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Report in Accordance with PARCOM Recommendation 91/4 on Radioactive

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Report in Accordance with PARCOM Recommendation 91/4 on Radioactive Sixth Implementation Report: Report in accordance with PARCOM Recommendation 91/4 on radioactive discharges Norway Radioactive Substances Series 2014 Sixth Implementation Report: Report in Accordance with the PARCOM Recommendation 91/4 on Radioactive Discharges by Norway OSPAR Convention Convention OSPAR The Convention for the Protection of the La Convention pour la protection du milieu Marine Environment of the North‐East marin de l'Atlantique du Nord‐Est, dite Atlantic (the “OSPAR Convention”) was Convention OSPAR, a été ouverte à la opened for signature at the Ministerial signature à la réunion ministérielle des Meeting of the former Oslo and Paris anciennes Commissions d'Oslo et de Paris, Commissions in Paris on 22 September 1992. à Paris le 22 septembre 1992. La Convention The Convention entered into force on 25 est entrée en vigueur le 25 mars 1998. March 1998. It has been ratified by Belgium, La Convention a été ratifiée par l'Allemagne, Denmark, Finland, France, Germany, Iceland, la Belgique, le Danemark, la Finlande, Ireland, Luxembourg, Netherlands, Norway, la France, l’Irlande, l’Islande, le Luxembourg, Portugal, Sweden, Switzerland and the United la Norvège, les Pays‐Bas, le Portugal, Kingdom and approved by the European le Royaume‐Uni de Grande Bretagne Community and Spain. et d’Irlande du Nord, la Suède et la Suisse et approuvée par la Communauté européenne et l’Espagne. Acknowledgement This report has been prepared by the Norwegian Federal Nuclear Safety Inspectorate (ENSI) 2 OSPAR Commission, 2014 Contents Introduction ............................................................................................................................................. 6 1. General information ............................................................................................................................ 6 1.1 Implementation of BAT/BEP in terms of the OSPAR Convention in Norwegian legislation/regulation ................................................................................................................ 6 1.2 Dose constraints/limits for nuclear facilities ............................................................................ 7 1.3 Discharge limits ......................................................................................................................... 7 1.4 Monitoring programmes of environmental concentrations of radionuclides .......................... 7 1.5 Environmental norms and standard (other than dose standards for humans) ........................ 8 1.6 National authority responsible for supervision of discharges .................................................. 8 1.7 Nature of inspection and surveillance programmes ................................................................ 8 2. Site–Specific Information ‐ Institute for Energy Technology, Kjeller ....................................... 8 2.1 Site characteristics .................................................................................................................... 8 2.1.1 Name of site .................................................................................................................... 8 2.1.2 Type of facility ................................................................................................................. 8 2.1.3 Year of commissioning/licensing/decommissioning....................................................... 9 2.1.4 Location ........................................................................................................................... 9 2.1.5 Receiving waters and catchment area, including, where relevant, information on water flow of receiving rivers ................................................................................... 9 2.1.6 Production ....................................................................................................................... 9 2.1.7 Other relevant information ............................................................................................. 9 2.2 Discharges ................................................................................................................................. 9 2.2.1 Systems in place to reduce, prevent or eliminate discharges of radioactive substances to the marine environment ........................................................................ 9 2.2.2 Efficiency of abatement systems .................................................................................. 11 2.2.3 Annual liquid discharges ............................................................................................... 12 2.2.4 Emissions to air ............................................................................................................. 13 2.2.5 Systems for quality assurance ....................................................................................... 13 2.2.6 Site specific target discharge values ............................................................................. 13 2.2.7 Any relevant information not covered by the requirements specified above ............. 14 2.2.8 Explanations for lack of data or failure to meet BAT/BEP indicators, as well as, when appropriate, a description of on‐going or planned activities. ........................... 14 2.2.9 Summary evaluation ..................................................................................................... 14 2.3 Environmental impact .............................................................................................................15 2.3.1 Concentrations of radionuclides of concern in representative samples of water, sediment and fish ........................................................................................................ 15 2.3.2 Environmental monitoring programme, frequency of sampling, organisms ............... 16 2.3.3 Systems for quality assurance of environmental monitoring program ........................ 16 2.3.4 Any relevant information not covered by the requirements specified above ............. 17 2.3.5 Explanations for lack of data or failure to meet BAT/BEP indicators, as well as, when appropriate, a description of on‐going or planned activities ............................ 17 2.3.6 Summary evaluation ..................................................................................................... 17 2.4 Radiation doses to the public .................................................................................................18 2.4.1 Average annual effective dose to individuals within the critical group ........................ 18 2.4.2 Total exposures ............................................................................................................. 18 2.4.3 The definition of the critical group(s) ........................................................................... 18 2.4.4 Information on exposure pathway(s) ........................................................................... 19 3 Sixth Implementation Report: Report in Accordance with the PARCOM Recommendation 91/4 on Radioactive Discharges by Norway 2.4.5 Basis for methodology to estimate doses ..................................................................... 19 2.4.6 Site‐specific factors ....................................................................................................... 19 2.4.7 Site specific target annual effective dose ..................................................................... 19 2.4.8 Systems for quality assurance of processes involved in dose estimates ...................... 19 2.4.9 Any relevant information not covered by the requirements specified above ............. 19 2.4.10 Explanations for lack of data or failure to meet BAT/BEP indicators ......................... 20 2.4.11 Summary evaluation ................................................................................................... 20 2.5 Summary BAT/BEP ..................................................................................................................20 3. Site‐Specific Information – Institute for Energy Technology, Halden ............................................... 21 3.1 Site characteristics ..................................................................................................................21 3.1.1 Name of site .................................................................................................................. 21 3.1.2 Type of facility ............................................................................................................... 21 3.1.3 Year of commissioning/licensing/decommissioning..................................................... 21 3.1.4 Location ......................................................................................................................... 21 3.1.5 Receiving waters and catchment area, including, where relevant, information on water flow of receiving rivers ................................................................................. 21 3.1.6 Production ..................................................................................................................... 21 3.1.7 Other relevant information ........................................................................................... 21 3.2 Discharges ...............................................................................................................................22 3.2.1 Systems in place to reduce, prevent or eliminate discharges of radioactive substances to the marine environment .....................................................................
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