Architecture and management of a geological repository - Andra

11 – Operational SafetyResultsTable 11.1.2Estimate of the annual dose received by the operators (mSv/year/person)operating in nuclear installationsActivityNuclear surface installationsReception of primary packagesControl of primary packagesInsertion of empty containersPreparation of disposal packagesControl of disposal packagesType of packageAnnual dose peroperator(mSv/year/operator)B / C 2.1SF (UOx) 4B / C 1SF (UOx) 1B / C 1.3SF (UOx) 1B 1.5C 1.5SF (UOx) 1.4B 1C 0.9SF (UOx) 0.8B 1.6C 0.9Placement of disposal packages intransfer casks and inspection oftransfer transfer casks at the surface SF (UOx) 1Surface control room / 0.5Surface monitoring / 2.3Surface maintenance / 3.7Underground nuclear installationsB 1.2Transfer and emplacement of thedisposal packages in cellsInstallation of cell plugsTransfer transfer cask inspectionat the bottomC 1.3SF (UOx) 4C 0.6SF (UOx) 0.9B 0.9C 1.1SF (UOx) 0.8Underground control room / 0.5Underground monitoring //maintenance2.2It is clear from these results that the highest values, between 2 and 4 mSv/year, would be associatedwith the reception of primary packages, the transfer and emplacement in the cell of disposal packagesand monitoring and maintenance of the installations. The values associated with other activities wouldbe less than 2 mSv/year.Doses received by personnel on site would therefore be lower than the limit set by Andra (5 mSv/year)and well below the statutory limit (20 mSv/year).• Dosimetric evaluation for members of the public around the periphery of the siteExternal exposure is not taken into account for members of the public in this evaluation on account ofthe distance between them and the nuclear installations.DOSSIER 2005 ARGILE -ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL DISPOSAL SYSTEM441/495