The Application of Exemption Values to the Transport of Radioactive Materials

Year
1995
Author(s)
P François - Institut de Protection et de Surete Nucleaire (IPSN), Av. du General Leclerc, B P N° 6, F-92265 Fontenay-aux-Roses, France.
J. Lombard - Institut de Protection et de Sûreté Nucléaire (IPSN), France
A. Carey - National Radiological Protection Board
M. Harvey - National Radiological Protection Board
J. S. Hughes - National Radiological Protection Board (NRPB), UK
S. Mobbs - National Radiological Protection Board
K. B. Shaw - National Radiological Protection Board (NRPB), UK
D. Raffestin - Centre d 'Etude sur I 'Evaluation de Ia Protection dans le Domaine Nucléaire
T. Schneider - Centre d 'Etude sur I 'Evaluation de Ia Protection dans le Domaine Nucléaire
File Attachment
462.PDF1.61 MB
Abstract
The principles and methods for establishing exemption values have been published by the European Commission DG XI (Radiation Protection 65) and endorsed by the International Atomic Energy Agency (Basic Safety Standards). These documents contain activity and activity concentration values below which reporting is not required. The exemption values are such that the radiological risk or detriment associated with the practice is so small as not to warrant the imposition ofthe system of reporting or prior authorization. Sources below the exemption values are of no regulatory concern for the I A EA. The main objective of this study is to examine the relevance of the BSS exemption values to the transport regulation. With regard to the IAEA transport regulation (Safety Series n°6), the Revision Panel of the transport regulation (RP3) and the Standing Advisory Group of the Safe Transport of Radioactive Material (SAGSTRAM -XI) endorsed the basic dose criteria of the International Basic Safety Standards for Protection Against Ionizing Radiation (BSS) and for the Safety of Radiation Sources (Safety Series No. I I 5-1). The basic dose criteria in all feasible situations for exemption used by the BSS are: