o u n t s h o u l d b e t a k e n o f t h e p o s s i b l e f o r m a t i o n o f e u t e c t i c a l l o y s w h i c h m i g h t i m p a i r t h e e f f i c i e n c y o f t h e p a c k a g i n g. F o r e x a m p l e, f a i l u r e o f s t e e l i n c o n t a c t w i t h u r a n i u m m i g h t o c c u r a t a t e m p e r a t u r e b e l o w C b e c a u s e o f t h e f o r m a t i o n o f a U - F e e u t e c t i c a l l o y, a l t h o u g h d e p o s i t i o n o f s t a b i l i z i n g m a t e r i a l s u c h a s t u n g s t e n m a y i n h i b i t t h i s p h e n o m e n o n. I n a d d i t i o n, c o p p e r m a y a l l o y w i t h l e a d a t t e m p e r a t u r e s e n c o u n t e r e d i n l e a d - p o u r i n g o p e r a t i o n s.

48 SECTIO N II 35 SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) BASIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) SPECIFIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) ADDITIONAL REQUIREMENTS FOR TYPE B (M) PACKAGES ( ) F o r t h e p r e l i m i n a r y d e s i g n o f t h e o u t e r s h e l l o f a l e a d - i n - s t e e l p a c k a g i n g, t h e f o l l o w i n g e q u a t i o n m a y b e u s e d t o e s t i m a t e t h e o u t e r s h e l l t h i c k n e s s r e q u i r e d t o r e s i s t f a i l u r e w h e n t h e p a c k a g e i s s u b j e c t e d t o t h e m e c h a n i c a l d r o p I I t e s t i n S e c t i o n V I I o f t h e R e g u l a t i o n s : w h e r e t = o u t e r s h e l l t h i c k n e s s ( i n. ) W = w e i g h t o f p a c k a g e ( l b ) s = t e n s i l e s t r e n g t h o f o u t e r s h e l l m a t e r i a l ( l b / i n 2 ) T h i s e q u a t i o n i s b a s e d o n a p a c k a g e d e s i g n e m p l o y i n g a n n e a l e d m i l d s t e e l a n d c h e m i c a l l e a d. P a c k a g e d e s i g n s e m p l o y i n g m a t e r i a l s o f p h y s i c a l p r o p e r t i e s d i f f e r e n t f r o m t h e f o r e g o i n g ( d i f f e r e n t s t r e n g t h a n d i m p a c t - r e s i s t a n c e o f s t e e l s, a n t i m o n i a l l e a d ) m a y r e q u i r e a d i f f e r e n t t h i c k n e s s o f t h e o u t e r s t e e l s h e l l t o m e e t t h e m e c h a n i c a l d r o p I I t e s t i n S e c t i o n V I I o f t h e R e g u l a t i o n s F o r a l a r g e l e a d - f i l l e d c a s k, t h e p h e n o m e n o n o f l e a d c r e e p s h o u l d b e c o n s i d e r e d, s i n c e t h i s m a y a f f e c t s u c h f a c t o r s a s t h e b o n d i n g o f l e a d t o s t e e l a n d t h e f o r c e s t h r o u g h o u t t h e s t r u c t u r e. T h i s p h e n o m e n o n o c c u r s a t a m b i e n t t e m p e r a t u r e s a n d l o w s t r e s s e s.

49 36 S E C T IO N n SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) BASIC ADDITIONAL REQUIREMENTS FOR TYPE B (U). PACKAGES ( ) SPECIFIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) ADDITIONAL REQUIREMENTS FOR TYPE B (M) PACKAGES ( ) F o r l e a d - f i l l e d c a s k s w i t h s t e e l s h e l l s, a t t e n t i o n s h o u l d b e p a i d t o t h e f a c t t h a t s o m e s t e e l s h a v e v e r y l i t t l e e l o n g a t i o n a t t h e t e m p e r a t u r e a t w h i c h l e a d m e l t s, a n d t h a t t h e c a s k c o u l d t h e r e f o r e b e f r a c t u r e d b y t h e i n c r e a s i n g v o l u m e o f t h e l e a d. W h e r e " b u i l t - i n " v o i d s a r e c o n t e m p l a t e d a s a m e a n s o f a c c o m m o d a t i n g t h e i n c r e a s e d v o l u m e o f l e a d o n m e l t i n g, i t s h o u l d b e r e c o g n i z e d t h a t, w h e n t h e l e a d c o o l s, a v o i d w i l l e x i s t w h o s e p o s i t i o n m a y b e d i f f i c u l t t o p r e d i c t, s i n c e i t w i l l b e l a r g e l y d e p e n d e n t o n t h e o r i e n t a t i o n o f t h e p a c k a g e i n t h e t h e r m a l e n v i r o n m e n t. I t s h o u l d a l s o b e r e c o g n i z e d t h a t t h e e f f e c t o f s u c h v o i d s m a y b e o f f s e t b y c r a c k s d e v e l o p e d i n t h e s t e e l s h e l l, e i t h e r d u r i n g t h e m e c h a n i c a l t e s t o r a s a r e s u l t o f l o c a l m e l t i n g o f l e a d a t a p o s i t i o n r e m o t e f r o m t h e v o i d. M o l t e n l e a d w i l l e s c a p e r e a d i l y t h r o u g h s u c h c r a c k s I n c o n s i d e r i n g t h e g e n e r a l d e s i g n f e a t u r e s i n S e c t i o n I I, a t t e n t i o n s h o u l d b e p a i d t o t h e c h o i c e o f m a t e r i a l s w h i c h w i l l f a c i l i t a t e t h e d e c o n t a m i n a t i o n o f t h e o u t e r s u r f a c e s o f t h e p a c k a g e P a r t i c u l a r a t t e n t i o n s h o u l d b e p a i d t o t h e c h o i c e o f j o i n t i n g m a t e r i a l s, e s p e c i a l l y i n r e s p e c t t o m a i n t a i n i n g j o i n t i n t e g r i t y i n t h e e v e n t o f s e v e r e i m p a c t f o l l o w e d b y f i r e F o r l o n g, s l e n d e r p a c k a g e s, p a r t i c u l a r l y w h e r e t h e l e n g t h - t o - d i a m e t e r r a t i o i s 5 o r m o r e, t h e r i g i d i t y o f t h e c o n s t r u c t i o n s h o u l d b e c a r e f u l l y c o n s i d e r e d w i t h s p e c i a l r e f e r e n c e t o t h e v i b r a t i o n c o n d i t i o n s e n c o u n t e r e d i n n o r m a l t r a n s p o r t.

50 S E C T IO N n 37 SECTION n - PACKAGE AND PACKAGE DESIGN REQUIREMENTS ( ) BASIC ADDITIONAL REQUIREMENTS FOR TYPE B (U)PACKAGES ( ) SPECIFIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) ADDITIONAL REQUIREMENTS FOR TYPE B (M) PACKAGES ( ) W h e n a p p l y i n g t h e g e n e r a l r e g u l a t o r y d e s i g n f e a t u r e s i n S e c t i o n I I o f t h e R e g u l a t i o n s r e g a r d i n g f r e e d o m f r o m p r o t r u d i n g f e a t u r e s, t h e d e s i g n e r s h o u l d, a s f a r a s p r a c t i c a b l e : ( a ) p o s i t i o n p a c k a g e d r a i n a g e f a c i l i t i e s s o t h a t t h e y c a n n o t b e d a m a g e d w i t h s u b s e q u e n t l o s s o f p r i m a r y h e a t t r a n s f e r m e d i u m ; ( b ) p o s i t i o n s e c u r i t y s e a l s, e. g. p a d l o c k s, s o t h a t t h e m a x i m u m p r o t e c t i o n i s a f f o r d e d t o t h e m d u r i n g t r a n s p o r t ; ( c ) p o s i t i o n w e l d s s o a s t o m i n i m i z e b o t h s t r e s s c o n c e n t r a t i o n a n d v u l n e r a b i l i t y t o f a i l u r e u n d e r i m p a c t c o n d i t i o n s, a s, f o r e x a m p l e, b y t h e u s e o f r o u n d e d r a t h e r t h a n s q u a r e c o r n e r s ; a n d (d ) m i n i m i z e p o s s i b l e f a i l u r e o f t h e p a c k a g e u n d e r i m p a c t c o n d i t i o n s t h a t c o u l d o c c u r t h r o u g h d a m a g e t o e x t e r n a l a p p u r t e n a n c e s s u c h a s t r u n n i o n s. S H I E L D I N G T h e e n t i r e s t r u c t u r e o f t h e p a c k a g e s h o u l d b e d e s i g n e d s o a s t o p r e v e n t t h e e m i s s i o n o f r a d i a t i o n i n b e a m s i n a n y d i r e c t i o n. P a r t i c u l a r e f f o r t s s h o u l d b e m a d e t o p r e v e n t " s t r e a m i n g " a t l i d j o i n t s a n d a l o n g d r a i n s a n d v e n t s. CONTAINMENT P r o v i s i o n s s h o u l d b e m a d e f o r p r o v i n g t h e l e a k t i g h t n e s s o f f i l l e d p a c k a g e s w i t h o u t b r e a c h i n g t h e c o n t a i n m e n t [ 1 ].

51 38 SECTION II SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) BASIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) SPECIFIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) ADDITIONAL REQUIREMENTS FOR TYPE B (M) PACKAGES ( ) T h e d e s i g n e r o f a p a c k a g i n g s h o u l d c o n s i d e r t h e d e s i r a b i l i t y o f p r o v i d i n g m e t h o d s o f o b t a i n i n g m e a s u r e m e n t s o f t h e i n t e r n a l p r e s s u r e s i n t h e p a c k a g i n g d u r i n g t r a n s p o r t, a n d, i n c e r t a i n c a s e s, o f p r o v i d i n g m e a n s o f t a k i n g s a m p l e s T h e d e s i g n s h o u l d e n s u r e t h a t w a t e r o r o t h e r m a t e r i a l g e n e r a t i n g v a p o u r o n h e a t i n g i s n o t u n i n t e n t i o n a l l y a c c u m u l a t e d i n c o n f i n e d s p a c e s i n t h e p a c k a g i n g s o a s t o e n d a n g e r t h e i n t e g r i t y o f t h e p a c k a g e i f i t w e r e s u b j e c t e d t o a f i r e o r f r e e z i n g c o n d i t i o n s. W h e r e a p a c k a g e i s i n t e n d e d f o r u s e w i t h a g a s e o u s p r i m a r y h e a t t r a n s f e r m e d i u m, t h e d e s i g n s h o u l d m a k e p r o v i s i o n f o r t h e n e c e s s a r y d r y i n g o u t o f t h e p e r t i n e n t s p a c e s p r i o r t o s h i p m e n t T h e d e s i g n o f p a c k a g i n g f o r u s e w i t h a p r i m a r y h e a t t r a n s f e r m e d i u m s h o u l d b e s u c h a s t o e n a b l e t h e p r e s e n c e o f t h e r e q u i r e d a m o u n t o f s u c h m e d i u m t o b e v e r i f i e d b e f o r e t h e p a c k a g e i s h a n d e d o v e r f o r s h i p m e n t T h e d e s i g n e r o f a p a c k a g e c o n t a i n i n g a p r i m a r y h e a t t r a n s f e r m e d i u m s h o u l d c o n s i d e r i n d i c a t i n g t h e a r e a o n t h e p a c k a g e s u r f a c e i n w h i c h t h e m a x i m u m t e m p e r a t u r e i s e x p e c t e d t o o c c u r a n d s u g g e s t i n g s o m e m e a n s o f m e a s u r i n g t h i s t e m p e r a t u r e A m e a n s o f r e l i e v i n g p r e s s u r e i n a p a c k a g e c o n t a i n i n g a p r i m a r y h e a t t r a n s f e r m e d i u m, i r r e s p e c t i v e o f w h e t h e r t h e v e n t i n g r e q u i r e s o p e r a t i o n a l c o n t r o l o r i s d e s i g n e d

52 S E C T IO N n 39 SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) BASIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) SPECIFIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) ADDITIONAL REQUIREMENTS FOR TYPE B (M) PACKAGES ( ) t o o p e r a t e a u t o m a t i c a l l y, e i t h e r o n a c o n t i n u o u s o r i n t e r m i t t e n t b a s i s, s h o u l d b e d e s i g n e d s o a s t o p e r m i t, u n d e r n o r m a l c o n d i t i o n s o f t r a n s p o r t, t h e p a s s a g e o f g a s o r v a p o u r b u t n o t o f l i q u i d I f t h e p r e s s u r e i n t h e c o n t a i n m e n t s y s t e m c o u l d r e s u l t i n a s t r e s s e x c e e d i n g t h e m i n i m u m y i e l d s t r e n g t h u n d e r t h e t e s t s i n S e c t i o n V I I o f t h e R e g u l a t i o n s ( p a r a s a n d ), a p r e s s u r e r e l i e f v a l v e m u s t b e f i t t e d t o p r e v e n t t h e y i e l d s t r e n g t h f r o m b e i n g e x c e e d e d. T h e y i e l d s t r e n g t h s h o u l d b e t a k e n a s t h e y i e l d s t r e n g t h o f t h i s m a t e r i a l a t t h e t e m p e r a t u r e i t w o u ld b e e x p e c t e d t o r e a c h u n d e r t h e c o n d i t i o n s o f t h e t e s t s I n d e c i d i n g w h e t h e r a p a c k a g e m e e t s t h e s p e c i f i c a d d i t i o n a l r e q u i r e m e n t s f o r T y p e B ( U ) p a c k a g e s, a c c o u n t s h o u l d b e t a k e n o f s t r e s s e s c a u s e d b y f a c t o r s o t h e r t h a n i n t e r n a l p r e s s u r e w h i c h c o u l d n e v e r t h e l e s s c o n t r i b u t e t o e x c e e d i n g t h e y i e l d s t r e n g t h o f t h e c o m p o n e n t, f o r e x a m p l e t r a n s p o r t a t i o n d i f f i c u l t i e s, d i f f e r e n t i a l e x p a n s i o n s o f m a t e r i a l s, e t c W h e r e i t i s n e c e s s a r y t o f i t l e a k t i g h t p r o t e c t i o n t o r e t a i n a n y l e a k a g e f r o m b l a n k e d - o f f v a l v e s, e t c., d u r i n g t r a n s p o r t, c o n s i d e r a t i o n s h o u l d b e g i v e n t o p r o v i d i n g f o r t h e d e t e c t i o n a n d r e m o v a l o f t h a t l e a k a g e i n a s a f e m a n n e r. B U I L T - I N P O I S O N S I f, f o r t h e p u r p o s e s o f n u c l e a r s a f e t y, t h e p a c k a g i n g i n c o r p o r a t e s n e u t r o n p o i s o n s,

53 40 SECTION n SECTION n - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) BASIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) SPECIFIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) ADDITIONAL REQUIREMENTS FOR TYPE B (M) PACKAGES ( ) t h e d e s i g n e r s h o u l d t a k e s t e p s t o e n s u r e t h a t t h e p r e s e n c e, q u a l i t y a n d d i s t r i b u t i o n o f s u c h p o i s o n s c a n b e v e r i f i e d f r o m t i m e t o t i m e a s n e c e s s a r y. M E C H A N I C A L C O O L I N G D E V I C E S M e c h a n i c a l d e v i c e s, s u c h a s p u m p s, m o t o r s, g e n e r a t o r s a n d f a n s, w h i c h a r e e s s e n t i a l t o t h e c o n t r o l o f t e m p e r a t u r e a n d p r e s s u r e c o n d i t i o n s w i t h i n a p a c k a g e, s h o u l d h a v e a h i g h d e g r e e o f o p e r a t i o n a l r e l i a b i l i t y. W h e n t h i s c a n n o t b e r e a s o n a b l y e n s u r e d, t h e p r o v i s i o n o f w a r n i n g d e v i c e s a n d s t a n d b y o r d u p l i c a t e e q u i p m e n t s h o u l d b e c o n s i d e r e d. S u c h a n c i l l a r y e q u i p m e n t s h o u l d b e r e l i e d o n o n l y t o m e e t t h e 5 0 C / 8 2 C s u r f a c e t e m p e r a t u r e l i m i t s ( a s a p p r o p r i a t e ) u n d e r n o r m a l c o n d i t i o n s o f t r a n s p o r t a n d n o t u n d e r a c c i d e n t c o n d i t i o n s. C L O S U R E S A N D T I E - D O W N S Y S T E M T o l e r a n c e s i n t h e d e s i g n o f p a c k a g i n g f e a t u r e s, p a r t i c u l a r l y m a t c h i n g f e a t u r e s o f c l o s u r e d e v i c e s, s h o u l d b e s u c h t h a t a n y s h e a r s t r e s s e s t o w h i c h t h e p a c k a g e w o u l d b e s u b j e c t e d i n t h e m e c h a n i c a l t e s t i n S e c t i o n V I I o f t h e R e g u l a t i o n s a r e i m p o s e d o n l y o n t h o s e p a r t s o f t h e p a c k a g i n g s p e c i f i c a l l y d e s i g n e d t o w i t h s t a n d s u c h s t r e s s e s T h e m a t e r i a l f o r t h e t i e - d o w n a t t a c h m e n t s s h o u l d b e s u i t a b l e f o r l o w t e m p e r a t u r e c o n d i t i o n s. A r u p t u r e o f t h e s e a t t a c h m e n t s s h o u l d n o t i m p a i r a n y f u n c t i o n o f t h e p a c k a g i n g.

54 SECTION n 41 SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) BASIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) SPECIFIC ADDITIONAL REQUIREMENTS FOR TYPE B (U) PACKAGES ( ) ADDITIONAL REQUIREMENTS FOR TYPE B (M) PACKAGES ( ) S O L A R H E A T L O A D I n a s s e s s i n g t h e s o l a r h e a t l o a d f r o m s o l a r r a d i a t i o n, a p p r o p r i a t e a b s o r p t i v i t y a n d e m i s s i v i t y f a c t o r s s h o u l d b e t a k e n i n t o a c c o u n t. I n a d d i t i o n, a t t e n t i o n s h o u l d b e p a i d t o t h e p o s s i b i l i t y o f t h e s h a d o w i n g o f s o m e s u r f a c e s b y o t h e r s u r f a c e s a n d t o t h e h e a t t r a n s m i s s i o n c h a r a c t e r i s t i c s o f v a r i o u s c o m p o n e n t s s u c h a s f i n s I f a p a c k a g e i s i n t e n d e d t o b e t r a n s p o r t e d o n l y i n a r e s t r i c t e d a r e a, c o n d i t i o n s d i f f e r e n t f r o m t h o s e s p e c i f i e d i n t h e R e g u l a t i o n s m a y b e u s e d i n a s s e s s i n g t h e s o l a r h e a t l o a d b y a g r e e m e n t w i t h t h e c o m p e t e n t a u t h o r i t i e s c o n c e r n e d. F o r e x a m p l e, i n t h e U n i t e d K i n g d o m, b e c a u s e o f t h e t e m p e r a t e c l i m a t e, a n a m b i e n t t e m p e r a t u r e o f 2 6 C m a y b e a s s u m e d a n d t h e i n s o l a t i o n f i g u r e s m a y b e r e d u c e d b y a f a c t o r ' o f 2. R E P R O C E S S I N G P L A N T A C C E P T A N C E C R I T E R I A M o s t i r r a d i a t e d - f u e l r e p r o c e s s i n g p l a n t s h a v e s p e c i f i e d p a c k a g e a c c e p t a n c e c r i t e r i a w h i c h a d e s i g n e r w o u l d b e a d v i s e d t o a s c e r t a i n a t t h e p r e l i m i n a r y d e s i g n s t a g e. I n f a c t, t h e h a n d l i n g f a c i l i t i e s a t t h e b e g i n n i n g a n d t h e e n d o f t r a n s p o r t, t h e f l a s k a n d i t s c o n v e y a n c e s h o u l d b e c o n s i d e r e d t o g e t h e r a s a s y s t e m.

55 42 SECTION n SECTION II - PACKAGING AND PACKAGE DESIGN REQUIREMENTS ( ) R E F E R E N C E [1 ] MESSENGER, W. de L. M., Tests on Transport Packaging for Radioactive M aterials (Proc. Seminar Vienna, 1971), IAEA, Vienna (1971) 217.

56 SECTION III SECTION m - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) M ATERIALS 301. The fundamental quantities A 2 used in the Regulations were calculated on the basis of a m odel which assum es that, if the m aterial is packed in a Type A packaging and the package becom es involved in a "m edian accident", 1 0 * 3 of the contents m ay escape from the package and 10~3 of this amount (i.e. 1 0 " 6 of the total package contents) m ay be taken into the body of a person in the vicinity of the accident In determining the activity lim its to be placed on the contents of packages for which no regulatory requirem ents relating to design and perform ance are laid down, no allowance can be made for the ability of the package to retain any of its contents if it should becom e involved in an accident. It must therefore be assum ed that the total package contents m ay be released and that 10 ' 3 of it may be taken into the body. To p reserv e, therefore, the same degree of safety as for Type A packages, the lim it for non-special form m aterial which may be transported in exempt packages is set at lo ' 3 A 2. 43

57 44 SECTION m SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC A CTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) This publication is no longer valid ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) 303. The determination of the A 2 values also takes into account the external radiation hazard of the m aterial, so that the adoption of 1 0 " 3 A 2 as an exemption lim it ensures that the radiation hazard associated with transporting exempt quantities of these m aterials is consistent with that associated with Type A packages A different situation a rise s in the case of special form m aterials, which, in the present context, will alm ost always be encapsulated. Special form m aterial m ust, by definition, comply with the tests specified in Section VII of the Regulations, paras , so that the probability of release of any loose radioactive m aterial, even in the event of a severe accident, is very sm all Thus, if radiotoxicity were the only hazard to be considered, much higher exempt quantity lim its could be accepted for encapsulated m aterials. However, the nature of special form m aterials does not provide any additional safeguards where the external radiation hazard is concerned. A lim it must therefore be imposed on the quantities of encapsulated m aterial that can be exempted from special packaging requirem ents so that this can be taken into account. The exemption lim it chosen in these cases is 10 ' 3 A x. This allows some relaxation of the quantities of m aterials that can be transported in

58 SECTION m 45 SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) the exempt category if they are properly encapsulated, but lim its the external d oseequivalent rate from an unshielded encapsulated source to 1 m rem /h at 3 m, i. e. one thousandth of the dose-equivalent rate used to determine the A x values The above discussion outlines the basis of the selection of the exemption lim its for the two form s of solid m aterials listed in Table V of the Regulations. A sim ilar argument leads to the selection of A x and 10"3 A 2, respectively, for the exemption lim its for encapsulated and unencapsulated gases In the case of liquids however, it was felt that there was a greater probability of a spill occurring, and an additional safety factor of ten was applied with the result that the exemption lim it for liquids is set at io -4 A Tritiated water requires special consideration, since the hazard of this m a terial is related m ore to its concentration than to its total activity. In the exposure m odel which led to the selection of 10 C i/1 as the low specific activity lim it for tritiated w ater.it was assum ed that a person involved in a spill of this m aterial could become splashed with a quarter of his body area remaining wet for a quarter of an hour.

59 46 SECTION HI SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) During this tim e, he would also be inhaling (and absorbing through his skin) tritiated water vapour. Such an exposure to tritiated water of concentration 10 C i/1 could lead to a whole-body dose of 3 rem. The dose r e ceived in such an incident is largely dependent on the specific concentration of the tritiated water, the total activity involved influencing the dose only insofar as it affects the quantity of liquid available for splashing and the area of ground that might be covered by a spill which, in turn, could affect the amount of tritiated water vapour that becom es available for inhalation. That is, the quantity of activity would be related m ore to the area of influence of a spill, and consequently to the number of people who could become involved, than to the dose each individual might receive The exemption lim its that have been set down for tritiated water are thus related to its concentration. For a concentration of one tenth of the low specific activity lim it of 10 C i/1 or greater, the exempt quantity is of the order of 1 0 "4 A 2, the general value of the exemption lim it for liquids, as discussed above. However, the A 2 value for tritiated water listed in Table VII of the Regulations is limited to 1000 Ci by convention; the true figure is about 5000 Ci and 1 0 "4 of this value has been rounded up to

60 SECTION m 47 SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIV ITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) 1 Ci to give the exemption lim it listed in Table V of the Regulations. This means that only m l of tritiated water at a concentration of 10 C i/1 could be transported as an exempt quantity, and it is highly unlikely that anyone involved in a spill of this volume of liquid could, on the basis of the low specific activity m odel outlined above, receive a whole-body dose approaching 3 rem, even if the exposure time were considerably longer than the quarter of an hour assumed in that model With this as a basic figure, the exem p tion lim its for tritiated water m ay be raised to a value of 100 Ci if the concentration is between 0. 1 and 1 C i/1 and to a value of 1000 Ci (the A 2 value listed in Table VII of the Regulations) if the concentration is below 0. 1 C i/ Tritium gas has also been listed separately in Table V of the Regulations. This is not because the hazard of tritium gas requires treatment different from other gases; indeed the same factors of 1 0 ' 3 A j and 1 0 "3 A 2 set down for other gases also apply to tritium. However, the A x and A 2 values listed for tritium gas in Table VII have been lim ited by convention to 1000 Ci and it was felt that 10 3 of this value gave artificially low values for the exemption lim its for this gas which were unnecessarily

61 48 SECTION m SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) restrictive in view of its relative lack of radiotoxicity. The true values of Aj and A 2 for tritium gas were therefore chosen for calculation of the exemption lim its. These are Ci in both ca ses, 10"3 of which gives the value of 20 Ci listed in Table V of the Regulations as the exemption lim it ('M aterials') for tritium gas. DESIGNER AND MANUFACTURER 312. The design of a capsule used for carrying quantities of radioactive m aterial not exceeding the exempt lim its for special form m aterials, nam ely 1 0 ' 3 A l4 does not require competent authority approval under Section VIII of the Regulations However, it is im plicit under the definition of special form radioactive m aterial that such capsules m ust comply with the impact, percussion, heating, corrosion and dynamic bending test requirem ents of Section VII of the Regulations, paras The competent authority m ay, at any tim e, call upon the designer to demonstrate that his capsule designs comply with these test requirem ents. Sim ilarly, the manufacturer m ay be called upon to demonstrate that the capsules are made according to the design specifications.

62 SECTION IE 49 SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIV ITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) COM PETENT AUTHORITY 315. Items complying with the provisions of Section III of the Regulations are exempt from all the package and administrative requirem ents of Section VIII. In particular, the design for special form radioactive m aterial, which in this context will invariably mean capsule design, does not require competent authority approval if the activity content of the capsule does not exceed 10 "3 A x It is, however, im plicit in its definition that special form radioactive m aterial in any quantity is required to comply with the impact, percussion, heating, corrosion and dynamic bending test requirem ents specified in Section VII of the Regulations, paras Although, in general, it m ay not be possible for the competent authority to keep track of the encapsulated radioactive m aterials being transported under exempt conditions in his area of responsibility, he m ay wish, when he knows that such capsules are being m ade, to assure him self on occasion that the designs conform adequately to the definition of special form radioactive m aterial in Section I of the Regulations, and that the capsules are being manufactured according to the design specifications.

63 50 SECTION m SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) CONSIGNOR 318. Means of transport: Exempt item s m ay be carried by any means of transport since, as presented for transport, they require no special handling for reasons of safety. Exempt item s which may be transported by post include articles manufactured from natural or depleted uranium and natural thorium (Section III of the Regulations, para. 312) and empty packages, although the provisions for transport by post (Section V, paras ) refer to the content lim its in Table V of the Regulations Size of packages: The size of the packages for m ost exempt item s is not specified. Some exempt item s m ay include fissile m aterials and, for the purpose of nuclear criticality safety, the quantity per package is lim ited to 15 g and the minimum external dimension of the package to 10 cm. The lim it on quantity is given only for uranium -235, since the other fissile m aterial, plutonium, and uranium -233 are already lim ited well below 15 gram s by the radioactivity lim its per package When delivering the exempt item s for transport, the consignor is required to certify that the item s m eet the regulatory requirem ents for transport as exempt item s. Therefore, although competent authority

64 SECTION III 51 SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC A CTIV ITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) approval of exempt item s is not required, the consignor must be prepared to provide the appropriate competent authority, if r e quested, with evidence that the item s as shipped met the applicable requirem ents Some comments on the provisions specific to certain of the exempt item s are set out below Marking: The marking "R adioactive" (Section III of the Regulations, para. 306 (b)), although not visible on the outside of the package, is required so that a person can be made aware that radioactive m aterial is present before he opens that part of the packaging, instrument or article which actually contains the radioactive m aterial Item and package lim its: The package lim its (Section III of the Regulations, para. 306) apply to individual packages, whether large or sm all, since each package has about the same probability of being involved in an accident and releasing its contents. Further, there is no activity lim it on a load of packages or item s, because the probability of many or a ll packages releasing their contents in an accident is very much le ss than that of a single package being disrupted.

65 52 SECTION m SECTION HI - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIV ITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) INSTRUMENTS AND ARTICLES (see Table I) 324. Except for luminous watches and device all instruments and articles containing radioactive m aterial must be marked "Radioactive1 TA B LE I. INSTRUMENTS AND ARTICLES Package lim its Nature of materials Item limits Other than by post By post Solids Special form i Ai Other forms 10-2 A2 ^ i A2 Liquids a '1 Az 10-2 a 2 Gases Tritium 20 Ci 200 Ci 20 Ci Special form 10-3 A:!0-2 A: 10-3 Other forms 10'3 A A A2 Transport other than by post 325. If radioactive sources, in solid or liquid form, are incorporated in instruments, some added degree of protection is provided against the escape of m aterial in the event of an accident and the exemption lim its in

66 SECTION in 53 SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIV ITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) these cases m ay justifiably be increased. The added degree of protection is a ssessed as a factor of 1 0, i. e. in an accident only one tenth of the radioactive content is considered likely to escape from the instrument, thus leading to exemption lim its for individual item s which are ten tim es as high as those for m aterials This added degree of protection, however, is not available in the case of gases, so that the exemption lim its for gaseous sources incorporated in instruments and articles remain the same as those for m aterials Packaging reduces both the probability of the packed item s being damaged and the likelihood of radioactive m aterial in solid or liquid form escaping from the package. Accordingly, the package lim its for instruments and articles incorporating solid or liquid sources have been set at tim es those for individual item s With packages of instruments and articles containing gaseous sources, the packaging may still afford some protection against damage, but it will not significantly reduce the escape of any gases which may be released within it. The package exem p tion lim it has therefore been reduced by a factor of 1 0 only in this case.

67 54 SECTION m s e c t io n m - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) 329. It is important to note that, although the derivation of "exem p t" quantities as outlined above justifies their safe transport without special packaging or administrative requirem ents, careful consideration led to the decision to reduce these quantities by a factor of 10 for transport by post. This decision was taken because of the possibility of contaminating a large number of letters, p a rcels, e t c., which would subsequently be widely distributed, thus increasing the number of persons who would be exposed to the possibility of an intake of A 2. This reduction factor of 10 would also reduce the radiation level from a source which had escaped from its shielding to 0. 1 m R /h at 3 m (100 m R /h at 10 cm ), which was considered to be conservative enough for safety in the postal environment in comparison with what is already accepted for other modes of transport. Transport by post (Table II) 330. Radiation levels on unpacked instruments and articles: The further limitation on the radiation level from single unpacked instruments or articles (Section III of the Regulations, paras ) is intended to prevent excessive radiation exposure of persons who might pickup such item s in the event of an accident.

68 SECTION III 55 SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIV ITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) TABLE II. SM ALL QUANTITIES OF RADIOACTIVE MATERIALS Package lim its Nature of materials Other than By post by post Solids and gases Tritium 20 Ci 2 Ci Special form 10-3 Al 10"4 Aj Other forms 10-3 A2 1 0 " 4 a 2 Liquids Tritiated water 0.1 Ci/ Ci 100 Ci between 0.1 Ci/1 and 1.0 Ci/1 100 Ci 10 Ci 1.0 Ci/1 1 Ci 10-1 Ci Other liquids 10-4 A2 1 0 '5 a 2 ARTICLES M ANUFACTURED FROM N ATU RAL OR D EPLETED URANIUM AND N ATU RAL THORIUM 331. A ircraft counterweights made of depleted uranium and coated with an epoxy resin, the uranium shielding encased in m etal in shipping containers, and X - and gam m a-ray radiography and m edical treatment devices are exam ples of the kinds of

69 56 SECTION m SECTION n i - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIV ITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) article intended to be covered by the exem p tion for manufactured articles (Section III of the Regulations, para. 312). The inactive sheath should cover all readily accessible external surfaces of the uranium or thorium to absorb the alpha radiation emitted and reduce the beta radiation level at the surface of the m aterial. A sheath or other m eans, such as a m etal alloy, can be used to control the oxidation of the uranium or thorium and the consequent build-up of loose contamination on the surface of such item s. There is norm ally a requirement for such articles to be marked as containing uranium or thorium to prevent their inadvertently being machined or disposed of as scrap. E M P TY PACKAGES General 332. Empty packages which once contained radioactive m aterial present little hazard provided they are conscientiously cleaned to rem ove loose contamination and are in good condition so that they m ay be securely r e -se a le d The lim it for rem oval of non-fixed contamination, i.e. contamination which can be m easured on a sm ear (Section V of the Regulations, para. 502), has been set so that the activity remaining inside a 1 -m

70 SECTION III 57 SECTION in - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIV ITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) cube packaging is of the order of 10-3 a 2. For such a packaging, which has an area of 6 X 104 cm 2, contaminated to 100 tim es the level specified for the "oth er alpha em itters" in Table X I of the Regulations, the total activity on the inner surface is 60 n Ci. The 10 "3 A 2 values for 239Pu, 226Ra and 210Po are 2 /uci, 50 /uci and 200 n Ci, respectively. Likew ise, for beta-gam m a contamination,the total p ermitted surface activity is 600 pc i, and the 10'3 A 2 values for 90Sr and mixed fission products are 400 pci Of course, for a package to qualify for exemption from the packaging and labelling prescriptions of the Regulations, its external surface contamination must not exceed the levels in Section V, para. 502, and the radiation level at any point on its surface must not exceed 0. 5 m rem /h Packages which do not meet these additional requirem ents m ay be eligible for transport as low specific activity m aterial (Section I of the Regulations, para ) or, given an acceptable estimate of their contents, as Type A packages. Consignor 336. Preparation for shipment of empty packages: For shipment of empty packages

71 58 SECTION m SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC A CTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ITEMS EXEMPT FROM THE PRESCRIPTIONS ( ) (Section III of the Regulations, para. 313), the same procedures for closing the package should be followed as when the contents are still present, including making sure that the gaskets are present and in good condition and that the lid is in place and tightly closed Labels and marking: The radiation lab els, W hite-i, Yellow -II and Yellow -III, must be rem oved, obliterated or covered up, but other markings such as the type of package, the gross weight, etc., m ay remain visible. ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW SPECIFIC ACTIV ITY MATERIAL (LSA) ( ) BASIC PRINCIPLES 338. The basic reason for the introduction of a category of low specific activity m aterials into the IAEA Regulations was the existence of certain solid m aterials, the specific activities of which are so low that it is inconceivable that, under any circum stances arising in transport, a sufficient m a ss of such m aterials could be taken into the body to give rise to a significant radiation hazard. Uranium and thorium ores and their physical or chem ical concentrates are m aterials obviously falling into this category This concept was extended to include other solid m aterials on the basis of a model

72 SECTION III 59 SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW SPECIFIC ACTIV ITY MATERIAL (LSA) ( ) which assum es that it is m ost unlikely that a person would remain in a dusty atmosphere long enough to inhale m ore than 1 0 m g of m aterial. If the specific activity of the m a terial is such that the m ass intake is equi-* valent to the activity intake assum ed to occur for a person involved in a median accident with a Type A package, nam ely 10 6 A 2, then this m aterial should not present a greater hazard during transport than the quantities of radioactivity transported in Type A packages. This leads to a low specific activity lim it of 1 0 ' 4 A 2 /g On the above b asis, m aterial with a specific activity not exceeding 10-4 A 2 /g m ay.be regarded as inherently safe for transport, since no requirement need be placed on the quality of its packaging to lim it its hazard to acceptable levels However, there are two important implicit assumptions made in the derivation of this lim it which restrict the number of m aterials that can be considered to belong to this inherently safe category. F irst, the activity must be uniform ly distributed throughout the m aterial; and second, there m ust be no conceivable mechanism by which this specific activity could be increased during transport. Natural uranium and thorium and their ores and concentrates meet these requirem ents, since such processes

73 60 SECTION III SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC A CTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW SPECIFIC A CTIVITY MATERIAL (LSA) ( ) as leaching of o re s, corrosion of uranium m etal, e t c., will only leave the specific activity unchanged or lower it. The same is true of tritiated water, since evaporation leaves the concentration essentially unchanged, and dilution can, of course, only decrease it Strictly speaking, solutions of radioactive m aterials, on the other hand, should only be considered inherently safe if the specific activity of the solute is lim ited to 1 0 ' 4 A 2 /g. Sim ilarly, certain solid m aterials in which radioactivity may be incorporated could be included in the inherently safe category provided that any radioactive m aterial which can be leached from them by water has a specific activity not exceeding 1 0 " 4 A z/g. It would, of course, be possible to lower the specific activity of a solute, or the solid content of m aterial leached from a solid m atrix, by dilution with inactive carrier if the object were to render a solution or a solid inherently safe for transport purposes Each of the item s described in (b), (c) (e) and (f) of Section I of the Regulations, para , are inherently safe in the above sense. They m ay therefore be carried in bulk if desired, and there is no need to invoke full-load conditions of transport. No specifications are n ecessary for the quality of packagings when they are not carried in bulk form, other than that they

74 SECTION m 61 SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS: LOW SPECIFIC A CTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW SPECIFIC ACTIV ITY MATERIAL (LSA) ( ) should be strong enough to prevent the loss of m aterial during transport. It must be rem em bered that, although the radiotoxicity of these m aterials is low, it is not negligible and steps must be taken to ensure that unn ecessary and, particularly, repeated exposures do not occur The remaining two item s, (d) and (g) of Section I of the Regulations, para. 121, describe a category of m aterials which are not inherently safe in the sense discussed above in that their specific activity could be increased by p ro cesses occurring during transport. Item (d), for example, could include solutions of which the specific activity, 10"4 A 2/g when packaged, could increase during transport by evaporation. The solute could very well have a specific activity much in excess of the inherently safe level of A 2/g Contaminated objects described under Section I of the Regulations, para. 121(g), are, strictly speaking, not low specific a c tivity m aterials at all. However, the category has proved useful in the past and is essentially a carryover into the revised Regulations of item A (e) of the 1967 edition of the IAEA Regulations. The appropriateness of classifying surface contaminated objects as low specific activity m aterials has been discussed by W ilson [1],

75 62 SECTION III SECTION HI - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW SPECIFIC ACTIV ITY MATERIAL (LSA) ( ) whose work should be consulted for further elaboration of a number of the points raised above Because the m aterials under item s (d) and (g) are not, by nature, inherently safe, their transport'm ay be carried out only under full load conditions. TRITIATED W ATER (CONCENTRATION 10 C i/l IT R E ) 347. Although tritiated water can be r e garded as inherently safe below a certain concentration lim it, the m odel used to derive the low specific activity lim its for solids (i. e. involving the maximum inhalation of 1 0 m g of dust) is not applicable to tritiated water where the principal mode of its intake by the body will be either by inhalation of water vapour or by direct absorption of liquid through the skin However, in assessin g this concentration lim it it is appropriate to choose a wholebody dose lim it which is consistent with the dose used to determine the low specific activity lim its of other inherently safe m aterials. These are based on the assum ed inhalation of a maximum of 1 0 m g of m aterial, the specific activity of which is lim ited so that the resultant doses to appropriate

76 SECTION m 6 3 SECTION ni - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL ; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW SPECIFIC ACTIVITY MATERIAL (LSA) ( ) critical organs do not exceed those adopted for the a ssessm en t of the A 2 values. In the case of whole-body exposure, this dose lim it is 3 rem ; hence, this dose m ust form the basis of the determination of the concentration lim it for tritiated water The low specific activity lim it for tritiated water in the 1967 edition of the IAEA Regulations was 5.0 C i/1. The actual health physics justification for this level was not recorded. However, the dose calculations would have assum ed a quality factor for tritium beta particles of 1. 7 and a biological h alf-life for body water of 1 2 days, the then current values recommended by the ICRP Recently, the ICRP recommended a revised value of 1 0 days for the biological h alf-life of w ater4 and a value of 1. 0 for the quality factor. If these values had been used to derive the low specific activity lim it for tritiated water, the value appearing in the 1967 edition of the IAEA Regulations would have been 10 C i/ However, in the recent revision of the Regulations, the basis for the establishment of a low specific activity lim it for tritiated water was examined afresh. The model assum ed for the m ost likely mode of exposure during a transport accident involving 4 ICRP Publication 10.

77 64 SECTION m SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW SPECIFIC ACTIVITY MATERIAL (LSA) ( ) tritiated water was the dropping of a drum during a loading or unloading operation, the drum splitting open and a person being splashed so that a quarter of his body surface area becom es wet. Since the spill is m ost likely to occur in the open, considerable dispersion of the tritiated water vapour will take place, but intake via inhalation and skin absorption of water vapour will still be significant and must be considered as well as direct absorption of water through the wet skin. It is assum ed that a quarter of an hour is n ecessary for the person to take off his wet clothing and remove the water from his skin and, conservatively, that he r e mains in the area covered by the spill during this tim e. It is reasonable to assum e that fairly prompt attention would be given by the exposed person to drying him self, as he would be aware that he was handling a radioactive m aterial (a drum of tritiated water m ust be labelled LSA). Work published in Canada [ 2] enables an em pirically based estim ate to be made of the dose resulting from such an exposure. This shows that a whole-bo'dy dose lim it of 3 rem would be delivered under these exposure circumstances by tritiated water with a concentration of 10 C i/ The above form s the basis for the choice of the low specific activity lim it for

78 SECTION in 65 SECTION III - ITEM S EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC A CTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW SPECIFIC ACTIVITY MATERIAL (LSA) ( ) tritiated water in the revised Regulations. Fortuitously, this is the same as the value given in the 1967 edition of the Regulations, revised to take account of the m ore recent ICRP param eters for tritiated water It is important to appreciate that, with tritiated water of this concentration, it is m ost unlikely that there would be doses in excess of 3 rem as the result of other modes of exposure. For example, consider a drum of tritiated water with an unsuspected leak standing in a confined compartment. With any reasonably sized leak which could go undetected, and with virtually no ventilation, the atm osphere in the compartment could, in the course of a few weeks, reach one tenth of saturation with tritiated water vapour. With a liquid concentration of 10 C i/1, a person would have to breathe this atmosphere for one hour to achieve a whole-body dose of 3 r e m. ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW-LEVEL SOLID RADIOACTIVE MATERIAL (LLS) (317) BASIC PRINCIPLES 354. From the comments received by the IAEA during the revision of its Regulations, it became apparent that there was a need for a new category of radioactive m aterials, principally to accommodate certain types

79 66 SECTION HI SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC A CTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW-LEVEL SOLID RADIOACTIVE MATERIAL (LLS) (317) of consignment of low - and m ediu m -level radioactive w astes. It was suggested-that this category could be included under low specific activity m aterials, but, since this could only be done by violating the basic concept of a low specific activity m aterial still further, a new category of low -level solid radioactive m aterials was defined Essentially, this category extends the concept of non-inherently safe low specific activity m aterials defined in Section I of the Regulations, para. 121 (d) and (g), to m aterials with a distributed activity of up to twenty tim es the levels specified there, liquids and solutions being specifically excluded To compensate for the reduction in safety in this kind of m aterial as compared with low specific activity m aterial, special requirem ents are imposed on the standards of the packagings which must be used, and, in addition, transport may be effected only under full-load conditions. C O N S O L I D A T E D W A S T E S ( A V E R A G E S P E C I F I C A C T I V I T Y 2X10-3 A 2 /g) 357. Three classes of material are included under the definition in Section I of the Regulations, para The first, for

80 SECTION III 67 SECTION n i - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW-LEVEL SOLID RADIOACTIVE MATERIAL (LLS) (317) which the category was specifically formulated, is waste in which the radioactivity is consolidated in some solid binding agent such as concrete, bitumen, e tc., before storage or burial. The activity is essentially uniformly distributed and is re la tively fixed; in a sense, the radioactivity has been rendered into a "sp ecial fo r m ". In these cases, however, the activity is not entirely insolubilized in its m atrix and it is n ecessary to place a performance sp ecification on the m aterial. This is given in Section I of the Regulations, para (a)(ii) The leaching rate lim it of 0.1 A 2 per week was arrived at by considering the case of a block of m aterial in its packaging (e. g. a steel drum), which had been exposed to the weather and had taken in sufficient rain to surround the block with a film of water for one week. If this package is then involved in a handling accident, som e of the liquid m ay escape, and,on the basis of the standard model for determining A 2 values, of this m ay be taken into the body of a bystander. Since the drum must be of good quality, meeting the appropriate UN industrial packaging specification, some credit can be given for its ability to retain som e of its contents; it m ay not be as good in this respect as a Type A package, for which it is assum ed that only of the package

81 68 SECTION III SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC A CTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW-LEVEL SOLID RADIOACTIVE MATERIAL (LLS) (317) contents escape in a median accident, but it m ay well be good enough to lim it escape to of the dispersible contents. Since the total body intake must be limited to 1 0 " 6 A 2 to maintain consistency with the safety built into Type A packages, the dispersible radioactive contents of the drum ( i.e. the liquid) must therefore not exceed 0. 1 A It should be noted that, in a 200-litre drum of consolidated waste weighing, say, 500 kg, the total permitted activity according to Section I of the Regulations, para. 120(a)(iii), is 10s A 2. The maximum perm issible leach rate of 0. 1 A 2 per week means that the binding of the activity in the solid must be good enough to lim it loss by water leaching to % of the total contents per week in this case The second class of m aterial that, under certain circum stances, conforms to the definition in Section I, para. 120(a),is irradiated solid m aterial, throughout which the activation products are distributed; the distribution in this case need not be uniform. Provided that such m aterial can meet the leach rate specification and that the d istributed activity does not exceed 2 X 1 0 ' 3 A 2 / g, it may, if properly packaged, be transported under full-load conditions in an entirely safe m anner.

82 SECTION n i 69 SECTION III - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIV ITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW-LEVEL SOLID RADIOACTIVE MATERIAL (LLS) (317) 361. Finally, the definition permits a number of solid articles which contain activation products to be collected together and tran s ported in the same container. What was envisaged here was the transport of a m isc e l lany of activated waste solids which would norm ally be placed in a cavity in a concrete block and sealed in with additional concrete. The cavity is then effectively filled with a solid throughout which the activity is, and rem ains, distributed,although it will not, of course, be uniformly distributed. The outer concrete m ay be regarded as a container (although it m ay need to be supplemented with a steel drum to m eet the packaging specifications laid down for the transport of these m aterials) and the inner cavity and filled region as the radioactive contents. The activity averaged throughout this region m ust not exceed 2X 10-3 A 2 /g. If it is possible, under accident conditions, for the outer concrete shell to break away and leave the inner block exposed, the leach rate from this inner block must not exceed 0.1 A 2 per week. If there is no such possibility, it is sufficient to ensure that the leach rate from the whole concrete block does not exceed 0. 1 A 2 per week; in this case, however, an outer drum would be an obligatory part of the packaging rather than a convenient casing in which to cast the outer concrete container.

83 70 SECTION III SECTION in - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC ACTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) ALTERNATIVE TRANSPORT ARRANGEMENTS FOR LOW-LEVEL SOLID RADIOACTIVE MATERIAL (LLS) (317) OBJECTS OF NON-RADIOACTIVE M ATERIAL CONTAMINATED WITH RADIOACTIVE MATERIALS (H IG H -LEVEL CONTAMINATION) 362. Under part (b) of this definition, objects heavily contaminated with fixed radioactive m aterial may be transported if adequately shielded and packaged (i.e. in a package conforming to the appropriate UN specification) and carried under full-load conditions. The maximum permitted surface contamination levels set down here are twenty tim es those permitted under the low specific activity definition in Section I of the Regulations, para.121(g), and 2 X 105 tim es those listed in Table X I of the Regulations This represents surface beta dose rates of the order of r e m /h and radiation levels of som e 700 r e m /h at 30 cm from the surface. These m aterials are therefore potentially very hazardous, which is why packaging specifications must be laid down here Note that the contamination must be in a "n on -readily dispersible fo r m ", which means that the objects must be thoroughly cleaned to rem ove all loose contamination.

84 SECTION m 71 SECTION m - ITEMS EXEMPT FROM SPECIFIED PRESCRIPTIONS; LOW SPECIFIC A CTIVITY MATERIAL; LOW-LEVEL SOLID RADIOACTIVE MATERIAL ( ) R E F E R E N C E S [1] WILSON, A.R.W., Transport o f Radioactive M aterials (R. Gibson, Ed.) Pergamon Press (1966) 132. [2] ONTARIO HYDRO-ELECTRIC POWER COMMISSION, An Estim ate o f the Dose Resulting from a Spill o f Tritiated Heavy Water during Transportation, M.S.D. 70, Ontario Hydro Report, 2 March 1970,

85

86 SECTION IV SECTION IV - ACTIV ITY LIMITS ( ) GENERAL 401. A s in the previous Regulations [ 1, 2], the various lim its prescribed for control of radioactivity are based on the activity contents lim its established for Type A packages. The previous system, whereby radionuclides are classified into seven Groups for transport purposes, each Group having its Type A contents lim its for non-special form m aterial with a 20-C i lim it for special form m aterial ( i.e. m aterial which is nondispersible when subject to specified tests) irrespective of the Group, has been developed to the " A 1/A 2" system, whereby each nuclide has a Type A package lim it, A1 curies, when in special form and a lim it, A 2 curies, when not in special form. It is important to recognize that this system is a further development of that used for Group cla ssification [ 3-5 ], While the replacem ent of the Group classification system by the Aif A% system results in lower package lim its for som e nuclides, for the m ajority it results in a relaxation of the previously restrictive package lim its set on the basis of the m ost toxic nuclide in the Group. This should be of considerable help to users of radionuclides for m edical, engineering and research purposes The A1fA2 system may be sum m arized as follow s: 73

87 74 SECTION IV - ACTIVITY LIMITS ( ) SECTION IV Type A package Radionuclide Contents lim it (Ci) In special form Ai In non-special form ^2 Note: 1. Ax is based on the lev el o f external radiation from the radioactive m aterial released after breakage o f its container in the event o f an accident; it is assumed that there is no intake of the m aterial. 2. Ag is the lesser o f the two quantities and A3, A3 being a corresponding quantity based on the intake of radioactive m aterial dispersed after breakage o f its container in the event of an accident The Regulations (Section IV) give the A i and A 2 values for a large number of single radionuclides listed in Table VII and also prescribe the procedure to be followed for determining A i and A 2 values for radionuclides not so listed and for m ixtures. It should be noted that radionuclides whose A1/A2 values are given in the table as "unlim ited" are by virtue of their specific activities low specific activity m aterial as defined by the Regulations The replacement of the Ci Type A package lim it for special form, which was based on a m odel involving the release from a package of a 1 -M e V gamma em itter and consequent exposure of persons to external radiation [3], by an A i curie lim it for each nuclide represents an increase in safety with regard to em itters of gamma photons in excess of 1 M ev and also with regard to alpha, beta and neutron em itters for which assessm en ts based on specified m odels were made. In the case of nuclides for which the 20-C i lim it was unnecessarily

88 SECTION IV 75 SECTION IV - A CTIV ITY LIMITS ( ) restrictive, for example em itters of gamma photons with energy significantly le ss than 1 MeV, the new system perm its significantly increased Type A package lim its up to an arbitrary numerical maximum of 1000 Ci, which was set mainly to take account of both alpha and soft beta em itters. On the other hand, for a considerable number of nuclides, including cobalt-60, the A x value is less than the previous "a c r o s s the board" special form lim it of 20 Ci The Type A package lim it of A 2 curies for a radionuclide not in special form is the le sse r of the special form A j value for the nuclide based on external radiation exposure and the value (termed A 3) which was calculated for internal exposure resulting from intake (inhalation, ingestion or wound) of 1 0 " 6 of the package contents and used as a basis for Group classification [ 3, 4]. Since the Group Type A package lim its for nonspecial form were set according to the m ost toxic m em ber of the Group (the overall difference in radiotoxicity between the m ost toxic m em ber of Group I and the lowest toxic m em ber of Group IV Groups V -V II include noble gases and tritium is a factor of the order of 1 0 s), the resulting A 2 values r e present a relaxation of Type A package lim its for m ost nuclides. An arbitrary numerical maximum for A 2 has been set at 1000 Ci It might be argued that the replacement of the previous "sev en -G ro u p " system by what is virtually a Group for each radionuclide is not justified by the broad assum p tions underlying the m odels on which the A i / A 2 values have been calculated and that the values listed should therefore be rounded

89 76 SECTION IV SECTION IV - A CTIV ITY LIMITS ( ) off. It should be noted that the values listed have been rounded off to steps corresponding to an accuracy of 10%. Further rounding off of the first figure (other than 0 ) to the nearest 5 or 10 would, in effect, result in a system involving an increased number of groups with som e nuclides in one group when in special form and in another group when not in special form. A fter careful consideration, it was decided that such further rounding off should not be done until the implications for the transport of radionuclides for medical and other uses were clearly understood on the basis of several years of experience in using the A : / A 2 system The introduction of the A1/A2 system for derivation of Type A package lim its has, for the m ajority of nuclides, resulted in an increase of lim its. Consequently, it is important to recognize that, on the basis of an assessm en t [ 6] of heat liberation from a Type A package (the contents lim its of which are A 1 / A 2), therevisedr egulations correct a deficiency in safety of the previous Regulations by requiring that the prescriptions designed to ensure integrity in the event of development of temperature and pressure within the containment system, which previously applied only to large radioactive source packages, be applied to all packages whose contents exceed the Type A package lim its, i.e. to all Type B packages. A s was the case with the large radioactive source packages, no upper contents lim its are prescribed for Type B packages in the revised Regulations, hence the "theoretical range" of contents for this type of package is very wide indeed. To obviate the need to carry out heat assessm en t for Type B packages

90 SECTION IV 77 SECTION IV - ACTIV ITY LIMITS ( ) whose contents are relatively sm all in respect of this very wide range, a lim it of 15 W /m 2 is prescribed in the revised R egulations for the average surface heat flux of a package which may be carried amongst general cargo (not bagged or sacked) or within freight containers without any special stowage provisions [7], Guidance is given in this Advisory Document on the safe stowage of packages with higher heat fluxes (paras ) Although the prim ary purpose of the A 1(/A 2 system is to set contents lim its for Type A packages, the revised Regulations, like the previous Regulations [1, 2, 4], make effective use of the system to prescribe activity lim its: (a) for item s exempt from specified prescriptions; (b) for low specific activity m aterial; (c) for low -level solid radioactive m aterial; (d) for the specification of containment standards for Type B packages; (e) beyond which shipment approval is required for Type B(M) packages; (f ) beyond which notification of the competent authorities concerned of Type B(U) packages is required prior to shipment. A CTIV ITY LIMITS FOR TYPE A AND TYPE B PACKAGES ( ) TYPE A PACKAGINGS AND PACKAGES Since the quantities of radioactive m aterials which m ay be loaded into Type A packagings are lim ited so that a radiation

91 78 SECTION IV SECTION IV ACTIVITY LIMITS ( ) ACTIV ITY LIMITS FOR TYPE A AND TYPE B PACKAGES ( ) injury would not result even if the package were completely destroyed, such packagings are required to withstand only norm al conditions of transport, and design approval by the competent authority is only necessary when the contents are fissile and not exempt from the additional requirem ents for fissile m aterials specified in Section VI of the Regulations. The rationale behind the Type A package is that it provides economical tran s port for the large number of sm all-activity consignments while simultaneously providing a high level of safety. Experience to date has confirmed the wisdom of this rationale. It is envisaged that consignors of Type A packages will institute their own control procedures to ensure compliance with the regulatory requirem ents The maximum activity permitted in a Type A package depends on the form of radioactive m aterial. A1 is the maximum activity of radioactive m aterial in special form; A 2 is the maximum activity of radioactive m aterial in all form s other than special. The Aj and A 2 values listed in Section IV of the Regulations were derived by considering accident situations and are based on the assumptions given below. (a) A-l quantities The m aterial is in special form which provides the sam e degree of containment as Type B packaging in preventing the radioactive contents from dispersing to the environment.

92 SECTION IV 79 SECTION IV - A CTIV ITY LIMITS ( ) A C T IV IT Y L IM IT S F O R T Y P E A A N D T Y P E B P A C K A G E S ( ) (b) A 2 quantities The m aterial is not in special form In deriving the A i and A 2 values, it is assum ed that the Type A package experiences transport conditions worse than the "n orm al conditions of transport" and is damaged to the degree that the special form m aterial becom es completely unshielded or that of the dispersible contents are released from the package and a further 1 0 " 3 of these released contents are taken up by a single individual. In cases where a Type A package contains a m ore dispersible form of radioactive m aterial such as liquids or gases (so that m ore than 1 0 ' 3 of the total contents might be expected to be released), the Regulations insist that the packaging meet additional requirem ents. For gases and liquids, the package must be capable of withstanding the additional free drop and penetration te sts. For liquids only, the use of adequate quantities of absorbent m aterial is permitted as an alternative. DETERM INA TIO N O F A j A N D A 2 DETERMINATION OF A x ( ) 412. A j is the Type A package contents lim it for a radionuclide in special form. The calculations to derive values of A i for radionuclides are based on the following assum ptions: the shielding of the package is completely destroyed; the em ergency whole-body dose to a person shall not exceed 3 rem ;

93 80 SECTION IV SECTION IV - A CTIV ITY LIMITS ( ) D E T E R M IN A T IO N O F A j A N D A 2 ( ) the exposure time at a distance of 3 m from the exposed source shall not exceed 3 h, i.e. the radiation level shall not exceed 1 re m /h at 3 m from an exposed source. (a) Gamma em itters A j is determined by the expression: r is the gam m a-ray constant, corresponding to the dose in R /h at 1 m per Ci. (b) X -r a y em itters (by electron capture or internal conversion) It has not been considered n ecessary to calculate separate lim its for the few X -r a y em itters as m ost of them are relatively unimportant as special form m aterial. Consequently, only two A1 values have been selected, depending upon the atom ic number (Z )o f the nuclide, one for nuclides of Z S 55 and the other for those of Z > 55. The upper lim its of X -r a y energies for nuclides of these two categories are 55 kev and 130 kev, respectively. Since such sources will either be m assive non-friable or uncapsulated sources, it is reasonable to assum e absorption of the X -r a y s by an amount equivalent to 0. 5 mm of steel. With these assumptions, the A x figures are Z s 55 A j = 1000 Ci Z > 55 A j = 200 Ci

94 SECTION IV 8 1 SECTION IV - A CTIV ITY LIMITS ( ) d e t e r m in a t io n (c) Beta em itters OF At AND A2 ( ) jo se rate at 3 m from a pure beta source arises from : (i) beta particles with energies > 0.9 MeV, and (ii) brem sstrahlung. Experimental m easurem ents with a hard beta source, 90Sr, result in 1.7 R /h per curie at 3 m. A s the critical organ for such beta rays at 3 m is the skin, and the m aximum perm issible dose for skin is six tim es that for the whole body, a value of 6 re m /h is considered to be equivalent to the reference exposure rate of 1 R /h. It is reasonable to assume that, after an accident, surrounding m aterials such as the beta window protector, rem ains of packaging, e t c., will provide additional shielding which can be very conservatively estimated as a factor of 3 (equivalent to 0. 2 mm steel). With these assum ptions, the value A i for 90S r / 90Y will be 10 Ci. The same value is given to beta em itters with E max of 2 MeV or m o re. For beta em itters, the relation brem sstrahlung-to-beta-particle dose increases as the maximum energy of the source decreases; the brem sstrahlung becom es the only contribution to the dose below a maximum energy of 0. 9 M ev. The dose rate from soft beta em itters increases very sharply as the source is approached. Thus a calculation of A i lim its based upon brem sstrahlung alone at 3 m would mean a hazard in the event of someone approaching such a source. The

95 82 SECTION IV SECTION IV - A CTIV ITY LIMITS ( ) D E T E R M IN A T IO N O F A j A N D A 2 ( ) upper lim it of A x of 1000 Ci will provide reasonable protection in this somewhat im probable event. The following A x lim its were determined on the basis of the above considerations: E max(mev) A x (Ci) < < C < (d) Alpha em itters A rbitrary lim its for A j were calculated as follows: A1 =103 A 3 (see p a ra.41 3) (e) Neutron em itters In all cases of (cr, n) and (7, n) sources, the limiting A x figures are those for the alpha or gamma nuclides of the sources, i.e. Ai=2 Ci. The only spontaneous fission neutron source of practical importance is 252Cf, for which this value is confirmed by calculations of the equivalent dose rate at 3 m. (f) Nuclides emitting different kinds of radiation A1 is the m ost restrictive value of those determined for each individual radiation in (a) to (e) above.

96 SECTION IV 83 SECTION IV A CTIV ITY LIMITS ( ) d e t e r m i n a t i o n (g) Parent nuclides of short-lived daughters O F A i A N D A 2 ( ) d a u g h t e r n u c l i d e can be assum ed to come into equilibrium with the parent during transport (a maximum journey time of 50 days is assum ed), A± is calculated for both the parent and the daughter, and the m ost limiting of the two values is a s signed to the parent nuclide. For radionuclides emitting different kinds of radiation and not listed in Section IV of the Regulations, Table VII, A j is the m ost restrictive value of those determined for each individual radiation; in both cases, however, A1 is restricted to a maximum of Ci. If, for such nuclides, the parent decays into a shorter lived daughter of a h alf-life not greater than ten days, A i should be calculated for both the parent and the daughter, and the m ost limiting of the two values should be assigned to the parent nuclide. DETERMINATION OF A A 2 is the le sse r of A j, the Type A package lim it for special form, and a quantity A 3, derived on the basis of intake resulting from dispersion of contents r e leased from the package in the event of an accident; in other words, A 2 is the m ore restrictive of the value A 3, based on the internal radiation dose, and the value A 1( based on the external radiation dose. The method of deriving A 2 for the various rad ionuclides involves the following assum ptions: the likelihood of a "m a jor accident" which could cause the escape of a large

97 84 SECTION IV SECTION IV - ACTIV ITY l im it s ( ) D E T E R M IN A T IO N O F A i A N D A z ( ) part of the package contents is verysm all; as the result of a "m edian accident", 1 0 ' 3 of the radioactive contents may escape from the package [ 3-5, 8]; 1 0 ' 3 of the escaped contents m ay be taken into the body of a person in the vicinity of the accident [ 3-5, 8]; an em ergency intake must not exceed half of the maximum perm issible annual intakes for workers (which is also the quarterly lim it during working hours) given in B asic Safety Standards for Radiation Protection (1967 Edition), IAEA Safety Series No. 9 (Table IIA, column 4) The original values listed in R ef. [3] (upon which the Group system of the 1967 Regulations was derived) were based upon a quarterly intake lim it relating to the doses given below. In ICRP Publication No. 1, these quarterly lim its are modified as shown in the second column. O rgan IC R P IC R P Whole body, gonads, red bone marrow Skin, thyroid, bone Other single organs 3 rem 8 rem 4 rem 15 rem 8 rem The change in ICRP values between 1959 and 1966 results in a change in the A 3 (defined below) values by a factor of 2, with the exception of those for nuclides for which the critical organ is the whole body, gonads or red bone m arrow. It should be noted that the A 3 figures are in agreement with the quarterly intake lim its in Basic

98 SECTION IV 85 SECTION IV - ACTIV ITY LIMITS ( ) d e t e r m in a t io n Safety Standards for Radiation Protection of Aj a n d a 2 (1967 Edition), with the exception of a few ( ) cases where the intake by wounds is considered to be the limiting factor. DETERMINATION OF A 2 FOR RADIO NUCLIDES NOT LISTED IN SECTION IV (TABLE VII) OF THE REGULATIONS A 2 is the m ore restrictive of the fo l lowing two values: (1) the corresponding A lf and (2) the value A 3 obtained from Table III. TABLE III. RELATIONSHIP B ETW EEN A 3 AND THE ATOM IC NUMBER OF THE RADIONUCLIDE H alf-life H alf-life H alf-life Atom ic number less than 1000 days greater than 1000 days to 106 years 10e years 1 to 81 3 Ci 50 mci 3 Ci 82 and above 2 mci 2 mci 3 Ci DETERMINATION OF A± AND A 2 FOR NOBLE GASES AND TRITIUM 416. The methods of calculation and the param eters are taken from Ref. [5], O VERALL MAXIMUM LIMITS FOR A : AND A A s stated above, the A x lim its for soft beta em itters and X -r a y em itters are lim ited to 1000 Ci. The individually derived A j and A 2 lim its for other nuclides (soft gamma em itters or nuclides of very low toxicity) are consistent with this upper

99 SECTION IV - ACTIV ITY LIMITS ( ) D E T E R M IN A T IO N O F A j A N D A 2 ( ) lim it, but it is important to appreciate that m ost "calculated A / ' values in excess of 1000 Ci are of little practical importance. NUCLIDES OF LOW SPECIFIC ACTIV ITY 418. Natural uranium and thorium and depleted uranium are by definition (Section I of the Regulations, para.-121) low specific activity m aterials. Other m aterials, such as 238U, 232Th, 235U (pure nuclide), e tc., TA B LE IV. A C T IV IT Y LIMITS FOR TYPE A PACKAGES Nuclide AxCi A2 Ci i*c Co 7 7 aosr (soy) Y ?Cs p po pU ?C Pm Ir AU Mixed fission products

100 SECTION IV 87 SECTION IV - ACTIV ITY LIMITS ( ) DETERMINATION OF A! AND A 2 ( ) are also low specific activity m aterials on the basis of the provision in Section I of the Regulations, para. 121(d). Since LSA m aterials m ay be shipped in strong industrial packagings or even as bulk shipment under full load conditions, there is no need to prescribe a lim it for Type A packagings for the transport of such m aterials Table IV lists some examples of application of the principles stated above. NOTIFICATION LEVELS FOR TYPE B PACKAGES 420. A s was the case with large radioactive source packages in the 1967 Regulations, no upper lim it is prescribed in the revised Regulations for the contents of Type B packages. The design requirem ents underlying competent authority approval of Type B(U) packages are such as to reduce to a very low level the probability of release of activity from such a package as the result of an accident during transport. Because of the increased risk associated with damage to a package with contents of an activity high enough to be "intim idating", the Regulations specify an activity lim it beyond which the consignor must notify the competent authority of each country through or into which the package is to be transported. (Such notification is also required for all Type B(M) packages, for any transport movement by special arrangement, and for a F issile Class III package, the design of which is subject to m ultilateral approval.) A s the

101 88 SECTION IV SECTION IV - A CTIVITY LIMITS ( ) d eterm in a tio n Regulations also require certificates of o f a n d A, approval of Type B(U) package design to be ( ) sent to the competent authorities concerned before the first shipment, such information should be of considerable help to persons responsible for the provision of assistance in,the event of an em ergency. On a som e what arbitrary basis, it was decided that notification before each shipment of a Type B(U) package m ust be given for Type B(U) packages whose contents exceed 3X 1 03 A x or 3 X A 2, as appropriate, or 3 X Ci, whichever is the least. CONTAINMENT STANDARDS FOR TYPE B PACKAGES 421. The 1967 Regulations introduced the concept of specifying a containment standard for a large radioactive source package in term s of activity loss in relation to specified test conditions. The revised Regulations prescribe containment standards for Type B(U) and Type B(M) packages essen tially based on those previously used for packages for large radioactive sources r e quiring unilateral and m ultilateral approval, respectively. The activity leak rates agreed upon are listed in Table V and make use of the A 2 values for the radionuclides concerned instead of the previous Group lim its. Quantitative containment standards are not presented for Type A packages. It is important to recognize that the prescription of standards, in term s of activity lo ss, for packages which, under the 1967 Regulations, were term ed "Type B packages" does not represent a relaxation in

102 SECTION IV 89 SECTION IV - A CTIV ITY LIMITS ( ) DETERMINATION OF A1 AND A2 ( ) TABLE V. A C T IV IT Y LIMITS FOR CONTAINMENT STANDARD OF TYPES B(U) AND B(M) PACKAGES ^ s. Package A fter tests to sim ulate damage \ in Normal transport Severe accident Type B(U) A2 x 10-6 Ci/h A2 x io " 3Ci/week Type BCM) Not designed for continuous venting Type B(M) Specially designed to allow continuous venting A2 x l0-6 Ci/h Az x5 x 10-5Ci/h 85K r: Ci/week Other radionuclides: A2 Ci/week Note: A2 values for noble gases to be those for the uncompressed state. the standard of safety. The fact that the packaging previously had to m eet the prescription "prevention of loss or dispersal of contents" in respect of specified test conditions does not mean that it was of a higher standard than that required to m eet the quantitative lim its set for containment in the revised Regulations. In any event, applications for approval under the revised R egulations will have to make a case for compliance with a quantitative rather than a qualitative standard.

103 90 SECTION IV SECTION IV - ACTIVITY LIMITS ( ) REFERENCES [1] INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for the Safe Transport o f Radioactive M aterials, Safety Series No. 6, STI/PUB/40, IAEA, Vienna (1961). [2] INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for the Safe Transport o f Radioactive M aterials, 1967 Edition, Safety Series N o.6, STI/PUB/148, IAEA, Vienna (1967). [3] FAIRBAIRN, A., DUNNING, N.J., "T h e classification of radioisotopes for packaging", Regulations for the Safe Transport o f Radioactive Materials: Notes on Certain Aspects o f the Regulations, Safety Series No. 7, STl/PUB/32, IAEA, Vienna (1961) 23. [4] ASPINALL, K. J., FAIRBAIRN, A., The Classification of Radionuclides for Transport Purposes and the Derivation of Activity Limits in Relation to Package Requirements, UKAEA Rep. AHSB(RP) R 23 (1963). y [5] FAIRBAIRN, A., MORLEY, F., KOLB, W., "T h e classification o f radionuclides for transport purposes", the Safe Transport o f Radioactive Materials (R. Gibson, Ed.), Pergamon Press (1966). [6] BROOK, A.J., DIXON, F.E., Heat Liberation from Type A Packages with Contents as in the Draft Revised Regulations, IAEA Document Ref. PL-383, Third Revised Draft, November 1970, Appendix III, UKAEA Rep. AHSB(S)R 193 (1971). [7] BROOK, A.J., DIXON, F.E., Stowage Provisions to Ensure Safe Dissipation of Heat from Radioactive M aterial during Transport, UKAEA Rep. AHSB(S)R 193 (1971). [8] HAGSGARD, S. e t a l., "T h e release o f radioactive m aterial in the event of the destruction of a full Type A package", AB Atomenergi Rep. A.E. STK 306 S.S. 217 (1965).

104 SECTION V SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) SECTION V 501. The information in this Section is intended mainly for the guidance of carriers of radioactive m aterials in respect of their role and responsibilities in the safe tran s port of radioactive m aterials Regulations have been developed by the International Atom ic Energy Agency to promote the safe packaging and shipment of radioactive m a teria ls. These Regulations, which serve as the basis for other national and international regulations, have the advantage of providing international and intermodal uniformity for the safe carriage of radioactive m aterials The basis for safety in the IAEA Regulations is the following relationship: overall safety = design safety + operational safety. Design safety is provided by the packaging, which must be designed to comply with performance requirem ents under both norm al and accident conditions of transport, and by relating the packaging integrity to the hazard potential of the m aterials to be carried. Operational safety is provided by operational procedures carried out by the consignor or consignee and the carriers or their agents C arrier responsibilities under the Regulations are summ arized below. 91

105 92 SECTION V SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) (a) To obtain n ecessary information from the consignor especially particulars of the consignment, the consignor's certification and, where applicable, instructions for supplementary operational controls, full load conditions, tie-down arrangem ents, stowage requirem ents and any "sp ecia l arrangem ent" conditions. (b) To apply separation distances, during both storage and carriage, between packages of radioactive m aterials and areas norm ally occupied by personnel, radiationsensitive items such as undeveloped photographic film s, and other hazardous m aterials. (c) To apply transport index control during storage and carriage, thus preventing accumulations of packages of radioactive m aterials which m ay reduce the factors of safety built into the Regulations. (d) To placard vehicles as required. (e) To follow consignor instructions. ( f ) To handle and transport shipments safely and expeditiously. (g) To report any accident or unscheduled incident to the consignor or consignee and to authorities as required by local regulations An understanding of the relationship between the consignor and the carrier is important for the safe transport of radioactive m aterials. The Regulations require that the consignor meet all applicable parts of the Regulations (particularly packaging and preparation for shipment) and certify that he has done so (the "con sign or's certification "). The consignor m ust provide this

106 SECTION V 93 SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) certification to the carrier along with the prescribed "particulars of consignment" and any special instructions relating to stowage or supplementary operational controls for the shipment, etc Additionally, the consignor is in a position to provide technical support to the carrier in the way of assistance in case of accidents, checking vehicles and storage areas for possible contamination, information with regard to insurance requirem ents, and instruction of carrier personnel It is very important that information provided by the consignor should be tran s mitted between connecting ca rriers. W herever practicable, this information should be distributed to the ca rriers concerned by the consignor Before undertaking the carriage of radioactive m aterials, carriers should be aware of the procedures to be followed in the event of a transport accident involving radioactive m aterials One of the ca rrie r's responsibilities is the placarding of road and rail vehicles carrying radioactive m a teria ls. This placarding is required for two basic reasons: (1) to identify the presence of radioactive m aterials on a vehicle so that the n ecessary loading precautions (transport index lim itations, segregation from other hazardous or radiation-sensitive cargo) can be observed when additional cargo is loaded; and (2) to indicate the presence of radioactive m aterial

107 94 SECTION V SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) if the vehicle is involved in an accident. It is very important that vehicles be placarded as necessary and that placards be maintained in a legible condition. CONTAMINATION LEVELS 510. The level of non-fixed radioactive contamination, i.e. contamination which can be removed from a surface by wiping with a dry sm ear (Section V of the Regulations, para. 502), is measured on the sm ear. If the surface area tested is less than 300 cm2, the sm ear is taken over the entire surface area. The bases for the levels chosen are set forth in IAEA Safety Series No. 7 (1961). In applying the lim its, allowance m ay be made for knowing that certain contaminants are not present or that they are present in amounts less than 10% of the total activity of the contaminant. If the contaminant is known to consist prim arily of unirradiated natural or depleted uranium or unirradiated natural thorium, for example an aircraft counterweight which contains only depleted uranium and is known not to have been exposed to other types of contaminants, such contamination m ay be limited to 10-3 /u C i/cm If the isotopes in the contaminant are not identified, reasonable assumptions must be made about the decay schem e and the m ost limiting level must be used for that contaminant whose absence is not certain or which is known to be present in not m ore than 10% of the total activity.

108 SECTION V 95 SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) 512. R egardless of the level lim its, the nonfixed levels should always be reduced to the lowest practicable level; that is, all item s should be decontaminated regardless of the level if the cost of such decontamination is reasonable. TEST FOR N O N -FIXED RADIOACTIVE CONTAMINATION 513. The level of non-fixed contamination m ay be determined by wiping an area of 300 cm2 of the surface concerned (or the total surface area if less than 300 cm 2) by hand with a filter paper, or a wad of dry cotton wool, or any other m aterial of this nature. When large surface areas are involved the number of sm ear sam ples taken and the places where they are taken should be such as to ensure a reasonable rep resen tative assessm en t of the contamination of the whole surface. The dry sm ear, by removing a certain quantity of activity from the contaminated surfaces, gives a practical means of detecting the contamination on large packages such as flasks for irradiated fuel. jrhe problem, however, is obviously to evaluate the actual level of the surface contamination by assessin g the ratio of activity rem oved by the sm ear to the initial surface activity. Experience has shown that a ratio of 10% is reasonable. This rate does not take account of the efficiency of counting instruments required to convert counts into disintegrations per second for the evaluation

109 96 SECTION V SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) of surface contamination in^uc i/cm 2. Such efficiency depends on the type of instrument and the energy of the radiation. TRANSPORT INDEX 514. Determination of the transport index provides a basis on which the carrier can segregate radioactive m aterial from persons and undeveloped film and so contribute to the safety of transport of F issile Class II and III packages. After careful consideration of proposals from M em ber States, the revised Regulations now require radiation level m easurem ents for determination of the transport index to be made 1 m from the external surface of the package, as was the case in the 1961 Regulations, not from the centre, as in the 1967 edition. In addition to this simplification, the revised Regulations extend the definition of transport index to facilitate control of F issile Class III packages. RADIATION CATEGORIES 515. The revised Regulations continue to use three categories and their associated labels and, on practical grounds, have increased the upper lim it for Category II Yellow from 10 mr to 50 m rem per hour on the surface and from 0.5 to 1.0 transport index. For Category III Yellow packages carried as a full load by road and rail, the revised

110 SECTION V 97 SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) Regulations allow a maximum surface radiation level of 1000 m r e m /h, provided that specified conditions to m inim ize exposure of persons are m et. It is important to note that all F issile Class III packages will require the Category III Yellow label. FREIGHT CONTAINERS 516. Because of the rapidly increasing use of freight containers in all modes of tran s port, the revised Regulations require that those used for the transport of radioactive m aterials be of a permanently enclosed character, rigid and strong enough for r e peated use, and be fitted with devices facilitating handling, particularly during transfer from one mode of transport to another. Except in the specific case given in para. 520 below, the Regulations lim it the transport index for a freight container to 50 and allow this index to be determined either by summing the transport indices of the packages carried inside it, or, when the packages are carried as a full load, by m easuring the radiation level (m rem /h ) at 1 m from the container's external surface, ^"^rovided that, if it contains a F issile Class II gackage(s), the greater number is used. For freight containers carrying a F issile Class III package(s), the transport index is assum ed to be 50 in all cases The Regulations require freight containers to be labelled on the following basis:

111 98 SECTION V SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) (a) Category I-W HITE including no packages of a higher category. (b) Category II-Y E L L O W transport index not exceeding 1.0. (c) Category III-YELLO W transport index exceeding 1. 0 or when the container is carrying a F issile Class III package or when the container is being transported under special arrangem ent For storage of freight containers in transit and their carriage by sea, the Regulations prescribe a transport index limit of 50 for each group and require a separation distance of 6 m between such groups (which, in a ship, can be filled by freight containers not containing radioactive packages). For storage, this separation distance is not required if the groups are separated by a permanent barrier such as the wall of a building On the basis of the definition that sm all freight containers either have an overall outer dimension of less than 1.5m or an internal volume of not more than 3.0 m 3, and provided that the total transport index in any hold or deck area does not exceed 200, the Regulations impose no lim it on the total transport index for all other freight containers aboard a single v e sse l. For radioactive m aterial in packages or sm all freight containers, the transport index lim it for a v essel is 200 as in the previous Regulations.

112 SECTION V 99 SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) For road and rail transport, the large freight container concept also enables the Regulations to allow the total transport index for such a container not containing F issile Class packages to exceed 50, provided that the persons loading the freight container have shown by measurem ent that the radiation levels during norm al conditions of transport will not exceed 200 m r e m /h at any point on, and 10 m rem /h at any point 2 m from, the container's outside surface and that each of its four vertical walls are placarded. TRANSPORT ( ) General requirements ( ) 521. The Regulations provide for the carriage of packages of radioactive m aterials in freight containers. The carrie r's responsibilities for freight containers are generally sim ilar to those for road and rail vehicles. The consignor and/or the inform a tion provided by the consignor should be consulted before loading a package of radioactive m aterials into a freight container; this is particularly important in respect of stowage requirem ents to ensure safe dissipation of heat The Regulations provide for so-called "fu ll-lo a d " shipments which are under the control of the consignor (even during carriage) with resultant relaxation of regulatory requirem ents. When handling or carrying a "fu ll-lo a d " shipment, the carrier must follow the consignor's instructions closely, particularly during trans-shipm ent Before contracting to carry bulk shipments of radioactive m aterials (such as

113 100 SECTION V SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) TRANSPORT ( ) General requirements ( ) radioactive o res, e tc.) the carrier must either be capable of carrying out the radiation surveying and possible decontamination of the transport conveyance on completion of the transport operation or must make arrangements to this end with the consignor For som e types of shipment (especially Type B(U) with contents exceeding specified lim its, Type B(M), F issile Class III, and special arrangem ents), the consignor is r e quired to provide advance notification of shipment to the competent authority of each country through or into which the shipment will p ass. Although this is the consignor's responsibility, the carrier m ay become involved in providing information, advising of changes to shipment itinerary, etc. The responsibilities in this regard must be clearly defined and agreed upon between consignor and carrier In some cases, for practical reasons, it is convenient for the consignee to act as the consignor's agent or even take over responsibility for the transport during the latter part of a journey. The carrier should be aware of any such arrangem ent and, particularly, of the point at which transfer of responsibility takes place. STOWAGE TO ENSURE HEAT DISSIPATION 526. Some Type B packages of radioactive m aterials may give off heat. This is a

114 SECTION V 101 SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) TRANSPORT ( ) General requirements ( ) result of radiation energy being absorbed in the shielding of the package and converted to heat energy which is transferred to the surface of the package and thence to the ambient a ir. Such heat dissipation capability is designed into the package and r e presents a safe and norm al condition. However, ca rriers must be careful not to reduce the heat dissipation capability of the package by sheeting the package up or by overstowing or close-packing it with other cargo which m ay act as therm al insulation. When packages of radioactive m aterials give off significant heat, the consignor is required to provide the carrier with instructions on the proper stowage of the package Provided that the heat load of a package in watts does not exceed a, where 'a 1is the effective radius of the package in centim etres [1], the heat will be effectively dissipated from the package by conduction alone. This means that if such a package becom es buried in loose bulk cargo it will not overheat Packages containing sources producing a heat flux at the package surface of less than 15 W /m 2 may be safely stowed for any length of time amongst packaged general cargo in any position within a vehicle, hold or freight container, and no special spacing provisions are required around such packages. Effective heat transfer will result from convection by air seepage through the gaps likely to exist in such general cargo. A close-fitting assem bly

115 102 SECTION V SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) TRANSPORT ( ) General requirements ( ) of such packages can be regarded as a single package, provided that the 15 W /m 2 limitation applies to the enveloping surface area of the assem bly To facilitate convection of heat by air seepage around their outer surface, packages subject to transport amongst packaged general cargo should be designed so that clearances at least 1 cm wide are likely to exist around the m ajor part of their outer surface Packages with average surface heat fluxes in excess of 15 W /m 2, but not exceeding 50 W /m 2, should be stowed in a vehicle, hold or freight container with a clearance around them of at least half the vertical height of the package, and im m ediately adjacent cargo should not reach a height above the package of m ore than half the vertical height of the package. Other cargo in the vicinity of such a package should not approach closer than 30 cm to the top of the hold or freight container Packages whose average surface heat flux exceeds 50 W /m 2 but whose peak surface heat flux is less than 90 W /m 2 may be safely transported provided that therm al radiation from such packages is unimpeded. In view of variations of heat flux over the package surface, packages with average heat fluxes in excess of 50 W /m 2 should be subject to thermal assessm en t as to whether tran s port under full load conditions is necessary. Should assessm ent indicate that full load

116 SECTION V 103 SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) TRANSPORT ( ) General requirements ( ) transport is unnecessary, the package should, if practicable, be stowed above the level of adjacent cargo to a ssist radiative heat lo ss Packages whose peak surface heat flux is likely to exceed 90 W /m 2 should be transported according to the full load r e quirements of the IAEA Regulations unless assessm en t by a heat transfer specialist shows this to be unnecessary. While any specific conditions to ensure effective heat dissipation from any such package should always be based on an assessm en t by a heat transfer specialist, it is anticipated that no real difficulty in ensuring heat dissipation will arise in practice with packages whose surface heat flux does not exceed W /m 2 over their exposed surfaces Provided that the stowage conditions meet the requirem ents of para. 530 above, any number of packages, or assem blies of packages complying with the requirements of para. 528 above, may be carried in a single vehicle, hold or freight container with the exception of packages which do not rely on heat loss by convection and radiation from their outer surface [2], For single packages other than those required to be transported under full load conditions, and for a number of packages transported according to the conditions prescribed in para. 530 above, no special ventilation provisions are n ecessary.

117 104 SECTION V SECTION V - CONTROLS FOR TRANSPORT AND STORAGE IN TRANSIT ( ) TRANSPORT ( ) General requirements ( ) 535. For sea transport, the therm al flux lim its given in the above recommendations can be raised if the use of holds below the waterline is guaranteed [ 3]. TIEDOWNS Tiedowns m ay be necessary to secure the package of radioactive m aterials to the transport conveyance. Tiedown equipment and instructions will som etim es be provided by the consignor and, in such cases, such equipment and instructions must be used and followed. Where no such instructions and equipment are provided, it is the carrie r's responsibility to secure the package to the conveyance. Light-weight packages being carried in closed conveyances do not present a problem in this respect. However, packages of heavy radioactive m aterials must be well secured to the transport conveyance, since, in the event of a sudden or em ergency stop of the conveyance, the packages and their momentum may have the destructive capability of a w recker's ball. Many packages in which high-density m etals such as lead are used for radiation shielding may have a deceptively high weight in relation to their volume. When the carrier is in should LIFTING TACKLE V ery heavy packages of radioactive m aterials, such as those for irradiated

118 SEC TIO N V 105 SEC TIO N V CONTROLS FOR TRAN SPORT AND STORAGE IN TRAN SIT ( ) TRANSPORT ( ) G en eral requirem ents ( ) reactor fuels, m ay have special lifting beams and tackle for use by carriers. W hen provided, such equipment must be used in accordance with the instructions provided by the consignor. In some countries, such equipment m ay not be used unless evidence is provided that it has been tested and inspected in accordance with statutory regulations. LEAKING PACKAGES AND CON TAM INATED CONVEYANCES ( ) 538. The Regulations include a prescription concerning decontamination of conveyances (Section V, para. 552) and in this respect require that residual radiation levels, after the removal of non-fixed radioactive contamination to below prescribed levels (Section V, para. 502, Table XI), be declared safe by a competent person Experience in the transport of irradiated fuel has shown that, when flasks are "dunked" or immersed in ponds at the reactor facility for purposes of loading, radioactive contamination can "sweat out" during transport, in spite of subsequent decontamination of the flask surface prior to transport to below the levels specified in Section V, para. 502, with the result that the contamination levels of parts of the flask surface of the conveyance m ay exceed the levels specified Although this problem m ay be alleviated by the provision of a "skirt" around the flask during its immersion in a contaminated pond, it is to be expected that careful consideration will be given to design provisions

119 106 SEC TIO N V SEC TIO N V - CONTROLS FOR TRANSPORT AND STORAGE IN TRAN SIT ( ) LEADING PACKAGES AND CON TAM INATED CONVEYANCES ( ) to obviate the need to "dunk" transport flasks in contaminated ponds. However, because of existing facilities, a contamination problem affecting transport of irradiated fuel will remain for some time to come It appears that solubles, particularly 137C s / 134Cs, can penetrate into the paint of a flask surface and that 60Co can penetrate into a stainless steel surface. Although both solubles then appear to be "fixed", exposure of the surface to a shower of rain during transport can convert such activity to a "non-fixed" condition with consequent contamination ("fixed" and "non-fixed") of the conveyance The example in the Annex to this Section outlines the procedure which has been used in one particular railway system to derive a safe working limit (Section V, para. 552) for radiation levels on rail vehicles that resulted from the transfer of contamination as described above. It must be stressed that, as the example is included here only to illustrate the method of derivation used, the derived working level (D W L ) is not intended for general application. C U STO M S (5 5 4 ) G E N E R A L 543. The Permanent Technical Committee of the Customs Co-operation Council has examined the problem of safety in customs operations involving the examination of

120 SEC TIO N V 107 SEC TIO N V ~ CONTROLS FOR TRANSPORT AND STORAGE IN TRAN SIT ( ) CUSTOM S (5 5 4 ) packages containing radioactive materials, and has agreed to issue the following recommendations: (a) clearance formalities should be carried out as quickly as possible; (b) internal inspection of packages containing radioactive material shall be waived if the nature and description of the goods can be established to the satisfaction of the customs authorities and if there is no suspicion of fraud; (c) any necessary internal inspection shall be carried out at places where adequate protection measures are available and radiation safety practices are observed These recommendations are of im portance, not only to avoid radiation risks to customs officers, but also to eliminate the delays in customs clearance which have occurred in the past and m ay decrease the usefulness of valuable radioactive material. This applies in particular to material for therapeutic purposes, which usually has only a short active life. S P E C IF IC A D V IC E 545. Customs authorities should identify and co-operate with regulatory authorities for the transport of radioactive materials so that they are aware of: (a) types and numbers of packages of radioactive materials which are likely to be encountered in customs examination;

121 108 SEC TIO N V SEC TIO N V - CONTROLS FOR TRANSPORT AND STORAGE IN TRAN SIT ( ) C U STO M S (5 5 4 ) (b) qualified persons equipped with radiation measuring instruments who could be contacted in the event of customs officers wishing to open a package for inspection or in the event of the receipt of a damaged package which might present a radiological hazard; (c) national regulations for the handling, storage and transport of packages of radioactive materials Packages which contain radioactive material can be identified by the customs officers, either by the label or, for exempt materials, by the transport documents Customs officers m ay have to make arrangements for; (a) examination of undamaged packages; (b) examination of packages that have received slight damage under normal transport conditions; (c) temporary storage of undamaged packages; (d) temporary storage of packages that have received slight damage under normal transport conditions The provisions of Section V of the Regulations, para. 554, should be observed during the examination of undamaged packages The provisions of Section V of the Regulations, para. 554, should also be observed during the examination of packages that have received slight damage under

122 SEC TIO N V 109 SECTIO N V - CONTROLS FOR TRANSPORT AND STORAGE IN TRAN SIT ( ) CUSTOM S (5 5 4 ) normal transport conditions, (ijowever, it is first necessary to handle the packages when moving them to the place where the examination can be performed. Such simple handling procedures need not necessarily be undertaken in the presence of a qualified person. In most cases, a customs officer could himself immediately place a package that has suffered such minor damage in an isolated secure place where it would await the arrival of a qualified person.^j No person should either remain near the package (a separation distance of 3 m would be sufficient) or touch it unless absolutely necessary. However, if the consignment comprises the low-level solid radioactive materials specified in Section I of the Regulations, para. 120(a), or the low specific activity materials specified in Section I, para. 121(d), (e) and (f), the customs officers should not handle the damaged packages without the advice of a qualified person The provisions of Section V of the Regulations, paras , should be observed during the temporary storage of undamaged packages Packages that have suffered slight damage under normal conditions of transport should be placed for temporary storage in an isolated secure place. A qualified person should then be summoned. During such storage, the separation distance between the damaged packages and all persons should be as great as practicable.

123 110 SEC TIO N V SECTIO N V - CONTROLS FOR TRANSPORT AND STORAGE IN TRAN SIT ( ) R E F E R E N C E S [1 ] BROOK, A. J., DIXON, F. E., Stow ag e Provisions to Ensure S a fe D issip ation o f H eat from R ad io activ e M a te ria l during Transport, UKAEA Rep. AHSB(S)R 193 (1971) p a ra.11. [2 ] ib id., paras [3 ] i b i d., paras , ANNEX D E R IV A T IO N O F S A F E W O R K I N G L IM IT, IN T E R M S O F E X T E R N A L R A D IA T IO N, F O R " F I X E D " A N D "N O N - F IX E D " C O N T A M IN A T IO N O N S U R F A C E S O F R A I L V E H IC L E S The present m axim um permissible level (M P L ) of beta/gam ma contamination is 10'4 /LiCi/ cm2. Application of this M P L to "non-fixed" contamination will prevent any hazard from inhalation or ingestion. Both "fixed" and "non-fixed" contamination, however, represent a potential source of external radiation for railway workers whose job it is to handle the rail vehicle. The relevant m axim um permissible doses re commended by the International Commission on Radiological Protection are as follows: Whole body, penetration radiation 0.5 rem in a year, Skin 3 rem in a year, Hands 7.5 rem in a year.

124 ANNEX T O SECTIO N V 111 SEC TIO N V - CONTROLS FOR TRAN SPORT AND STORAGE IN TRAN SIT ( ) In the case of surface'contamination, the beta dose predominates. For instance, beta/gam ma dose-rate ratios varying from 50 : 1 to 200 : 1 have been calculated for disc sources of 3000 MWd/tonne uranium with cooling periods of between 33 days and 5 years. It is apparent, therefore, that irradiation of the skin or hands will be more limiting than whole-body exposure to gam m a radiation. In addition, the beta dose rate falls off sharply with distance; for instance, there is a reduction by a factor of about 3 in the dose rate from an infinite plane beta source at a distance of one foot, and, with point sources, the attenuation with distance is even greater. It is thus clear that the risk of the skin of the hands being exposed is greater than that of skin on other parts of the body being irradiated. In the course of their duties, certain m em bers of the railway staff will come into contact with the rail vehicles, e.g. loading inspectors, breakdown crew s. It is estimated that the maximum time any individual (e.g. a loading inspector) is likely to spend in contact with, or in the immediate vicinity of, a vehicle is one hour per week. O n the basis of this time, a derived working limit (D W L ) can be calculated as follows: M axim um permissible hand dose = 7. 5 rem in a year On the basis of a m axim um hand contact time of 1 h/week for any individual, total contact time = 50 h in a year.

125 112 ANNEX T O SECTIO N V SEC TIO N V - CONTROLS FOR TRANSPORT AND STORAGE IN TRAN SIT ( ) Therefore, on this assumption, the surface dose rate corresponding to the m axim um permissible hand dose = 150 m r e m /h (It should be noted that a uniform contamination level of 10-4 /uci/cm 2 beta/gamma, the present contamination M P L, derived on the basis of transfer and subsequent ingestion of "non-fixed" contamination, will produce a dose rate of only about 1 m r e m /h. ) A series of measurements was carried out on fuel element transport flasks and rail vehicles, in which the surface dose rates measured with Instrument Type 0030 and lithium borate thermoluminescent dosemeters were compared. The ratio of the beta/gamma dose rate measured with T L D to that measured with Instrument Type 0030 varied from about 2 to 10, with a m ean value of 4.5. The T L D dosemeter measures the dose rate in a thickness of 40 m g /c m 2 of lithium borate powder covered with a P V C sachet of thickness 15 m g /c m 2. Under these conditions, it is calculated that the dosemeter would underestimate the skin dose (the skin dose is assumed to be the dose delivered to the tissue through an equivalent thickness of 7 m g /c m 2) from a caesium-137 source by a factor of 3. The factors for higher energy beta emitters would, however, be significantly lower. The contamination on the rail vehicle (well area) tends to occur in small discrete patches. Measurements made with an extended plane source of contamination gave a much lower T L D : ratio of less than 2. After combining these factors,

126 ANNEX T O SEC TIO N V 113 SEC TIO N V - CONTROLS FOR TRANSPORT AND STORAGE IN TRAN SIT ( ) it is reasonable to assume that the derived working limit as measured with the Instrument Type 0030 will be 15 m r e m /h. In another series of experiments, meas urements of contamination on transport flasks and rail vehicles taken with an Instrument Type 0030 were compared with those made with a B1 2H probe. Tw o ratemeters, Types 1828 and R M 2, were used with the probe, and the results were in good agreement with each other. The following approximate relationship was established, after averaging over a statistically significant number of results: 15 m r e m /h, beta/gam ma, indicated on 0030 =750 counts/s, beta/gamma, indicated on B1 2H probe. It is therefore proposed that the 750 counts/s, indicated on the B1 2H probe, be adopted as the D W L. It is further proposed that the above D W L s should only be applied to the wellarea framework which supports the transport flask. Contamination levels on other parts of the rail vehicle should not be allowed to exceed the limit of 10"4 ^ C i /c m 2, beta/gam ma, currently recommended by the IA E A. The D W L is extremely conservative for the reasons given below. (a)- Contamination occurs only in small patches, over a very small fraction of the exposed surfaces of the rail vehicles. It is therefore highly unlikely that the operator hands touching the vehicle will often be in contact with contamination.

127 114 ANNEX T O SECTIO N V SEC TIO N V - CONTROLS FOR TRANSPORT AND STORAGE IN TRAN SIT ( ) (b) Beta dose rates fall off sharply with distance from the surface of the rail vehicle, and it is unlikely that the operator's hands will be in actual contact with the rail vehicle for the full one hour per week allowed in the assessment.

128 SECTION VI SEC TIO N V I - FISSILE M ATERIALS ( ) B A SIC P R IN C IP L E S 601. The principle adopted for the definition of fissile material in Section I of the Regulations, p ara.117, is to include only those fissile radionuclides which are either known to be available or are likely to become available for transport in quantities which are significant in relation to criticality safety. It should be noted that the revised Regulations have extended the provisions whereby packages containing fissile material limited as to quantity, enrichment or concentration m ay be exempt from the specific provisions for the Fissile Class packages On the basis of this definition, Section VI of the Regulations, para. 601, then permits packages containing fissile material limited as to quantity, enrichment or concentration to be exempt from the specific provisions for Fissile Class packages The basic safety principles underlying the design of Fissile Class packages are set out in Section VI of the Regulations, para They are aimed at ensuring that, when Fissile Class packages are transported, criticality cannot arise as a result of any circumstances of transport. Circumstances envisaged include the possibility of damage to packages, neutron interaction between packages and neutron moderation and reflection by materials common to the transport environment, particularly water. 115

129 1 1 6 SEC TIO N VI SEC TIO N VI - FISSILE MATERIALS ( ) 604. There are three classes of Fissile package termed I, II and III. A Fissile Class I package is inherently safe because of its design; in the case of Fissile Classes II and III, limitation of number and this limitation combined with other operational controls, respectively, are required to supplement the safety incorporated in the design of the package. A n allowable number is defined in Section VI of the Regulations, para. 619, for Fissile Class II packages, and examples which comply with Fissile Classes I, II and III are given While in no way detracting from the value of Fissile Class I packages, the revised Regulations promote the use of Fissile Class II and Fissile Class III packages. Under the Regulations, a Fissile Class III package was required to be transported under the "special arrangement" prescription; this requirement is now removed. To facilitate the international movements of Fissile Class II and III packages, the revised Regulations give examples for which no further competent authority approval of package design is re quired subject to compliance with specified conditions. However, in view of the im portance of ensuring that the countries concerned are given the opportunity of examining the operational controls and their application, all shipments of such packages continue to be subject to multilateral approval. A P P L I C A T I O N O F P A C K A G I N G T E S T S T O FISSILE C L A S S P A C K A G E S 606. Any Fissile Class package must comply with the radiological safety require-

130 SEC TIO N VI 117 SEC TIO N V I - FISSILE M ATERIALS ( ) merits of the Regulations concerning activity content and packaging standard. In respect of the packaging standard, the tests as set out in Section VII of the Regulations provide a means of ensuring this. In addition to using these tests to ensure radiological safety, the Regulations also use them as a means to assess the integrity of a Fissile Class package for the purpose of criticality; this essentially involves knowing to what extent the package and its components m ay be deformed and penetrated by water. It should be understood that, whereas Fissile Class Packages must survive these tests to qualify as Type A or Type B, they must be assessed in the light of the tests for transport criticality certification. For this purpose, they are not required to survive the tests, but the assessed results of the tests will be used for criticality assessment. A C C I D E N T E N V I R O N M E N T - S IM U L A T IO N O F D A M A G E 607. Whereas the 1967 Regulations used tests to simulate the damage resulting from one kind of accident, namely a severe impact followed by a fire, it is important to recognize that the 1973 Regulations have included a further and quite separate accident condition, namely the 15-m water immersion test, which is intended to simulate the damage resulting from an accident in which a package becomes im mersed in deep water, which can happen, for example, during its transfer from a ship to a barge. In other words, the environmental evaluation of a Fissile Class package,used for the purpose of criticality

131 118 SECTIO N VI SEC TIO N V I - FISSILE M ATERIALS ( ) computation,is based on the condition of the package after two quite separate accident conditions: (a) the condition of the package after its subjection to the mechanical and thermal tests, in that order, following which, unless the designer is prepared to allow the criticality specialists to assume the presence of water in the worst possible places and quantities within the package, the 0. 9-m water inleakage test must be carried out as specified in Section VII of the Regulations, p ara.724; (b) the condition of the package after immersion in 15 m of water. Whichever is the most limiting case will then form the basis of the criticality certification. F ISSILE C LASS I A N D II P A C K A G E S 608. It is also important to recognize that the provisions specific to Fissile Class I and II packages as set out in Section VI of the Regulations provide a means of ensuring safety under two quite separate requirements: (a) that a single package cannot give rise to a criticality incident during transport; (b) that specified assemblies of packages m ay travel together safely. FISSILE C LASS III P A C K A G E S 609. Fissile Class III packages m ay be nuclearly safe by reason of specific controls imposed on them during shipment and, consequently, actual approval for each shipment

132 SEC TIO N VI 119 SEC TIO N VI - FISSILE M ATERIALS ( ) must be obtained from each country involved, thus ensuring that all necessary checks can be made as to the availability of the requisite control facilities. A s such checks can be very time-consuming, designers are advised to design to Fissile Class I or II when frequent shipments are necessary on a routine basis. T E S T S F O R N E U T R O N A B S O R B E R S 610. W hen the packaging for a Fissile Class package is deliberately designed to include a neutron absorber or "poison", the design should be such as to facilitate verification, during scheduled maintenance, of the presence of that poison, for example cadmium sheet, in a good condition. In addition, the designer should consider what tests m ay be used to confirm the presence and distribution of neutron poison as required by Section VII of the Regulations, para (Inclusion of examples of such tests is especially invited for future issues of this document.) D E S IG N E R 611. In addition to the advice in paras , the following advice is given to a designer of packaging for fissile material: (a) liquid neutron poisons should not be used because their loss represents an. additional safety risk compared with that of solid poisons; in addition, voids may occur in unfavourable positions of the package or there can be a build-up of pressure;

133 120 SEC TIO N VI SEC TIO N VI - FISSILE M ATERIALS ( ) (b) as far as practicable, the requirement that the package diameter be subcritical should be taken into account in the design; (c) if birdcages are used to ensure a minimum distance between packages, the holes in the birdcages should be small enough to ensure that other small packages also containing fissile materials will not pass through the birdcage fence. M A N U F A C T U R E R 612. It is essential that each item of packaging should conform to the specification approved by the competent authority. This is particularly important with respect to closures, especially as regards the joint and jointing material. The manufacturer should be aware of the requirements of the regulatory prescription "quality control". In this respect, it is particularly important that arrangements be made to ensure that any material specified by the designer to be included in the packaging as a built-in neutron absorber is either: (a) not omitted as a result of error, or (b) replaced by some other material which the person actually making the packaging might think would serve the purpose of the intended material; for example, if cadmium is specified for inclusion in packaging to be used under the terms of Fissile Class I, it is imperative that it is not replaced by some metal which is of similar appearance, e.g. zinc Consequently, it is advisable that a rigorous inspection procedure be applied

134 SEC TIO N VI 121 SEC TIO N V I - FISSILE M ATERIALS ( ) during manufacture to ensure the incorporation of any built-in poison to each packaging actually made and that a simple form of certification to this effect be used between the inspector and the customer he serves. CONSIG N O R 614. The transport index system as defined in Section I of the Regulations, para. 137, provides a means whereby the carrier can effect any requisite control during transport without a special label for fissile material being necessary. Consequently, it is imperative for the consignor to ensure that the labelling is carried out in strict accordance with the requirements of Section V of the Regulations, paras It is also particularly important for the consignor to implement the requirements of Section VIII of the Regulations, para. 832, which is concerned with the provision of information for carriers. This should be done by instructions written in an appropriate way for the personnel concerned; in this respect, instructions to ensure proper transfer from one carrier to another are especially important When a consignment is despatched under the terms of an example given under Section VI of the Regulations, paras , it is most important that arrangements be made to ensure observance of the transport controls specified therein The consignor should not despatch fissile packages of Class I, II or III until the consignee has indicated his readiness

135 122 SEC TIO N VI SECTIO N V I - FISSILE MATERIALS ( ) to receive them. Whilst it is recognized that this is not strictly relevant to the actual transport operation, failure to observe this precaution may result in the nonacceptance of delivery by the consignee, or compromise the consignee's criticality control procedures. C A R R IE R 618. When one carrier hands over a fissile consignment to another, it is most important for the transfer to be done so as to ensure proper understanding by the receiving carrier of any instructions issued by the consignor A s the Regulations are designed to enable the carrier to contribute to criticality safety by his observation of the transport index requirements as set out in Section V of the Regulations, paras , strict compliance with these requirements, particularly so that the sum of transport indices in any group of packages does not exceed 50, is most important The requirements for storage in transit of both packages and freight containers as set out in Section V of the Regulations, paras , stipulate a separation distance of 6 m between groups of packages, each with a total transport index of 50, unless such groups are in freight containers. E M E R G E N C Y T E A M S 621. When an emergency team is called to an accident, it is not necessary to know

136 SEC TIO N VI 123 SEC TIO N VT - FISSILE MATERIALS ( ) whether fissile materials are involved (although it would be desirable), provided that the requirements for storage in transit are applied in dealing with the packages If there is reason to believe that fissile packages are involved and the labels have been destroyed, then any group of packages should be restricted to five with a 6-m separation between groups.

137

138 SECTION VII SEC TIO N V II - T E S T AND IN SPECTIO N PROCEDURES ( ) T E ST S FOR PACKAGING ( ) T a rg e t for the drop tests (7 0 8 ) 701. One example of a target meeting the regulatory requirements is a steel plate on the upper surface of a block of concrete of mass at least ten times that of any specimen to be dropped onto it. The block should be set on firm soil and the steel plate on its upper surface should be at least cm thick and wet floated onto the concrete so as to be in intimate contact with it. The target should have plane dimensions at least 500 m m larger on all sides than any sample package that is to be dropped onto it and it should be as close to cubic in form as practicable. T ests for dem onstrating a b ility to w ithstand norm al con ditions o f transport ( ) W A T E R S P R A Y T E S T 702. One method of performing the water spray test which is considered to satisfy the conditions in Section VII of the Regulations, para. 711, is described below. (a) The specimen shall stand on a flat horizontal surface, either on its base or turned upside down, whichever is likely to cause most damage to the package. It shall be subjected to a water spray for a period of 15 min from each of four directions, as indicated in (c) below. Changes in spray direction shall be made as rapidly as possible. 125

139 126 SEC TIO N v n SEC TIO N vn - T E S T AND INSPECTION PROCEDURES ( ) T E ST S FOR PACKAGING ( ) Tests for dem onstrating a b ility to w ithstand norm al conditions o f transport ( ) (b) (i) The spray cone apex angle shall be approximately 60, measured at the nozzle. (ii) The centre-line of the spray cone shall be at an angle of 45 to the horizontal. The distance from the nozzle to the nearest point on the specimen shall be 3m. (iii) The water consumption shall be equivalent to a rainfall rate of 5 cm /h, averaged over the area of the spray cone at the point of impingement on the specimen and normal to the centre-line of the spray cone. (iv) Water shall drain away as quickly as delivered. (c) The spray shall be directed downward at 45 onto the specimen with its axis in the vertical plane as follows: (i) for rectangular specimens, the vertical spray plane shall contain the diagonal joining the sprayed corner with the opposite corner; (ii) for cylindrical specimens standing on one plane face, the spray shall be applied from each of four directions at interval of 90. Further information on this method of carrying out the water spray test is given in R e f.[l]. F R E E D R O P T E S T 703. For packagings up to 25 kg in weight, no apparatus other than a measure to deter-

140 SEC TIO N v n 127 SEC TIO N V II - T E S T AND INSPECTIO N PROCEDURES ( ) T E ST S FOR PACKAGING ( ) T ests for dem onstrating a b ility to w ithstand norm al conditions o f transport ( ) mine the height of the drop is required. The packaging m ay be easily held in the hands at the required height and then dropped onto a concrete surface. If a particular drop attitude is required, the packaging m ay be suspended from a thin cord held in one hand and the cord m ay then be cut. For heavier packagings up to about 100 kg, the packaging should be suspended from a single cord tied to some suitable object (such as the jib of a stacker truck) with the lashing around the packaging adjusted to give the required attitude. Release can be accomplished by cutting the cord with a pair of secateurs or a long armed pruner (see Ref.[l], Fig. 8) and letting the packaging drop onto a concrete surface about 15 cm thick. For very heavy packagings, a release hook must be used and the test could be conducted in a manner similar to that described for the 9-m drop test, including target, except that the height of the drop is reduced in accordance with Section VII of the Regulations, Table X X V II. P E N E T R A T I O N T E S T 704. Many tests have been done with relatively simple apparatus [1], The penetration test rig is built from one of the common laboratory angle materials in the form of a frame, a length of guide tube and a 6 -kg bar, 3. 2 cm in diameter with one hem i spherical end. A clearance hole for the release pin is drilled across the longitudinal axis of the bar and a steel pin and a length

141 128 SEC TIO N V II SEC TIO N VII - T E S T AND INSPECTIO N PROCEDURES ( ) T E ST S FOR PACKAGING ( ) Tests for dem onstrating a b ility to w ithstand norm al conditions o f transport ( ) of flexible cable are used for releasing the bar The packaging is placed on the ground under the test rig in such a position that it will suffer m axim um damage. The position of the guide tube in the rig is adjusted so that the hemispherical end of the bar is 1 m above the packaging. The release pin, inserted into the hole in the bar and resting on top of the tube, retains the bar at the correct height. To release the pin from the bar, pull the cable end so that the release pin is clear of the bar. The bar is now free to fall onto the packaging. N O N - M A N D A T O R Y TESTS 706. The packaging and package design requirements in Section II of the Regulations essentially comprise design principles and test requirements. While this section of the advisory document includes, in the text, information relating to mandatory tests, it should be appreciated that, to meet some design principles, various additional tests m ay have to be performed. This is especially true for vibration (Section II of the Regulations, para. 215), and details of tests used in M em ber States are given in an annex to this section. M IS C E L L A N E O U S 707. Several miscellaneous tests, not specifically called for in the IA EA Regulations, are described in R e f.[1]. These

142 SECTION v n 129 SECTIO N V II - T E S T AND INSPECTIO N PROCEDURES ( ) T E S T S FOR PACKAGING ( ) tests are methods of demonstrating com pliance with specific design principles and illustrate simple ways of proving the integrity of components such as drum handles and sealing tape. T ests for dem onstrating a b ility to w ithstand a c c id e n t con ditions o f transport ( ) M E C H A N I C A L T E S T S : E X A M P L E S O F T H O S E P E R F O R M E D IN T H E U N IT E D K I N G D O M Nine-metre drop test 708. The method of drop testing described in R e f.[1] is divided into two sections su m marized below. The first describes a method of testing packagings of up to 3 tons (3054 kg) in weight; to test comparatively light packagings, it would be uneconomical to use the full crane facilities and, in fact, it m ay not be possible to.release light packagings satisfactorily with a release hook designed for 3 tons. The second section describes a method of drop testing packagings up to 25 kg which can be manhandled from an electric platform truck (e.g. Simons truck). Packagings_up to_3_tons_ _305jl kg] 709. The target consists of a block of concrete 8 ft X 9 ft X 8 ft, 30 tons in weight, having a surface area of 72 ft2. The upper surface of the concrete is covered with a 1-in. thick steel plate approximately 8 ft X 9 ft, secured to the concrete by 14 3/4-in. ragbolts and clamping

143 130 SECTIO N vn SEC TIO N V II - T E S T AND INSPECTION PROCEDURES ( ) T E S T S FOR PACKAGING ( ) T ests for dem onstrating a b ility to withstand a c c id e n t conditions o f transport ( ) brackets. Anchor points are positioned 17 ft from the centre of the target to secure the crane jib with ropes. Two concrete platforms are placed at right angles to the target, approximately 30 ft from its centre, with steel mounting plates on which to attach high-speed cinecameras. Steel frames are placed on two sides of the target facing the cinecamera positions and are used to secure background boards. The boards are white with black lines marked off at 6 -in. intervals, to determine such features as deformation when the results of the drop test are being analysed with the aid of the cine film The crane is a 20-ton, truck mounted, diesel electric, fully mobile crane with unlimited full-circle slewing in either direction. To carry out the drop test, an 80-ft jib is fitted, with a manually operated quickrelease hook, rated at a safe working load of 3 tons, suspended from the crane hook The crane is positioned so that the jib is in line with the centre of the target. The crane outriggers are fully extended and the jacks on the ends of the outriggers screwed down so that they are in contact with the ground. The crane jib is secured by rope to the two anchor points and the quickrelease hook is attached to the crane The packaging under test is slung from the quick-release hook so that it will sustain m axim um damage on impact with the target. The safety peg on the quickrelease hook is removed. It is an advantage to attach a steadying cable to the packaging to minimize any movement before the test.

144 SEC TIO N V II 131 SEC TIO N vn - T E S T AND INSPECTIO N PROCEDURES ( ) T E ST S FOR PACKAGING ( ) T ests for dem onstrating a b ility to w ithstand a c c id e n t conditions o f transport ( ) 713. A length of string, 9 m long, with a small weight attached to one end, is secured to the lowest corner of the packaging (i.e. the point which will impact when released) with a slip knot. The packaging is raised until the small weight is just in contact with the target, indicating that the packaging is at the correct height for the test. A length of string is attached to the' weight to enable the string and weight to be pulled free from the packaging without the operator having to stand underneath the suspended load A method of synchronization (e.g. a 'count-down') is agreed on by the camera operator and the person responsible for actuating the release hook. On a signal from the camera operator, the hook cable is pulled, thus releasing the packaging. Pack^ings_up_to_ about _25_kg 715. The following method of testing is economical and can also be arranged at relatively short notice, these points being of great importance where results are urgently required and the money available for the test is limited. A n electric platform truck as used for servicing overhead lamp standards, etc., is suitable. This truck has a hydraulically operated, double - cantilever arm which rotates on a turntable. The cantilever arm supports a platform with a handrail at waist height and has an independent control console which enables the operator to move the platform in any direction or height within the scope of the

145 132 SEC TIO N vn SEC TIO N V II - TES T AND IN SPECTIO N PROCEDURES ( ) T E ST S FOR PACKAGING ( ) T ests for dem onstrating a b ility to w ithstand a c c id e n t conditions of transport ( ) vehicle. The truck is fitted with outriggers and jacking screws that are extended to provide stability when the cantilever and platform are being operated. (Figure 7 of Ref.[l] shows a drop test being carried out from the truck. ) 716. A suitable concrete surface is chosen for the drop test on a secluded site. The platform truck is set up with its outriggers extended and jacking screws locked in position. The operator climbs into the platform with the packaging for testing and a length of string 9 m long, weighted at one end The operator raises the platform by means of the independent control console, lowers the weighted string over the edge of the platform and continues to raise the platform until the weighted end of the string just touches the ground. Having carefully observed the 9 m position, he allows the string to fall to the ground, holds the packaging over the edge of the platform at the correct height and allows it to fall. Light packagings may be suspended by a cord, and the cord severed by secateurs or scissors as an alternative if so desired. Punch test 718. The mechanical test comprises two drops, one of 9 m onto the target, such as in para. 701 above, the other of 1 m, as outlined below, onto a "punch" fastened upright on such a target. The order in which a package is subject to these two

146 SEC TIO N v n 133 SEC TIO N V II - T E S T AND INSPECTIO N PROCEDURES ( ) T E S T S FOR PACKAGING ( ) Tests for dem onstrating a b ility to w ithstand accid e n t conditions o f transport ( ) drops should be such that, on completion of the mechanical test, the package will be most liable to m axim um damage in the thermal test which,follows The punch is a solid mild-steel cylindrical bar 6 in. (1 5.3 cm) in diameter and 8 in. (20. 3 cm) long with one of the flat ends mounted on a rectangular base and secured to the steel surface of the drop test target. The radius of curvature of the edge of the upper face of the punch should be 6 m m. The packaging should be so positioned, 1 m above the punch, that on impact it suffers the m axim um damage. W hen the release hook is operated, the package falls onto the punch. Use of scale model(s) for demonstrating compliance with the requirements of the 9-metre drop test 720. Experience has demonstrated that scale model testing is a useful method for demonstrating compliance with the requirements of the 9-m drop component of the mechanical test. The conditions of similitude are simple to create, provided the same materials are used for the model as for the full sized object. In an economical manner, it is thus possible to study the position of fall that produces the m axim um damage, the deformation of the package and the deceleration of packaging parts. In addition, many design features, for instance shock-absorbers or screws, can be optimized by model testing. The choice of the reduction scale depends on the accuracy which is necessary

147 134 SEC TIO N v n SECTIO N V II - T E S T AND IN SPECTIO N PROCEDURES ( ) T E S T S FOR PACKAGING ( ) Tests for dem onstrating a b ility to withstand a ccid e n t con ditions o f transport ( ) to ensure sufficient perfect model presentation; for example, the reduction of scale might be greater for a study of packaging deformation as a whole than for testing certain parts of the packaging. Therefore, when an application for approval of packaging design is based on scale model testing, it should include a demonstration of the validity of the scale used. In particular such demonstration should include [4] : (a) indication of model scale; (b) demonstration that the model constructed reproduces sufficiently accurately the details of the packaging or packaging parts to be tested; (c) list of parts or features not reproduced in the model; (d) justification for deletion of parts or features in the model; (e) justification of the similitude criteria used Where modelling might be used to evaluate problems of brittle fracture, attention is drawn to the fact that brittle fracture occurs more readily in thicker parts. In the case of cast iron or cast steel packagings, account should be taken of the fact that the physical characteristics of the material m ay be affected by the overall size and section thickness of the casting [4]. T H E R M A L T E S T 722. The following test procedures are considered to be adequate to satisfy the general test conditions under Section VII

148 SEC TIO N vn 135 SEC TIO N V II - T E S T AND IN SPECTIO N PROCEDURES ( ) T E ST S FOR PACKAGING ( ) T ests for dem onstrating a b ility to w ithstand a ccid e n t conditions o f transport ( ) of the Regulations, para In all the examples the specimen should be at a tem perature corresponding to equilibrium with m axim um expected heat output and in air at 38 C ambient temperature. Open fire test 723. The specimen, at the equilibrium tem perature, shall be exposed to an open fire meeting the conditions in para. 724 below. The specimen shall be supported so that its bottom is 1 m above the initial level of the fuel. The structure supporting the specimen shall be such that it does not prevent direct exposure of any significant area of the specimen to the heat generated. The specim en shall be positioned so that m axim um damage will result The open fire shall consist of the burning in open air of a distillate of petroleum with a distillation end point of 330 C m axim u m and a flash point of 46 C m inimum and with a gross heating value of from kcal/kg to kcal/kg. The fire shall be such that all sides of the specimen are exposed to a luminous flame not less than 0.7 m and not more than 3 m thick. The tank holding the fuel shall be of such a depth as to contain the fuel with only nominal freeboard The specimen shall be exposed to the fire under the above conditions for 30 min. It shall not be cooled artificially until another three hours have elapsed or until it has been demonstrated that all internal

149 136 SEC TIO N v n SEC TIO N VII T E S T AND IN SPECTIO N PROCEDURES ( ) T E ST S FOR PACKAGING ( ) Tests for dem onstrating a b ility to w ithstand a c c id e n t conditions o f transport ( ) temperatures have begun to fall, whichever is the earlier, and any combustion of the packaging itself shall be allowed to proceed for three hours after the cessation of external heating unless it terminates earlier naturally. Furnace test Method I 726. The specimen, at the equilibrium temperature, shall be exposed to a furnace test meeting the conditions in para. 727 below. The specimen shall be placed in the centre of the furnace chamber, whose interior surface area shall be at least ten times the external surface area of the specimen The furnace shall be heated up so that its temperature is never below that of the standard fire curve (see ISO Standard No. R 834, 1968) which has as its initial starting temperature the value 30 C. After 35 min, the heating shall cease The specimen shall not be cooled artificially until another three hours have elapsed or until it has been demonstrated that all internal temperatures have begun to fall, whichever is the earlier, and any combustion of materials of the specimen shall be allowed to proceed for three hours after the cessation of external heating to the specimen unless it terminates earlier naturally. Furnace test Method II 729. Introduction: This method enables conventional furnaces designed for the heat

150 SECTIO N V II 137 SEC TIO N V II - T E S T AND IN SPECTIO N PROCEDURES ( ) T E S T S FOR PACKAGING ( ) T ests for dem onstrating a b ility to w ithstand a c c id e n t con ditions o f transport ( ) treatment of steels to be used for the thermal test. Provision is required of apparatus for the measurement and recording of the furnace wall temperature and of support beams on the furnace base to facilitate loading and unloading by fork-lift truck. Because of the requirements for furnace wall emissivity and specimen surface absorptivity, a restriction on the packaging furnace size ratio is not necessary. (Such a restriction could not result in an increase of heat flux into the package of more than 1/9, i.e. that for an increase of surface emissivity from 0. 9 for a normal furnace wall surface to a value of 1.0 for the perfect black body.) A detailed description of operation according to this method is given in Ref.[l], 730. Method: Ensure that the furnace walls are thoroughly "soaked" with heat and at a temperature such that the recorded value will not fall below 800 C when the specimen is inserted. Ensure that the furnace wall surface emissivity is at least 0.9. (Note. For a furnace capacity of approximately 1-2 cubic metres, a "soak" time of approximately 2h and a wall temperature of approximately 83 0 C should be adequate.) 731. Insert the specimen at the equilibrium temperature and maintain the furnace wall temperature at 800 C (+ 10 C). After 30 min, withdraw the specimen Allow the specimen to cool naturally until another three hours have elapsed or until it has been demonstrated that all

151 138 SEC TIO N v n SEC TIO N VII T E S T AND INSPECTIO N PROCEDURES ( ) T E S T S FOR PACKAGING ( ) T ests for dem onstrating a b ility to w ithstand a c c id e n t con ditions o f transport ( ) T h e rm a l test (7 2 0 ) internal temperatures have begun to fall, whichever is the earlier. Allow any combustion of materials of the specimen to proceed, for three hours after the cessation of external heating to the specimen unless it terminates earlier naturally. Compliance with the requirements of the thermal test 733. In thermal testing with scaled models, it is difficult to create reasonable conditions of similitude, even when the conditions of similitude for each of the thermal processes concerned will be regarded in different experimental arrangements. Thus the assessment of the test criteria here, especially for large packagings, for example irradiated fuel flasks/casks, is based frequently on analytical models and finite difference techniques combined with com puter application. In most cases, this theoretical work must be assisted by some experiments on materials of the packaging components or on parts of the packaging to assist in a reasonable choice of physical parameters. The designer is referred to the literature on this subject as listed in the Bibliography at the back of this publi cation. T ests for in te g rity o f co n ta in m en t and sh ield ing (7 2 5 ) Radiation leakage test [3] 734. One method of proving the integrity of shielding, in accordance with Section VII of the Regulations, para. 725, for Type A,

152 SEC TIO N vn 139 SEC TIO N V II - T E S T AND INSPECTIO N PROCEDURES ( ) T E S T S FOR PACKAGING ( ) T ests for in teg rity of co n ta in m en t and shield ing (7 2 5 ) Type B(U) and Type B (M ) packages after the tests specified in Section VII is as described below. (a) With a suitable source inside the specimen,the entire surface of the specimen shall be examined with an X-ray film or an appropriate instrument to determine if there has been a loss of shielding. (b) If there is evidence of loss of shielding at any point on the surface of the specimen, it must be determined by actual m easurement and calculation that the radiation level from the specimen will satisfy the regulatory requirements of Section II of the Regulations, para. 225(b) and para. 229 for Type A and Type B packages, respectively. For this requirement, the surface refers to the surface of the specimen prior to the tests Paragraphs 736 and 737 below describe two examples of immersion test procedure. The first utilizes internal air pressure and has a practical sensitivity of about 10 3 Torr-litre/s; the second utilizes a bath of ethylene glycol and a reduced external pressure, and has a practical sensitivity of about 10-5 Torr-litre/s. Several minutes of observation m ay be required when the points of possible leakage are not fully exposed, since escaping gas could be held up for a time before becoming apparent and, conversely, previously entrapped external air could escape and be mistaken for leakage.

153 140 SECTIO N vn SEC TIO N V II - T E S T AND INSPECTIO N PROCEDURES ( ) T E S T S FOR PACKAGING ( ) T ests for in teg rity o f co n ta in m e n t and shielding (7 2 5 ) Containment test for vessels forming the whole or part of the containment system and referred to in the text below as "the component") Dimensipns_gre_at_er!han_ 8 in^ (20 m)_dj_amj_ X 3_in._(58_cm} 736. The test described in Ref.[l] can be carried out satisfactorily with relatively elementary equipment. A pressure supply is required, which can come from either a compressed air line or a gas bottle, nitrogen being a suitable gas. If a compressed air line is used, a pressure in excess of 15 lb/in2 should be available, and, if a gas bottle is used, a pressure regulator must be fitted. A flexible hose, a pressure gauge, a valve for isolating the pressure supply, a pressure relief device and a union adaptor are required to connect the pressure supply to the component. The final item is a tank or drum of sufficient capacity to accommodate the component when it is submerged in water. Punen_sions_less _than_ 8. in^ _[_20 cm)_diam^ X 23_in._(58_cm^ The apparatus in the test described in Ref.[l] consists of a vacuum pump and motor mounted on the lower platform of a laboratory trolley. The vacuum pump is connected to a circular mounting plate on the top platform of the trolley by a flexible pipe and vacuum valve, the vacuum valve being used to isolate the pump from the test chamber. The test chamber consists of a

154 SEC TIO N vn 141 SECTIO N V II - T E S T AND INSPECTIO N PROCEDURES ( ) T E S T S FOR PACKAGING ( ) T e sts for in teg rity o f co n ta in m en t and sh ield ing (7 2 5 ) length of standard Q V F 5 glass tube which is clamped to the circular mounting plate by a backing flange and joint insert. A top cover plate fitted with a vacuum gauge and relief valve is placed on the top of the Q V F glass tube, a gasket being sandwiched between the top cover plate and the glass tube to form the seal. The flexible pipe from the vacuum pump is attached to a rigid pipe set vertically in the mounting plate, the length from the face of the mounting plate to the end of the rigid pipe being approximately 2 in. shorter than the overall length of the glass tube. A quantity of glycol is placed inside the glass tube and is the liquid in which the component is tested. By observing any bubbles of air in the glycol, the presence of a leak can be detected. Two different sizes of test chamber can be assembled by changing the Q V F glass tubing, the mounting and the top cover plate. One size is 6 in (15 cm) in diam. X 12in. (30cm) long and the other is 9 in. (22. 5 cm) in diam. X24 in. (60 cm) long. W hen using the 9-in. Q V F tube, an extension can be added to the rigid pipe in the mounting plate to make full use of the overall length of Q V F tube. Containment test internal hydraulic pressure [4] 738. The following test has been used as an alternative method to that described in para. 736 above, where a tank of dimensions adequate to accommodate the containment 5 Q uickfit Visible Flow.

155 142 SEC TIO N vn SEC TIO N v n - T E S T AND INSPECTIO N PROCEDURES ( ) T E ST S FOR PACKAGING ( ) T ests for in teg rity o f c o n ta in m en t and shield ing (7 2 5 ) system so that any leakage could be observed was not available. This test is considered to have a practical sensitivity equivalent to 1 0 '1 Torr-litre/s of gas leakage for containers with closures of such a design that leakage can be readily observed. Care should be taken to leave no air in the container and to maintain a constant temperature of the system The containment system to be tested should have a pressure adaptor fitted in either the lid or the body. A compressedair-driven hydraulic pump (e.g. an air hydro-pump), a pressure gauge, a control valve and a flexible hose m ay be used The containment system should be completely filled with water and assembled with its lid and gasket and with the appropriate tightening torque applied to the lid-securing bolts. The pressure adaptor is connected to the pressure gauge and the control valve and flexible hose to the air hydro-pump, care being taken to bleed any air from the system A n internal hydraulic pressure of kg/cm 2 gauge (for practical purposes the equivalent of a reduction of atmospheres externally) is applied, the control valve is closed and the pressure is held for 30 min. Drop in pressure is not necessarily an indication of leakage, but m ay be due to changes in temperature or the effects of any air left in the system. These factors must be taken into account, and reapplication of pressure m ay be required. However, if no trace of water leakage can be seen near the

156 SEC TIO N vn 143 SECTIO N v n - T E S T AND INSPECTIO N PROCEDURES ( ) T E S T S FOR PACKAGING ( ) T ests for in teg rity o f co n ta in m en t and shield ing (7 2 5 ) gasket joint and if there is no drop in pressure shown on the gauge, the vessel m ay be considered leaktight within the limits given above. Contents leakage test A n Americal National Standards Institution (ANSI) Trial Standard for leaktightness of containers for shipment of radioactive materials is in course of preparation. Radioactive material containment, in accordance with the Regulations, involves so many variables that a single standard test procedure is not feasible. The trial standard: (a) relates the regulatory requirements for radioactive material containment to practical detectable mass flow leakage rates; (b) defines leaktight in terms of a m ass flow rate; (c) makes some simplifying, conservative assumptions so that many of the variables m ay be consolidated; and (d) describes specific leakage tests. T E S T S FOR SPECIAL FORM RADIOACTIVE M ATERIAL ( ) 743. Radioactive materials m ay be transported in Type A packages in the form of sealed and unsealed sources. The term "sealed source" means a source of ionizing radiation emitted from radioactive material contained in a system which prevents,under expected conditions of use, the escape of dangerous amounts of activity W hen the sealed source complies with the regulatory requirements of Section VII

157 144 SEC TIO N v n SECTIO N vn - T E S T AND INSPECTIO N PROCEDURES ( ) T E ST S FOR SPECIAL FORM RADIOACTIVE MATERIAL ( ) of the Regulations, paras , it is termed "special form radioactive material". The m axim um permissible activities A x apply to special form radioactive material in Type A packaging. The term "unsealed source" means a source of ionizing radiation contained in any state of aggregation, but usually in a receptacle which would not permit, under the expected conditions of use, the loss from the receptacle of amounts of activity and their dispersal in the environment When the characteristics of a radioactive material are such as to reduce the probability of intake after a transport accident to a negligible level, then the theoretical acceptable Type A package content, A 2, can be raised to a level, A 1, which is based on the external radiation risk of the unshielded content (Section IV of the Regulations, paras ). To take advantage of this higher content limit in a Type A package, special form radioactive material has been defined in para. 135 of Section I of the Regulations. By virtue of this definition, the special form radioactive material will have properties such that, even after a transport accident, dispersal of the material by fracture, crumbling, melting, sublimation or ignition is improbable. To check the properties of special form radioactive material, a series of tests (Section VII of the Regulations, paras ) have to be performed The following factors require consideration during the design of a sealed source:

158 SEC TIO N vn 145 SEC TIO N vn - T E S T AND IN SPECTIO N PROCEDURES ( ) T E ST S FOR SPECIAL FORM RADIOACTIVE M ATERIAL ( ) (a) the possibility of galvanic reaction between dissimilar materials, particularly metals for encapsulation; and (b) the location of welds, which should be such as to minimize both stress concentrations and the possibility of failure under impact, percussion and bending It should be ascertained that the capsule, even after use in the intended manner, will still meet the regulatory specification for special form radioactive material (Section I of the Regulations, para. 135). Consideration should be given to external contamination from the material and to longer-term effects, such as diffusion of the radioactive contents through the capsule walls When a capsule is designed in accordance with IS O /T C 8 5 /S C 4 /W g l (Seer. 53)77 for sealed sources in agreement with the competent authority concerned, the tests in Section VII of the Regulations, paras 732, 733 and735, need not actually be performed if the capsule meets the following ISO class specifications: (1) temperature Class 6, (2) impact Class 4 at least; (3) the ISO ham m er for impact has a m ass 10 times greater than the m ass of the capsule plus content When, by agreement with the competent authority concerned, the performance tests of a capsule design are not performed with radioactive contents, the leakage assessment may be made by a volumetric leakage assessment method. A rate of 10"4 Torr -1/s for solid content and a rate

159 146 SEC TIO N vn SEC TIO N vn - T E S T AND INSPECTIO N PROCEDURES ( ) T E S T S FOR SPECIAL FORM RADIO ACTIVE MATERIAL ( ) of 10 "6 Torr -1 / s for liquid and gaseous content would be considered in most cases to be equivalent to the activity release of 0.05juCi prescribed in Section VII of the Regulations, para Particular attention should'be paid to m axim um damage conditions in the percussion test, Section VII of the Regulations, para For example, it can be necessary for tiny, long and slender capsules (i.e. radium needles) to be tested in a vertical position to meet the m axim um damage condition. Capsule percussion test [1] 751. The apparatus described below produces an impact equivalent to a 1. 4-kg billet falling through 1 m as required by the Regulations, and consists of a steel tube 2. 8 in. (7. 2 cm) bore X 30 in. (76 cm) long, machined at one end so that two protruding lugs are left. The lugs are welded to a square base plate, and the gap between the lugs permits the capsule and lead target sheet to be placed into position. A 4 -lb cylindrical steel test bar, whose outer diameter gives a good sliding fit within the in. tube and which is tapped to take a flat-faced screwed insert 2.5 cm in. diam. with a 3-mm radius on its lower edge, is used as the test bar. A flat lead plate is fitted between the lugs on the tube and is the test anvil to support the capsule being tested (see Fig. 10 of R e f.[1]).

160 SEC TIO N vn 147 SEC TIO N v n - T E S T AND INSPECTIO N PROCEDURES ( ) T E S T S FOR SPECIAL FORM RA D IO ACTIVE MATERIAL ( ) 752. The rig is assembled with the square plate firmly supported, and the capsule to be tested is placed on the lead plate at the base of the tube. The test bar is placed in the open end of the tube and held at the correct height by the cord. The cord is then released, allowing the test bar to fall and strike the capsule. R E F E R E N C E S [1 ] D A VIES, A. J., D escription o f Various T est M ethods Used at AERE H arw ell to C om ply w ith th e IAEA Regulations for R a d io a ctiv e Transport C o n tain ers, UKAEA Rep. AERE R , HMSO ( ). [2 ] WILSON, E. J., PARTRIDGE, A.H., Brittle Fracture Problem s in R elatio n to T h ic k W alled P a ck a g in g, Paper presented at 2nd In t.s y m p. o n P a ck a g in g and T ransp ortation o f R ad io activ e M a te ria ls, G atlin bu rg, O cto b er , CONF [3 ] INTERNATIONAL STANDARDS ORGAN IZATION, T h e C ontents L e a k a g e T est and R ad iation L eak ag e T e s t, ISO Document No.ISO / TC 85 SC 4 (Seer. 81) 95E (1968). [4 ] DIXON, F. E., An Indexed List with Commentary of Experim en ta l Work C o nnected with Transport C ontainers for R ad io activ e M a te ria l Perform ed at AERE, H arw ell, , UKAEA Rep. A ERE-R ANNEX E X A M P L E S O F V IB R A T IO N T E S T S 1. V IB R A T IO N T E S T U S E D IN T H E U N IT E D K I N G D O M Introduction. The aim of this test is to determine whether or not a package will withstand the vibration it m ay experience during surface transport.

161 148 ANNEX TO SEC TIO N V II Resonance searching and resonance endurance testing have been rejected for the reasons given below. (1) They do not necessarily reproduce the effects of the real environment. (2) They are complex and difficult to perform in practice, particularly for closed packages. (3) It is not intended to produce diagnostic data for design purposes. Instead the principle has been followed of adopting a test which simulates the damage occurring in the real environment. Manipulation of the basic environmental parameters has therefore been kept to a minimum, and, in particular, no attempt has been made to devise an acceleration test. The test specification is intended to provide a means of differentiating between acceptable and unacceptable designs whilst retaining simplicity and making the minimum demand on the skill of the test engineer. It is limited by the fact that the complex vibrational conditions occurring in practice cannot be fully simulated in a single test. For example, there are six degrees of freedom for a rigid body, but this test specifies motion in only one plane. Whenever there is good reason for not testing the whole packaging to this specification, consideration should be given to the separate testing of components or of subassemblies. It should be borne in mind that the method of mounting the component or subassembly in or on the package might cause magnification of the vibration experienced by the complete package in service. This test is not mandatory (see para. 219 of this publication). It is instead intended as a guide for designers which attempts to cover the entire range of transport environments, with the

162 ANNEX TO SECTIO N V II 149 possible exception of large piston-engined aircraft. Requirements for machine table and adaptors. The table of the machine shall be horizontal and shall have a vertical sinusoidal acceleration nominally free from self-induced harmonics or other distortion when loaded with a resonance-free mass equivalent to that of the sample under test. (The reference to 'resonance-free' relates to the frequency range of the test, i.e. between 5 and 150 H z. ) The table and adaptors used for securing the sample to the machine must be sufficiently rigid to avoid modifying the motion of the machine. Samples not secured to machine table. For samples not secured to the machine table, the weight of the table must be at least ten times that of the sample. Random motion testing. In random motion testing, the vibrator system shall be driven from a standard Gaussian noise generator and shall be such that peaks of up to three times the rms value are transmitted to the vibrator table. Distributions other than Gaussian are the exception in nature, and only Gaussian driving sources are used for random vibration testing. Peaks greater than three times the rm s value occur for less than 1% of the testing time, and, if they are to be accommodated, the capacity of the driving system must be derated. Limitation to three times the rm s peaks is customary in vibration testing. Condition of samples (a) Packages for testing should be manufactured according to normal production standards as far as possible.

163 150 ANNEX TO SEC TIO N V II (b) The package contents should re present the service loading expected to produce the most damage under vibration, e.g. part loaded, loose contents, etc. (c) When there is a good reason for not testing the whole package to this specification, consideration should be given to the separate testing of components or of subassemblies. Securing of samples (a) For packages normally secured to the conveyance, the sample shall be secured to the vibrator table in the manner used in practice. Failure of the anchorage to maintain the package in contact with the vibrator table shall be regarded as rendering the test void. (b) For packages not'normally secured to the conveyance, the sample shall be confined to the table top by means of side walls attached to the table. Orientation. If it is practicable for the package to be transported in more than one attitude, the sample shall be given the full vibration test in each attitude. (The vibration test need be performed only along one axis if there is three-dimensional symmetry or along each of three dissimilar axes if there is two-dimensional sym m etry.) The vibrator table shall be driven to the acceleration spectral density envelope shown in Fig.l as determined by an analyser with a bandwidth not greater than one third of an octave. The rm s level of the test specified in F ig.l was obtained from a report which describes severe tests, in which a 5-ton truck travelled over rough ground. The frequency range was specified to correspond with that of the sinusoidal test.

164 ANNEX TO SECTIO N VII 151 SPECTRAL DENSITY (g V H z ) FREQUENCY (H z ) F I G.l. V ib ratio n test: sp ectra l den sity / freq u en cy. One third octave band analysis is justifiable on the grounds that the basic data are not precise enough to warrant finer analysis (which, incidentally, might not be readily available in many testing facilities). There would also be the problem that a fine analysis might reveal a spectral shape containing precipitous peaks and notches whose removal would demand sophisticated and expensive driving equipment (equalizers), as well as more powerful vibration systems. Such sophistication is not justified when the specification represents a rounding-off of the original environment.

165 152 ANNEX TO SEC TIO N V II The duration of the test shall be between 6. 5 and 65 hours, depending on the percentage of rough road in the total environment (Fig. 2). Comment. The duration of the random test should be such that it causes the same degree of fatigue damage as the sinusoidal test. This must be derived from the sinusoidal vibration specification by considering cumulative damage theory. Cumulative damage. Reversal of stress in a component will, if repeated many times, cause a type of damage known as fatigue damage. The number of reversals required to cause fatiguing of a component are related to the level of the stress, and this relationship is expressed graphically by an S-N curve. The accepted theory relating to stress reversal (Miner's Hypothesis) claims that stress reversals at different levels m ay accumulate towards the total required for failure, each set of reversals contributing in proportion to its stress as well as its number. S-N curve. The nature of an S-N curve depends on the material under consideration. It is necessary to know the mathematical equation of the curve if an equivalent random test is to be calculated. A s an example, a type of curve will be considered in this note based on 'D S T T ',a n abbreviation for the hypothesis that a doubling of stress demands one tenth of the previous testing time for equivalent fatigue damage. If a stress reversal corresponding to an acceleration reversal + Yg (g being the acceleration produced by gravity) causes failure after N cycles, then an acceleration

166 ANNEX TO SECTIO N VII 153 reversal of ± 2 Y g will cause failure after cycles. If the acceleration reversal is ± pyg, the number of cycles needed to cause N failure is therefore p5.32. Similarly, if the damage potential due to an acceleration reversal of + Yg is D, then the damage potential due to an acceleration reversal of + pyg is p3-32 D. Nature of random test. It is assumed that the random test is the application of a random force of Gaussian distribution, of limited bandwidth, of known spectral density, and of peak level not greater than four times its standard deviation. It can be shown that the number of peaks per second exceeding a value py for a random function of standard deviation a is: n= exp(-p2y 2 )/2cT2 (1) where al is the standard deviation of o ^ - (P Y ) = / / 87T3fV (2 *f)d f (2) 0 and (f>(27rf) is the power spectral density of the random function. Each peak will have a damage potential, related to its acceleration amplitude py, of p 3-32 D, and the accumulation of damage per second is the sum of the products of the frequency of occurrence of each peak level and its damage potential. As the value n in Eq. (1) is not the frequency of occurrence of a peak level but the frequency of occurrence of peaks in excess

167 ANNEX TO SECTIO N VII of a level, the product n p 3-32D does not represent the damage rate due to peak level + py. At any level (p + 6 p )Y the damage already included at the level py must be. subtracted... at level (p + 6 p )Y, the true damage potential = (p + 6 p) d. p3.32 p In the limit, as 6p tends to dp, this rectified damage potential becomes d (p 3'32D) = p 2>32D -dp and the rate of accumulation of damage due to peaks occurring between py and (p + dp)y is n p 2-32D dp The total rate of accumulation of damage is therefore 4 o o (3) If the sinusoidal acceleration specification, whose random equivalent is required, demands N reversals, each of ± Yg, then the duration T of the equivalent test N D seconds o 4 o N seconds

168 ANNEX TO SEC TIO N V II 155 Figure 2 shows the relationship between percentage rough road element of the environment and the test duration. W here circumstances prevent a random test, the following parameters for a sinusoidal test can be considered as an equivalent alternative. Sinusoidal test. While the use of random vibration gives the most likely type of motion to be met in transport, the equipment required to create this motion for a test is far more sophisticated than that required for DURATION OF TEST ( h ) PERCENTAGE OF ROUGH ROAD IN TOTAL ENVIR ONMENT F IG.2. V ibration test duration in term s o f p ercen tag e o f rough road.

169 156 ANNEX TO SEC TIO N VII sinusoidal vibration testing. The parameters given for a sinusoidal test are, therefore, intended to produce an equivalent test. (a) The peak acceleration of the vibrator table shall be controlled to ± 2g, except that the applied thrust must not exceed five times the weight of the package. The acceleration should be measured after the removal of unwanted harmonics from the wave form. (b) The frequency of vibration shall fluctuate between 5 and 150 Hz at a rate of 1 octave/min. (c) The duration of the test shall be between 1 million and 10 million cycles, depending on the percentage of rough road in the total environment. The tolerances on the controlled parameters shall be within the following limits: acceleration + 10%; frequency ± 5%; spectral density + 100% - 0%. Spectral density is analogous to the distribution of vibratory power through the frequency range. It is the square of the acceleration measured within a bandwidth, divided by that bandwidth, and is expressed as g2 per Hz. Setting up random acceleration levels is always somewhat imprecise, and the tolerance on levels in this sort of test is always greater than that set on a sinusoidal test. Detection of cracks. Before and after the test, the container will be examined for surface cracks by a method appropriate to its design, e.g. fluorescene dye under ultra-violet light.

170 Cycling test ANNEX TO SEC TIO N VII VIBRATION TESTS USED IN THE UNITED STATES OF AMERICA The cycling test is the simplest attempt to simulate the vibration environments of actual transportation. It requires a vibrational source which allows adjustment of amplitude as well as frequency, whereas the source required for the bounce test is of fixed amplitude. The item to be tested is attached to the table of the vibrational source, and the test is run by sweeping a band of frequencies according to a specified amplitude versus frequency schedule. For simulation of transportation vibration, the schedule used is based directly on measured or expected vibrational spectra. Three types of sweep are commonly employed. The logarithmic sweep is generally preferred in the specifications. The total time per sweep is usually specified. If T is the specified sweep time and the frequency is to be swept in the range ^ through f2, the frequency f(t) is continuously adjusted in time such that log f(t) = ^ log f2 + (l - log f i The second means of sweeping the frequency range is a piecewise linear sweep in time. This type of sweep is employed when the available testing apparatus does not allow a continuously variable or programmable sweep rate, but rather provides several or many constant sweep rates. The piecewise linear sweeps are arranged for

171 158 ANNEX TO SECTIO N VII the best approximation of the logarithmic sweep. The least sophisticated technique of providing a frequency sweep consists in testing at a discrete number of frequencyamplitude pairs. Total time of dwell at each pair is chosen so that the net effect best approximates the logarithmic sweep within the constraints imposed by the set of frequencies available on the particular testing machine. Resonance test Resonance tests are commonly specified in conjunction with cycling tests, although they are sometimes required alone. These tests consist of a single frequency sweep to identify the frequencies at which the test item exhibits resonance, followed by dwells at some or all of the resonant frequencies. Specifications generally require a dwell of certain duration at each resonance, the amplitude being taken from a specific amplitude versus frequency schedule. The resonant search generally requires that the package be fitted with one or more accelerometers. Resonance is then indicated by a peaking of the ratio of package acceleration to table acceleration, as the frequency is slowly swept. Example 1 Cargo tied down Amplitude versus frequency schedules are as shown in Figs 3 and 4 for four classes of transport: air, tracked vehicles, trucks plus semi-trailers plus railroad,

172 ANNEX TO SEC TIO N VII 159 PACKAGE W EIGHT LESS TH A N 125 lb lb G REATER TH A N 150 lb 0.1 DOUBLE AMPLITUDE ( in. ) FREQUENCY (H z ) FIG.3. Air transport test schedule (Exam ple 1).

173 160 ANNEX TO SECTIO N VII DOUBLE AMPLITUDE ( in.) FR EQ U ENCY (H z ) FIG.4. Land transport test schedule (Exam ple 1).

174 ANNEX TO SEC TIO N V II 161 UPPER LIMIT FREQUENCY (H z ) PACKAGE W EIGHT ( lb ) F IG. 5. U pper lim it frequency for a ir transport test ( E xam p le 1 ). and two-wheel trailers. Package weight is taken into account in the air transport schedule. The test frequency range is Hz, except for air transport of packages weighing more than 100 lb. In exceptional cases, the upper limit frequency is decreased with increasing weight, as shown in Fig. 5 in Example 2.

175 162 ANNEX TO SECTIO N V II Test time is 15 min per axis per 1000 miles of land transport and 1 h per axis per 1000 miles of air transport. If both modes are included, the land transport test time shall apply only to the frequency range from 2 Hz to the intersection with the air transport schedule and the air transport time applies to the frequency range from that intersection to the upper limit frequency. Resonance search is conducted by a single sweep of the frequency range for each axis at amplitudes taken from the schedules. Resonant dwell is taken at the four most severe resonances along each axis if that m any are clearly defined. Dwell time is 2. 5 min per 1000 miles of land transport or 10 min per 1000 miles of air transport. The cycling test is used for the re mainder of the test time. A logarithmic sweep at the rate of 15 min per sweep is preferred, although a piecewise linear sweep is acceptable. Loose Cargo Resonant search is conducted over the range from 10 to 55 Hz with a m inimum double amplitude of in. by increasing in 1-Hz steps and maintaining at least 10 s at each frequency. This test is run solely to establish that the resonant amplification factors do not exceed 2.0. Example 2 The low-frequency cycling test extends over the range 2-5 Hz. Test level is 1-in. double amplitude and the test time is 15 min per axis. The sweep is to be a

176 ANNEX TO SEC TIO N VII 163 logarithmic sweep at 2 min/octave. H o w ever, a discrete frequency alternate is acceptable: 5 min each at 2, 3 and 5 Hz. The high frequency cycling test follows the schedule of Fig. 6 from 5 to 500 Hz, except that the upper limit frequency is taken as in the aircraft portion of the test in Example I (see Fig. 5). Test time is 15 min per axis. Again a logarithmic sweep DOUBLE AMPLITUDE (in.) F R E Q U E N C Y (H z ) FIG. 6. Test schedule ( Exam ple 2 ).

177 164 ANNEX T O SECTIO N VII is preferred, and, although the sweep rate is not specified, it is required that at least four 5-max Hz-5 sweeps be executed. Two alternatives are allowed in the sweep: seconds n z in in ch es d iscrete frequ en cy sweep seconds Hz double am plii in in ch es The resonance test specifies 15-min dwell at each resonant frequency. Example 3 Procedure I The cycling test is divided into two ranges: Hz and H z. Ten sweeps per axis ( Hz) are taken over the low range and 14 sweeps per axis over the high range ( ). A logarithmic sweep is specified such that each sweep requires 20 min. The amplitude schedules are shown in Fig. 7.

178 ANNEX T O SEC TIO N VD 165 The resonance test consists of 20-min dwell at each resonant frequency, the amplitude being the same as in the cycling test. If no resonances are found, two extra 15-min sweeps are required in each of the cycling ranges. DOUBLE AMPLITUDE (In.) FREQUENCY (H z ) F IG.7. Test schedule (Exam ple 3 ).

179 166 ANNEX T O SEC TIO N VII A discrete frequency alternative is allowed. For the cycling test, this alternative requires 60-min dwells at each of the frequencies given below. longitudinal axis: 10, 17, 28, 46, 76, 128, 212 and 350 Hz transverse axis I: 12, 20, 33, 54, 91, 152, 250 and 417 Hz transverse axis II: 14, 24, 38, 65, 107, 178, 297 and 500 Hz. If no resonances are detected, the resonant dwells are replaced by 15-min dwells (each axis) at 10, 46, 152 and 500 Hz. Procedure II The cycling test over the range Hz requires 16 logarithmic sweeps ( Hz) of 1 5 -min duration, according to the schedule in Fig. 7. The discrete frequency alternative requires 10 min at each of the following frequencies: 10, 11, 12, 14, 15, 16, 17, 18, 20, 22, 24, 26, 28, 30, 32, 35, 38, 41, 44, 47, 51, 55 and 60 Hz.

180 SECTION VIII SECTION VIII - ADMINISTRATIVE REQUIREMENTS ( ) 801. Packaging d esigners, consignors and and other applicants are advised that, before including any of the inform ation derived from this Advisory Document in their applications for approvals for sp ecial form or for package or shipment approvals, and before applying recommended te st procedures, they should a scerta in the extent to which such in form a tion is acceptable to the appropriate com petent authority. APPROVAL OF SPECIAL FORM RADIOACTIVE MATERIAL ( ) 802. The need for competent authority approval of sp ecial form m aterial has been reviewed in the light of the introduction of A j quantities. The revised Regulations r e quire certificatio n of approval by the country of origin of the design unless the activity of the radioactive m aterial involved is 1 0 '3 Aa or le s s, whether encapsulated or not In addition to the item s under Section VIII of the Regulations, para. 802, the application should include the following: (1) description of the use and the operating p aram eters of the sp ecial form radioactive m a teria l, e. g. tem perature and stressin g, if it is not designed for transport purposes only; (2) te sts to be done on the m aterial in addition to the te sts specified in Section VII of the Regulations, p aras , e. g. corrosion and vibration te sts; (3) ju stification for using, during the te sts in Section VII of the Regulations, any 167

181 168 SECTION v m SECTION VIII - ADMINISTRATIVE REQUIREMENTS ( ) APPROVAL OF SPECIAL FORM RADIOACTIVE MATERIAL ( ) m aterial other than the radioactive m aterial to be transported (see Section VII, para.701(a)); (4) analysis of reproducibility of the construction methods and a quality control program m e, i. e. weld and su rface inspection or leakage assessm en t In the design of cap sules, the full range of possible p re ssu res within the capsule should be considered. These p re ssu res may re su lt from the fa cto rs given below. (a) P re ssu re at closing. Heat tra n s m itted during the welding operation to close the capsule m ay resu lt in an internal p ressu re other than atm ospheric. (b) Radiolytic decomposition and radiation decay products m ay resu lt in a gradual p re s sure build-up within the capsule. (c) P re ssu re resulting from tem p erature which the capsule may experience during serv ice a s a resu lt of radiation decay heating (esp ecially if the capsule is efficien t ly insulated) or extern al heat so u rces It w ill be appreciated that com pliance with any or a ll advisory m aterial does not autom atically mean that a ll the regulatory requ irem en ts related to sp ecial form m a te ria l are m et. In this re sp ect, attention is drawn to ISO sealed sources when their a c ceptance as sp ecial form m a terial or volum e tric methods for leakage assessm en t have to be considered When a sp ecial form radioactive m aterial is not designed for transport purposes only, the manner and the expected duration of use should be considered to

182 SECTION v m 169 SECTION VIII - ADMINISTRATIVE REQUIREMENTS ( ) APPROVAL OF SPECIAL FORM RADIOACTIVE MATERIAL ( ) decide whether a lim itation of the period of validity of approval for this sp ecial form m aterial is advisable. APPROVAL o f T Y P E A PACKAGE DESIGNS ( ) g07_ in gen eral, no approval by the com petent authority is n e c e ssa ry for Type A packages, except when they contain fissile m aterial. If the radioactive m aterial has, in addition, any other hazardous ch a ra c te r is tic s (see Section I of the Regulations, para. 105), it might be n ecessa ry for the package to be approved under regulations relevant to them Even when approval for Type A packages is not required, the consignor should be able to dem onstrate to the s a tis faction of the competent authority, if n ecessa ry, that the package used is designed and constructed in accordance with relevant requirem ents in Sections II and VII of the Regulations. W here n ecessa ry, the consignor should consult the competent authority on questions arisin g during design and testing of Type A packages. T Y P E B 809. The applicant should contact the com petent authority during the p relim inary design stage to discuss the im plem entation of the relevant design p rin cip les.

183 170 SECTION VIII SECTION VIII - ADMINISTRATIVE REQUIREMENTS ( ) APPROVAL OF PACKAGE DESIGNS ( ) 810. In addition to the item s under Section VIII of the Regulations, para. 805, the application should include the item s listed below. R eports on te sts done in addition to the te sts specified in Section VII, i.e. te sts on corrosion, b rittle fractu re, v ibration, etc. ; proposed quality assurance program m es by which the reproducibility of the construction methods used is justified [2 ]; schedules for m inor maintenance of the package, when n e cessary, before each shipment, and for m ajor maintenance at longer intervals (specifying the frequency with which parts of the packaging, i. e. gaskets, valves, bolts, nuts, e t c., have to be inspected and/or renewed). APPROVAL OF TRANSPORT BY SPECIAL ARRANGEMENT ( ) BASIC PRIN CIPLES 811. Although the Regulations facilitate econom ical movement, on a routine b asis, of many consignm ents which m eet all the relevant regulatory p rescrip tio n s, Section VIII, p aras , rep resen ts a m ost im portant part of the Regulations, p articu larly since it provides a means whereby m aterial associated with re se a rch and development work can be shipped in the packaging which is available and with the minimum of delay. Experience has shown that this is m ost im portant for the nuclear industry, which is in a state of rapid development with applications in many fields, including power generation, engineering and m edicine.

184 SECTION v m 171 SECTION VIII - ADMINISTRATIVE REQUIREMENTS ( ) APPROVAL OF TRANSPORT BY SPECIAL ARRANGEMENT ( ) 812. However, it should be cle a rly understood that the b asic principle underlying the application and approval of any movement by sp ecial arrangem ent is that the o v erall safety, com prising that incorporated in the package design and that represented by the operating controls during the actual m ovem ents, must not be le ss than the overall safety of m ovem ents which comply with all the relevant detailed p rescrip tions of the Regulations. The regulatory requirem ents under Section VIII, p aras , are intended to ensure th is, and specify the inform ation to be included in an application to the competent authorities concerned for approval of a sp ecial a rran g e ment movement and the inform ation to be included in the approval ce rtifica te The level of safety n ecessary in special arrangem ent shipments is norm ally achieved by im posing operational controls to compensate for any deficiencies in the packaging or the shipping procedures. Some of the operational controls which may be effectiv ely employed a re listed below. (a) Exclusive use of vehicle. This provides effective "fu ll load" control of the shipment by the consignor. (b) E sco rt of shipment. The esco rt is norm ally a radiation surveyor who is equipped with survey instrum ents and is fam iliar with em ergency procedures enabling him to identify quickly any radiation and contam ination hazards p resen t and to provide approp riate advice to the civil authorities at the accident scene. The esco rt, whenever p ossible, should trav el in a separate vehicle so that he w ill not be incapacitated by the

185 172 SECTION v n i SECTION VIII - ADMINISTRATIVE REQUIREMENTS ( ) APPROVAL OF TRANSPORT BY SPECIAL ARRANGEMENT ( ) same accident. The esco rt should also be equipped with stakes, ropes, and signs to cordon off an accident area and with a fire extinguisher to control m inor fire s. If absolutely n ecessary, the radiation surveyor m ay be accom panied by police and fire departm ent e sco rts. (c) Routing of shipment may be controlled to avoid are a s of high population density and possible hazards such as steep gradients and railw ay level crossin g s. (d) Tim ing of shipment may be controlled to avoid busy periods such as rush hours and week-end tra ffic peaks. (e) Shipments may have to be d irect, e. g. without stopover or trans-shipm ent, where n ecessary. (f) Transport vehicle speeds may have to be lim ited, p articu larly if the im pact resistan ce of the packaging is low and if the slow er speed of the transport vehicle would not cause additional hazards (such as c o llisions involving faster-m o v in g veh icles). (g) Consideration should be given to the need for giving notification of shipment to civ il au thorities, p articu larly police and fire departments and em ergency plan p a rtic i pants, so that they may be prepared for any contingency. (h) Em ergency procedures (either ad hoc or standing) should exist for any contingenc ie s resulting from the shipment being in volved in an accident. (i) A ncillary equipment such as package-to-vehicle tiedown or shock absorber system s and other protective devices or stru ctu res should be used, where n ecessary, to com pensate for package d eficien cies.

186 SECTION v n i 173 s e c t io n v m - ADMINISTRATIVE REQUIREMENTS ( ) APPROVAL OF TRANSPORT BY SPECIAL ARRANGEMENT ( ) COM PETEN T AUTHORITY 814. Experience has shown that there is a p ra ctica l need for the two kinds of sp ecial arrangem ent d escribed below. (a) The "seaso n tick et" kind, for which a ce rtifica te of approval extends for a sp ecified period, for exam ple a calendar y ear, so enabling movements to be made according to the specified conditions without separate application p rior to each movement. Should there be a need to extend the in itial period, an application is made to the competent authority. (b) The "o n e-o ff" kind where the c e r tificate applies to a p articu lar sp ecific re q u ire m ent. A fter the movement is completed, the ce rtifica te lap ses. CONSIGNOR 815. The great m ajority of sp ecial arran g e m ents involve consignm ents moving by road under full load conditions. Should an e sco rt, for example a separate vehicle carrying fire fighting equipment and following the lead vehicle, be justified on safety grounds, this w ill be laid down in the ce rtificate of approval. If a requirem ent for some form of esco rt is not ju stified on safety grounds and the consignor provides an esco rt for some other reason, for exam ple secu rity, this must be cle a rly understood by a ll concerned. CARRIER 816. The c a r r ie r should give cle a r written instru ctions to h is staff as to the actions

187 174 SECTION v n i SECTION v n i - ADMINISTRATIVE REQUIREMENTS ( ) APPROVAL OF TRANSPORT BY SPECIAL ARRANGEMENT ( ) they must take to fulfil the conditions of the approval ce rtifica te. These may include: the detailed route to be followed; instructions on parking and overnight stops; instructions on speed re strictio n s; instructions on action to be taken in an em ergency, for example erection of isolation b a rrie rs. SPEC IA LLY EQUIPPED TRANSPORT UNIT 817. In some c a s e s, competent authority approval of movements to be made under sp ecial arrangem ent may be facilitated if specially equipped transport vehicles are available. Such vehicles may be provided with: radiation shielding; m oisture-proof su rfa ces to prevent the absorption of rad ioactive m aterials and to facilitate the cleaning and decontamination of working su rfaces; lifting gear; anchoring devices and other m eans of securing radioactive loads; additional em ergency equipment, e. g. decontamination fa cilitie s, absorbent m aterials, rem ote handling devices (length > 1 m), warning signs. CONSIGNOR'S CONSIGNOR RESPONSIBILITIES ( ) 818. The following ch eck list is intended as a general checklist for consignors of Type A and B packages. As drafted, it does not in clude provisions relating to fissile m aterials, but otherw ise includes a ll regu latory provisions, so that a consignor m ay use it to

188 SECTION v n i 175 SECTION VIII - ADMINISTRATIVE REQUIREMENTS ( ) CONSIGNOR S RESPONSIBILITIES ( ) prepare a sim ilar document sp ecific to his type or types of shipment. Although the checklis t item s are presented in a logical ord er, this order may be varied to suit the p articu la r application. (a) Define m aterial p aram eters including: radionuclide(s); activity; form ; decay heat output; other hazardous p ro p erties; if the m aterial is in sp ecial form, a scerta in that the requirem en ts of the sp ecial form design approval ce rtifica te are m et; if the m aterial is irradiated fuel, define additional p aram eters such as cladding m a terial and in tegrity, burn-up, p ostirrad iation decay tim e, etc. (b) Review package design approval ce rtifica te to determ ine that: proposed m aterial loading is within the lim its of "authorized contents"; packaging com plies with ce rtifica te r e quirem ents in a ll resp ects; ce rtifica te is cu rrent. (c) Obtain and becom e fam iliar with draft operating instru ctions for packaging. (d) Inspect packaging and perform m aintenance as n ecessa ry. (e) Where m u ltilateral approval of package design and/or shipment is n ecessary, a scerta in that a ll n ecessa ry competent authority approvals have been obtained.

189 176 SECTION VID SECTION VIII - ADMINISTRATIVE REQUIREMENTS ( ) CONSIGNOR S RESPONSIBILITIES ( ) (f) A fter loading radioactive contents into packaging, secure package closure to perm it rem oval of package from loading facility. (g) On rem oval of package from loading facility: rough check radiation lev els; rough check surface contamination and perform whatever g ro ss decontam ination is n ecessary ; if package has been loaded under w ater, ascertain that water drainage is complete to the degree assum ed in the package design approval; ascertain that any item s added to the package do not com prom ise safety (Section II of the Regulations, para. 208 and Section V, para. 501); com plete the securing of the closure; move package to preparation-for-shipm ent area. (h) P erm it package to reach therm al and/or p ressu re equilibrium as n ecessary or the figures specified in the approval c e r tificate. (i) F in al check radiation lev els. (j) Fin al check non-fixed radioactive contamination on external su rfaces to ensure com pliance with Section V of the Regulations, para (k) A scertain com pliance with the p re shipment requirem ents of Section VII of the R egulations, para (1) A scertain com pliance with appropriate lim itations on maximum p e rm issible su rface tem perature. (m) P erform n ecessary prior-to-sh ip m en t inspections to ensure com pliance with

190 SECTION v n i 177 SECTION VIII - ADMINISTRATIVE REQUIREMENTS ( ) CONSIGNOR S Section VII of the Regulations, p aras 738 r e s p o n s ib il it ie s and 739. ( ) (n) Apply sea l to clo su re. (o) In stall im pact and therm al shields as appropriate. (p) Apply and com plete lab els. (q) Check that n e cessa ry competent authority identification m arks are on package. (r) Make final check for com pliance with a ll requirem ents of package design and shipment approval certifica te s and with the relevant p arts of the Regulations (including regulations for other hazardous p roperties, if appropriate). (s) F o r Type B(U) packages with contents in e x cess of certain cu rie values (see Section VIII of the Regulations, para. 834), ensure that all competent authorities through whose ju risd iction the proposed shipment w ill pass have been provided with a copy of the package approval ce rtifica te. (t) Notify competent au thorities, tra n s port fa cility o p erators, and consignee as appropriate. (u) L ist "p a rticu la rs of consignment" and include "consig n o r's certificatio n " appropriately signed and dated. (v) Provide inform ation for c a r r ie r, including the following as appropriate: consignee, destination, routing; supplementary operational controls; stowage provisions (particularly where package su rface heat flux exceeds 15 W/m2 ); sp ecial handling and tiedown re q u irement and equipment; full load instru ctions; adm inistrative procedures (particu larly

191 178 SECTION vm SECTION VIII - ADMINISTRATIVE REQUIREMENTS ( ) CONSIGNOR* S RESPONSIBILITIES ( ) the relaying of appropriate inform ation to connecting c a r rie rs); special em ergency procedures; appropriate documentation. (w) P rep are a ll n ecessa ry documentation, including radioisotope tra n sfe r authorizations, im port/export authorizations, sales in voices, etc. (x) R elease shipment to c a r rie r The consignor's certification is valid during the com plete transport operation from consignor to consignee unless there is evidence at any stage of leakage of activity; action must then be taken as specified in Section V of the Regulations, p aras QUALITY CONTROL IN FABRICATION AND MAINTENANCE OF PACKAGING (839) 820. The designer of any approved packaging should, p rior to fabrication, establish a quality assu rance program m e [1-3] to ensure that the packaging is manufactured in accordance with the approved design, and should be prepared to provide the competent authority with complete certification that the approved design requirem ents have been fully implemented. The m anufacturer or designer should also prepare provisional operating and maintenance instructions for use by the consignor to ensure integrity of the safety featu res of a ll packaging made to the approved design. The above-m entioned docum ents should constitute part of an application for approval The quality assu rance program m e should cover a ll phases of packaging production, including management and planning,

192 SECTION v in 179 SECTION v n i - ADMINISTRATIVE REQUIREMENTS ( ) QUALITY CONTROL IN FABRICATION AND MAINTENANCE OF PACKAGING (839) design, m aterials procurem ent and fa b ric a tion, inspection, operation and m aintenance and audits. In line with the quality assu rance program m e, the m anufacturer should prepare detailed w ritten procedures for id en tification of m a teria ls, control of fabrication p roc e s s e s, inspections and te sts. F o r these a ctiv ities, national or international standards m ay be used for establishing inspection and te st procedures. Some of the essen tial featu res in fabrication are listed below. (a) The m anufacturer should require the m aterials supplier to certify the quality and conditions of m aterials having a stru ctu ral function or which are subject to s tre s s or corrosion. O therw ise, consideration should be given to the need for analyses of and te sts on a m aterial before its use. Those considered m ay include ch em ical and sp ectro m e tric analysis; dimension and weight checks; te sts for hardness and b rittlen ess (under im pact) and for ten sile, bending, im pact, corrosion, therm al and nuclear p roperties. The p roperties at extrem e operating tem perature should be confirm ed. (b) U nless some certificatio n system is in force to ensure adequate sk ill of w eld ers, their competence should be determined by testing typical sam ple welds. Nondestructive te sts should be made on welds at appropriate stages of m anufacture. This is p articu larly im portant to ensure the quality of p refab ricated components of the packaging. (c) Packaging su b-assem blies should be inspected and checked for proper fit, and consideration should be given to testing them under p re ssu re. Consideration should also be given to interchangeability of sp ares.

193 180 SECTION v m SECTION vm - ADMINISTRATIVE REQUIREMENTS ( ) QUALITY CONTROL IN FABRICATION AND MAINTENANCE OF PACKAGING (839) (d) Welded stru ctu res should be s tre s s relieved where n ecessary. It should be noted that, with lead-shielded packaging, a sm all a ir gap w ill norm ally exist behind a piece welded in the sh ell to close the pour opening. M oreover, to produce an adequate weld, it m ay be n ecessary to provide a backing strip o r air-g ap im m ediately behind the weld seam. P a rticu la r care should be taken to ensure that there are no voids between the lead and the steel into which water m ay seep as a resu lt of undetected corrosion or weld failu re. (e) To ensure that the lead does not ch ill during pouring, it m ay be n ecessary to p re-h eat the shell. (f) The bonding of lead to cladding, when such bonding has been assum ed, should be inspected. Inspection should sim ilarly be made to ensure that voids have not been form ed during solidification of the lead used as a shielding m ateria l. ADVICE TO THE MANUFACTURER 822. The m anufacturer should set up a quality control program m e covering the main phases of m anufacture and select a co n stru c tion method to ensure constant quality of the product. Automation of the fabrication p ro c e s s, or of p arts of it, will help to reach th is goal and to reduce the need for quality control.

194 SECTION v m 181 SECTION VUl - ADMINISTRATIVE REQUIREMENTS ( ) REFERENCES [1 ] MESSENGER, W. de L.M., Tests on Transport Packaging for Radioactive M aterials (Proc. Symp. Vienna, 1971), IAEA, Vienna (1971) 423. [2 ] SHAPPERT, L.B., Tests on Transport Packaging for Radioactive M aterials (Proc. Symp. V ienna, 1971), IAEA, Vienna (1971) 411. [3 ] USAEC, RDT Standard, Quality Assurance Program Requirements, RDT F 2-2 T, USAEC (1969).

195 182 ANNEX TO SECTION VIII ANNEX TO SECTION VIII EXA M PLES OF APPROVAL REQUIREM ENTS TA BLE I. SUMMARY OF THE REQUIREMENTS FOR APPROVAL OF SPEC IA L FORM M ATERIAL AND PACKAGE DESIGNS Subject of approval Competent authority whose approval is required 1 Special form material Country of origin 2 Type A None unless contents are fissile and not exempted from the fissile requirements under Section VI of the Regulations, para Country of origin. 3 Type B(U) Country of origin 4 Type B(M ) Country of origin and all countries en route 5 Fissile packages Package designs complying with Section VI of the Regulations, paras 620, 623 and 624 Package designs complying with Section VI o f the Regulations, paras and 622 All other package designs 6 Packages subject to transport by special arrangement None Country of origin Country of origin and all countries en route Country of origin and all countries en route NOTE: "Country of origin" refers to the country where the design originated.

196 ANNEX TO SECTION VUl 183 TA BLE II. SUMMARY OF THE REQUIREM ENTS FOR APPROVAL O F SHIPMENTS AND PRIOR NOTIFICATION Package 1 Type A Competent authority whose approval is required for each shipment None Prior notification of each shipment 2 Type B(U) Type B (M) Continuously venting None Country of origin and all countries en route Country of origin and all countries en route when contents exceed 3 x Ai or 3 x A2, as appropriate, or 3 x C i, whichever is the least Type B(M ) Not continuously venting Country of origin and all countries en route when contents exceed 3 X 103 Ai or 3 X 103 A2, as appropriate, or 3 x 104 Ci whichever is the least Country of origin and all countries en route Fissile packages Fissile Class I and II None, except where specified for Fissile Class II in the IAEA Regulations Fissile Class III 6 Packages subject to transport under special arrangement: Country of origin and all countries en route Country of origin and all countries en route NOTE: Before shipping a Type B(U ) packagefthe contents of which exceed 3 X 103 Ai or 3 x A2, as appropriate, or 3 x 104 C i, whichever is the least, for the first tim e, the consignor must ensure that copies of each applicable competent authority certificate applying to the design have been submitted to the com petent authority of those countries through or into which it is to be transported.

197

198 G en eral B IB L IO G R A P H Y Internationales Ubereinkommen flber den Eisenbahnfrachtverkehr (CIM). Anlage I. Internationale Ordnung ffir die Beforderung gefshrlicher Guter mit der Eisenbahn (RID), gqltig vom 1 April 1967, Zentralamt fiir den Internationalen Eisenbahnverkehr in Bern, Switzerland (1967). INTERNATIONAL MARITIME CONSULTATIVE ORGANIZATION, International Maritime Dangerous Goods Code, Class 7, Radioactive Substances, Intergovernmental Maritime Consultative Organization, London (1967). INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for the Safe Transport of Radioactive Materials, 1967 Edition, Safety Series No.6, STI/PUB/148, IAEA, Vienna (1967). HMSO, European Agreement Concerning the International Carriage of Dangerous Goods by Road (ADR), Annex A: Provisions Concerning Dangerous Substances and Articles, Annex B: Provisions Concerning Transport Equipment and Transport Operations, Geneva, 30 September 1967, HMSO, London (1968). INTERNATIONAL AIR TRANSPORT ASSOCIATION, IATA Restricted Articles Regulations, 15th Edition, Effective 1 June 1972, International Air Transport Association, Montreal (1972). INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for the Safe Transport of Radioactive Materials, 1973 Revised Edition, Safety Series No.6, STI/PUB/323, IAEA, Vienna (1973). T estin g HMSO, The Efficient Use of Fuel, HMSO, London (1944). DIXON, F.E., PARTRIDGE, A.H., Experimental Work at AERE on the Development of Packaging for Radioactive Materials Which Will Meet the IAEA Regulations, AERE, Rep. R.4810 (1965). GIBSON, R. (Ed.), The Safe Transport of Radioactive Materials, Pergamon Press (1966). INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, The Contents Leakage Test and Radiation Leakage Test, ISO/TC85(85/N95)i International Organization for Standardization, Geneva (1968). UNITED STATES ATOMIC ENERGY COMMISSION, USAEC Rules and Regulations/Title 10 -Part71, Packaging of Radioactive Material for Transport, December 31, 1968, USAEC (1968). DIXON, F.E., An Indexed List with Commentary of Experimental Work Connected with Transport Containers for Radioactive Material Performed at AERE, Harwell, , AERE Rep.R.6797(1971). GRELLA, A.W,, in Tests on Transport Packaging for Radioactive Materials (Proc. Seminar Vienna, 1971), IAEA, Vienna (1971) 29. Package testin g DAVIES, A. J., Description of Various Test Methods Used at AERE Harwell to Comply with the IAEA Regulations for Radioactive Transport Containers, AERE Rep. R.3003 (1959). 185

199 186 This publication is no longer valid FAIRBAIRN, A., in TestsonTransportPackagingforRadioactiveMaterials(Proc.Seminar Vienna, 1971), IAEA, Vienna (1971) 3. BROBST, W.A., ibid, 21. T ests for Type A packaging DIXON, F.E., COHEN, L.R., ibid., 93. DOMANUS, J.C., ibid., 65. T e s ts fo r T ype B packaging?? ts FOCKER, C.M., Dimensional Methods and their Application, E. Arnold and Co. (1953). LANGHAAR, H.L., Dimensional Analysis and Theory of Models, J. Wiley and Sons (1956). CLARKE, H.G., Jr., REDDI, M.M., Structural Integrity of Shipping Containers for Radioactive Materials, Part I, Study of Transport Operations and Container Construction, Appendix A. Feasibility of Applying Model Theory to Simulate Impact Damage of Shipping Containers, NYO Rep (1962). CLARKE, H.G., Jr., ONDERKO, W.E., Model Impact Tests Pertaining to Shipping Containers for Radioactive Materials, TID-7651 (1962) , SHAPPERT, L.B., The Cask Testing Program at the Oak Ridge National Laboratory, TID-7651 (1962) McLENEGAN, D.W., SMITH, C.W., R1PPERGER, E.A., BREEN, J.R., Application of External Energy Absorbers to Large Fission Product Shipping Casks, TID-7651 (1962) SHAPPERT, L.B., Drop Tests Performed on the Franklin Institute s 1/4 Scale Model of a 40-ton Cask, ORNL Rep. No.ORNL-TM-629 (1963). RIPPERGER, E.A., Model Studies of Buffered Shipping Containers for Fission Products, Rep. No. HW-77963, Univ. of Texas (1963). CLARKE, H.G., Jr., Experimental Studies of Cask Impact Resistance, SC-RR (1965) SAYWELL, G.L., Destructive Drop Tests of a Model Fuel Shipping Cask, SC-RR (1965) CLARKE, H.G., Jr., Impact resistance of casks, Nuclear Engng - Part XIV, Chem. Engng Progr. Symp. Series No.56 61, A.I.Ch.E., New York, N.Y. (1965) ROWE,; R.E., BASE, G.D., "Model Analysis and Testing as a Design Tool, Proc. Inst. Civil Engineers, Paper No , February BLOMQUIST, R., JONASSON, G., Packaging and Transportation of Radioactive Materials (Proc. 2nd Int. Symp. Gatlinburg, 1968), Union Carbide Corporation and USAEC, Gatlinburg (1968) 354,

200 187 CLARKE, B.C., Jr., ibid., 373. EVANS, J.H., NELANS, H.A., STODDART, W.C., ibid., 253. JETTER, R.I., ibid., 607. WILSON, E.J., PARTRIDGE, A.H., ibid., 245. A OKI, S., in Tests on Transport Packaging for Radioactive Materials (Proc. Seminar Vienna, 1971), IAEA, Vienna (1971) 539. IRVINE, A.R., SHAPPERT, L.B., EVANS, J.H., DAVIS, F.C., ibid., 587. SHIMOMURA, S., KANAE, Y., MURAMATSU, A., AOKI, S., NAKATA, S., NAKAZAWA, H., ibid., 549. WILLIAMSON, S., ibid., 563. WILLIAMSON, S., ibid., 603. T h e rm a l tests_ McADAMS, W.H., Heat Transmission, McGraw-Hill (1954). CARSLAW, H.S., JAEGER, J.C., Conduction of Heat in Solids, Oxford University Press, London, Oxford (1959). FISHENDEN, M., SAUNDERS, O.A., Introduction to Heat Transfer, Oxford University Press (1961). REDDI, M.M., Structural Integrity o f Shipping Containers for Radioactive M aterials, Part II: Some Aspects of Fire Simulation in Shipping Container Studies, NYO Rep (1964). TEAGUE, H. J., BROOK, A.J., "Approximate calculative assessment made relating to wall temperatures and behaviour of cask in fire test", Proc. Int. Symp. for Packaging and Transportation of Radioactive Materials, Sandia Corporation SC-RR-65-98, USA (1965) 732. WACHTEL, G.P., "Can we model a fire test", Proc. Int. Symp. for Packaging and Transportation of Radioactive Materials, Sandia Corporation, SC-RR-65-98, USA (1965) 133. AUPETIT, J., "Resistance to fire of lead-lined casks", Proc. Int. Symp. for Packaging and Transportation of Radioactive Materials, Sandia Corporation SC-RR-65-98, USA (1965) 473. LANGHAAR, J.W., "The problem of demonstrating resistance to fire", Packaging and Transportation of Radioactive Materials (Proc. 2nd Int. Symp. Gatlinburg, 1968), Union Carbide Corporation and USAEC, Gatlinburg (1968) 292. MORIYA, T., "Test and theoretical analysis of fire resistivity of beta-ray thickness gauge containers", ibid., 477. VEITH, K.-H., "Assessment of the thermal behaviour of irradiated fuel casks", ibid., 306. BROOK, A. J., intestsontransportpackagingforradioactivematerials (Proc.Seminar Vienna, 1971), IAEA, Vienna (1971) 467. TAYLOR, W.R., ibid., 479. TEAGUE, H.J., ibid.,455.

201

202 PA N E L ON TECHNICAL REQUIREM ENTS FOR IM PLEM ENTING THE AGENCY'S TRANSPORT REGULATIONS (P an el of E x p e rts w hich P r e p a re d the A d v iso ry M ate ria l) V ienna, 1-5 N ovem ber 1971 C h airm an F a ir b a ir n, A.D. U nited Kingdom A tom ic E n e rg y A uthority, R isley, U nited Kingdom P a n e l m e m b e rs AUSTRALIA F ry, R.M. CANADA B lackburn, R.W. C a n b e rra H ouse, London, U nited Kingdom A tom ic E nergy C ontrol B oard, Ottawa FRANCE R edon, A. C e n tre d etudes n u c le a ire s, F o n te n a y -a u x -R o ses/s e in e GERMANY, FED ERA L REPU BLIC OF V eith, K. H. B undesanstalt fu r M aterialprufung, B erlin ITALY F a illa, L idia C om itato N azio n ale p e r l'e n e rg ia N u cleare, R om e 189

203 assisted by F o r a s a s s i, M. JAPAN A oki, S._ a s s is te d by O nodera, A. POLAND M usialow icz, T. UNITED STATES OF B a rk e r, R. USSR M artynov, S. P. Istitu to di Im pianto N u c le a ri, U n iv e rsita di P is a, P is a Tokyo Institute of Technology, Tokyo H itachi Ship B uilding and E n g in eerin g C o., Tokyo C e n tra l L a b o ra to ry fo r R adio logical P ro te c tio n, W arsaw AM ERICA D ivision of R a d iatio n P ro te c tio n S tan d ard s, US A tom ic E n e rg y C om m ission, W ashington, D. C. A ll Union Office "Isotope", Moscow S c ien tific S e c re ta ry Swindell, G.E. D ivision of N u clear Safety and E n v iro n m ental P rotectio n, In te rn a tio n a l A tom ic E n e rg y A gency, V ienna, A u stria

204 HOWTO ORDER IAEA PUBLICATIONS Exclusive sa le s a g e n ts fo r IAEA publications, to w hom all orders and inquiries should b e ad d ressed, have been appointed in th e follow ing countries: UNITED KINGDOM Her M ajesty's Stationery Office, P.O. Box 569, London SE1 9NH UNITED STATES OF AMERICA UNIPUB, Inc., P.O. Box 433, New York, N.Y In th e follow ing cou ntries IAEA publications m ay b e pu rch ased from the sales ag e n ts or booksellers listed or through your m ajor local booksellers. P aym en t can b e m ad e in local currency or with UNESCO coupons. ARGENTINA AUSTRALIA BELGIUM CANADA C.S.S.R. FRANCE HUNGARY INDIA ISRAEL ITALY JAPAN NETHERLANDS PAKISTAN POLAND ROMANIA SOUTH AFRICA SPAIN SWEDEN U.S.S.R. YUGOSLAVIA Comisi6n Nacional de Energta At6rruca, Avenida del Libertador 8250, Buenos Aires Hunter Publications, 58 A Gipps Street, Collingwood, Victoria 3066 Office International de Librairie, 30, avenue Marnix, Brussels 5 Information Canada, 171 Slater Street, Ottawa, Ont. K1 A OS 9 S.N.T.L., Sp len6 51, Prague 1 Alfa, Publishers, Hurbanovo n^mestie 6, Bratislava Office International de Documentation et Librairie, 48, rue Gay-Lussac, F-75 Paris 5e Kultura, Hungarian Trading Company for Books and Newspapers, P.O. Box 149, Budapest 62 O xford Book and Stationery Com p., 17, Park Street, Calcutta 16 Heiliger and Co., 3, Nathan Strauss Str., Jerusalem Libreria Scientifica, D ott.de Biasio Lucio "aeiou", Via Meravigli 16, Milan Maruzen Company, Ltd., P.O. Box Tokyo International Marinus Nijhoff N.V., Lange Voorhout 9-11, P.O. Box 269, The Hague Mirza Book Agency, 65, The Mall, P.O. Box 729, Lahore-3 Ars Polona, Centrala Handlu Zagranicznego, Krakowskie Przedmiescie 7, Warsaw Cartimex, Decembrie Street, P.O. Box , Bucarest Van Schaik's Bookstore, P.O. Box 724, Pretoria Universitas Books (Pty) Ltd., P.O. Box 1557, Pretoria Nautronica, S.A., P6rez Ayuso 16, Madrid-2 C.E. Fritzes Kungl. Hovbokhandel, Fredsgatan 2, Stockholm 16 Mezhdunarodnaya Kniga.Smolenskaya-Sennaya 32-34, Moscow G-200 Jugoslovenska Knjiga, Terazije 27, Belgrade O rders from cou ntries w h ere sa le s a g e n ts have not y e t b een appointed and req u ests fo r inform ation should be addressed directly to: ^ Publishing Sectio n, International A tom ic E nergy A gency, Karntner Ring 11, P.O.Box 5 9 0, A-1011 V ien n a, Austria

205 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1973 PRICE: US $7.00 A ustrian Schillings 147,- ( 2.90; F.Fr. 32, ; DM 20,- SUBJECT GROUP: II H ealth, Safety and W aste M anagem ent/ R adiation P rotection