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Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

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Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Report of the Federal Republic of Germany for the Sixth Review Meeting in May 2018 Table of Contents - 3 - Table of Contents List of Figures ............................................................................................................................... 8 List of Tables ............................................................................................................................... 11 List of Abbreviations .................................................................................................................. 14 Summary ..................................................................................................................................... 21 A Introduction .......................................................................................................................... 31 A.1 Structure and content of the report ........................................................................... 31 A.2 Historical development and current status of utilisation of nuclear energy .......... 32 A.3 Overview ..................................................................................................................... 42 B Policies and practices ......................................................................................................... 45 B.1 Reporting .................................................................................................................... 45 B.1.1 Spent fuel management policy .......................................................................... 45 B.1.2 Spent fuel management practices..................................................................... 46 B.1.3 Radioactive waste management policy ............................................................. 46 B.1.4 Radioactive waste management practices ........................................................ 47 B.1.5 Criteria used to define and categorise radioactive waste .................................. 47 C Scope of application ............................................................................................................ 51 C.1 Spent fuel and radioactive waste from civil use of nuclear energy ........................ 51 C.2 Distinction between NORM and radioactive waste .................................................. 51 C.2.1 Practices ........................................................................................................... 52 C.2.2 Work activities .................................................................................................. 52 C.2.3 Future amendments resulting from the new Radiation Protection Act ............... 55 C.3 Spent fuel and radioactive waste from the military sector ...................................... 55 C.4 Radioactive discharges .............................................................................................. 55 D Inventories and lists ............................................................................................................ 57 D.1 Spent fuel management facilities .............................................................................. 59 D.1.1 On-site storage facilities of nuclear power plants .............................................. 61 D.1.2 Central storage facilities ................................................................................... 62 D.1.3 AVR cask storage facility in Jülich .................................................................... 65 D.1.4 Pilot conditioning plant ...................................................................................... 66 D.2 Spent fuel inventory ................................................................................................... 66 D.2.1 Spent fuel quantities ......................................................................................... 66 D.2.2 Activity inventory ............................................................................................... 71 D.2.3 Predicted amounts ............................................................................................ 72 D.3 Radioactive waste management facilities ................................................................. 73 D.3.1 Conditioning plants ........................................................................................... 73 D.3.2 Storage facilities ............................................................................................... 73 D.3.3 Repositories ..................................................................................................... 75 D.3.4 Asse II mine ...................................................................................................... 78 D.4 Inventory of radioactive waste .................................................................................. 82 D.4.1 Inventory of radioactive waste and forecast ...................................................... 82 Table of Contents - 4 - D.4.2 Inventory of the Morsleben repository for radioactive waste .............................. 87 D.4.3 Inventory of the Asse II mine ............................................................................ 89 D.4.4 Inventory from past practices ............................................................................ 91 D.5 List of decommissioned facilities .............................................................................. 91 D.5.1 Overview .......................................................................................................... 91 D.5.2 Power reactors ................................................................................................. 92 D.5.3 Experimental and demonstration reactors ......................................................... 93 D.5.4 Research reactors ............................................................................................ 93 D.5.5 Nuclear fuel cycle facilities ................................................................................ 93 D.5.6 Status of some current decommissioning projects ............................................ 93 E Legislative and regulatory system.................................................................................... 103 E.1 Article 18: Implementing measures ......................................................................... 104 E.1.1 Implementation of the obligations under the Convention ................................. 104 E.2 Article 19: Legislative and regulatory framework .................................................. 104 E.2.1 Legislative and regulatory framework ............................................................. 104 E.2.2 National safety provisions and regulations ...................................................... 108 E.2.3 Licensing system ............................................................................................ 121 E.2.4 System of prohibiting the operation of a facility without licence ....................... 132 E.2.5 Regulatory inspection and assessment (supervision) ..................................... 132 E.2.6 Enforcement of provisions and terms of the licences ...................................... 134 E.2.7 Responsibilities ............................................................................................... 136 E.3 Article 20: Regulatory body ..................................................................................... 137 E.3.1 Regulatory body ............................................................................................. 137 E.3.2 Effective independence of the regulatory functions ......................................... 145 F Other general safety provisions ....................................................................................... 147 F.1 Article 21: Responsibility of the licence holder ...................................................... 147 F.1.1 Responsibility of the licence holder ................................................................. 147 F.1.2 Responsibility if there is no licence holder ...................................................... 148 F.2 Article 22: Human and financial resources ............................................................. 149 F.2.1 Human resources ........................................................................................... 149 F.2.2 Financial resources during operation and decommissioning ........................... 151 F.2.3 Financial resources after closure of a repository ............................................. 153 F.3 Article 23: Quality assurance ................................................................................... 154 F.3.1 Quality assurance ........................................................................................... 154 F.3.2 Product control ............................................................................................... 154 F.4 Article 24: Operational radiation protection ........................................................... 159 F.4.1 Basis .............................................................................................................. 159 F.4.2 Radiation exposure of occupationally exposed persons .................................. 160 F.4.3 Radiation exposure of the general public ........................................................ 162 F.4.4 Measures to prevent unplanned and uncontrolled releases ............................ 163 F.4.5 Limitation of operational
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