Solid Radioactive Waste Strategy Report.pdf - UK EPR

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EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 162 / 257 10.1.4.6 Records for Decommissioning Throughout the EPR’s life-cycle, information required for decommissioning purposes will be identified, prepared, up-dated and maintained. The information retained for decommissioning operations will include: · Facility design and subsequent modifications; · Operational history; · Incidents and associated response or remedial actions; · Radiological surveys; · Radioactive substances, waste quantities, locations, condition and ownership; · Safety cases; · Physical condition of the EPR and site, including evidence from the Examination, Maintenance, Inspection and Testing record; · Knowledge of relevant staff. Documents related to decommissioning, including the decommissioning plan, end-state and decommissioning history will be generated and retained in a manner consistent with the predicted timescales of the decommissioning operations. 10.1.4.7 British Radwaste Management Information System (BRIMS) In addition to the radioactive waste records described above. Information on wastes can also be stored in the Britisih Radwaste Management Information System (BRIMS). BRIMS is a suite of databases used to store and compile data for the Radioactive Waste Inventory that is used for the short and long-term management of waste. This is conducted on behalf of the Crown with the Intellectual Property Rights belonging to Defra. It is, however, maintained by the nuclear industry as a whole, including the regulators and the government, and also receives financing from the HSE. The system has become the industry wide tool and will be maintained for the foreseeable future. Defra has proposed that by 2010 it could become a “live” inventory with it being able to be accessed and/or amended whenever necessary rather than at the current three year intervals [Ref.52]. The individual waste packages stored on-site will be marked/labelled (i.e. bar codes, engraving) and these will be related back to BRIMS where data concerning that specific waste package will be kept [Ref. 53].
EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 163 / 257 10.2 Strategy And Assumptions The following strategic baseline and assumptions underline this solid operational waste management strategy: 1) The operational WTB and Intermediate Waste Storage Facility (ISF) are separated and independently operated. 2) If possible the liquid and solid waste treatment and conditioning systems are of modular design (e.g. skid mounted) permitting upgrade and replacement as new technologies become available. 3) VLLW and LLW that are exempt from regulatory control are immediately shipped off-site. The WTB storage area provides a buffer for waste packages conditioned. The buffer zone will have sufficient capacity to meet production rates over a cycle. 4) VLLW can be disposed of in its immediate state. No treatment, conditioning or special packaging will be used for VLLW. Resins will be dewatered. 5) VLLW and LLW disposal sites will be available at the time of NPP start up. 6) The utility may choose to perform only basic treatment steps for solid VLLW/LLW on site and send these wastes directly to centralised off-site facilities for conditioning. 7) Combustible wastes can be directly sent to central (off-site) incineration facilities. At the time of the NPP start up such facilities will be internationally or nationally available and accessible. The waste building storage area provides buffer storage for waste generated during a reactor cycle to be sent to an incinerator. 8) Wastes that are suitable for melting will be directly sent to central (off-site) smelting facilities after pre-treatment, for example sorting and compaction. At the time of NPP start up such facilities will be internationally or nationally available and accessible. The waste building storage area provides buffer storage for packages generated over 1 reactor cycle. 9) Residues from off-site processing such as incineration and melting (e.g. slag) are not returned to the NPP but subject to further treatment in the off-site processing facility. 10) ISF design life will be 100 years and all ILW will be stored there until such time as the GDF becomes available. 11) ILW is transferred to the ISF immediately after treatment and/or conditioning. The waste building provides an 18 month buffer capacity. The waste building provides buffer storage for 1 reactor cycle. 12) The utility could decide to condition waste in its primary packaging and store for extended periods until sufficient decay has taken place or until off-site shipment for final disposal is scheduled. 13) ILW wastes that go into on-site storage will be immediately retrievable. If following decay the activity of such packages is below the threshold for ILW, these packages will be removed from storage and sent off-site as LLW. 14) The NPP will operate its own active laundry. As such these effluents are routed to the waste treatment systems prior to discharge. 15) The discharge limits set for plant operations in the context of the OSPAR treaty do not exceed the discharges that are based in current treatment technology and best practice in 2008.
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