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Name	Category	Date	Size
EPR UK Decommissioning Waste Inventory.pdf	Supporting Documents	20-06-2023	95.83 KB
This document provides an evaluation of UK EPR™ decommissioning waste, based on the assumption that decommissioning begins immediately after 60 years of UK EPR™ operation, in order to maximise activated matters volumes. The analysis identifies the masses in the different level of waste categories, depending on the origin of the equipment and structure in the plant, and includes waste generated by decommissioning activities. The study also introduces types and volumes of packaged nuclear wastes. Download
Dry Interim Storage Facility for ILW.pdf	Supporting Documents	20-06-2023	2.64 MB
This document presents a clear and concise description of the design and operation of the proposed interim storage facility for intermediate level waste packages from a UK EPR™ plant for 60 years of operation. The document describes the UK legislation and safety requirements that will be met by the facility, and the methodology that will be followed for the detailed design studies of the facility. Although the detailed design is not complete, none of the features are novel, they all employ proven technology. The document demonstrates that the proposal is licensable in the UK. Download
Decontamination.pdf	Supporting Documents	20-06-2023	673.36 KB
This document provides additional information on decontamination during operation, maintenance and decommissioning. The following issues are addressed: decontamination during operation and maintenance; minimisation of decontamination waste arising from the UK EPR™; and decontamination during Post Operation Clean Out (POCO) and during decommissioning. Download
Decommissioning.pdf	Supporting Documents	20-06-2023	2.4 MB
This document demonstrates the feasibility of decommissioning the UK EPR™ (including decommissioning of the interim storage facilities for Spent Fuel and ILW), using current technology, and demonstrates that the design allows decommissioning to be carried out in a controlled, careful and systematic manner. The baseline decommissioning plan covers the entire lifecycle of the site, including achieving operational shutdown, performance of Post Operational Clean Out, a care and maintenance period, if this should be required, and decommissioning to a state that is suitable for its future intended use. Download
Critique of the NDA RWMD Disposability Assessment.pdf	Supporting Documents	20-06-2023	45.62 KB
This document provides an EDF/AREVA critique of the NDA RWMD Disposability Assessment reports. The principal issues arising from the review process are outlined, and each issue is briefly discussed, noting how the issue is expected to be resolved. Overall, EDF and AREVA concur with RWMD that the issues can be addressed by the operator under the Letter of Compliance process. Download
Comparison with HSE_NII SAPs.pdf	Supporting Documents	20-06-2023	1.94 MB
This document provides an assessment of the UK EPR™ design against the HSE_NII Safety Assessment Principles (SAPs), which express HSE_NII views on relevant good practice in reactor design and operation, and against which it assesses safety submissions for civil nuclear facilities in the UK. This comparison between the UK EPR™ design and the expectations of the SAPs is intended to be a contribution to the demonstration that the EPR™ design process has followed "relevant good practice", as required by the guidance from HSE_NII in application of the ALARP principle. The EPR™ design was developed within a French and German framework involving both national Safety Authorities, following a specific set of recommendations for the design of new PWRs, known as the "Technical Guidelines", which were the fundamental requirements applied to the EPR™ design. Subsequently, the EPR™ design was compared against international standards such as IAEA safety guidelines, EURs and WENRA reference levels. These guidelines and principles do not correspond in all respects to the recommended practices suggested in the SAPs. Nonetheless, it is considered that all the key nuclear safety requirements embodied in the SAPs are met by the UK EPR™ design, and in particular that the UK EPR™ achieves the fundamental objective that the radiological risk to workers and the public is as low as reasonably practicable, which is the basic legal requirement underpinning UK nuclear safety regulations. Download
Case for Disposability of Spent Fuel and ILW.pdf	Supporting Documents	20-06-2023	229.77 KB
This document provides information on how and when the issues raised by the Radioactive Waste Management Directorate (RWMD) Disposability Assessment of EPR™ waste and spent fuel will be addressed. Each of the issues is discussed and it is concluded that it will be the responsibility of the site operator to address the issues discussed as part of the normal site licensing and regulatory processes. Download
BAT Demonstration.pdf	Supporting Documents	20-06-2023	659.94 KB
This document provides a key reference to the GDA UK EPR™ Integrated Waste Strategy (IWS) document. The information presented demonstrates that the Best Available Techniques (BAT) are being applied in the design of the EPR™ to minimise radioactive wastes at source and to minimise the impacts of the disposal of wastes into the environment. Much of the information presented has been drawn from the PCER, but other information has also been used, including international literature relating to waste management and detailed technical reports. Potential radionuclides are identified, and their significance assessed. For the small number of radionuclides that are assessed as significant, more detailed information has been provided in "BAT forms", in particular on the minimisation techniques applied and conformance with the IWS. The report covers the radioactive wastes arising from reactor operations, noting that the optimised EPR™ design will influence decommissioning waste management requirements. Download
Chapter 12 - Non-radiological Impact Assessment.pdf	Pre-Construction Environmental Report (PCER)	20-06-2023	820.39 KB
Chapter 12, Non radiological Impact Assessment, comprises 7 sub-chapters. Sub-chapters 12.1 and 12.2 identify the potential impacts of the UK EPR™ on the terrestrial and aquatic ecosystems, including the impact of chemical discharges. Sub-chapter 12.3 presents an ecological impact assessment for a representative site. Sub-chapter 12.4 identifies potential socio-economic impacts of the UK EPR™ and outlines the overall approach to stakeholder engagement. Sub-chapter 12.5 outlines the potential uncertainties associated with the methods used for the assessment of non-radiological impacts. Sub-chapter 12.6 outlines the objectives of the site specific environmental protection and monitoring programme which will be established. Sub-chapter 12.7 summarises the initial results of the generic non radiological impact assessments, and outlines the further work that will be required. Download
Chapter 11 - Radiological Impact Assessment.pdf	Pre-Construction Environmental Report (PCER)	20-06-2023	840.81 KB
Chapter 11, Radiological Impact Assessment, comprises 5 sub-chapters. Sub-chapter 11.1 describes the methodology and assumptions used for an initial conservative radiological assessment of the dose from radioactive waste discharges to the environment, and identifies those discharges requiring more detailed assessment . A generic annual dose to the public is calculated. Calculations of potential short term doses from gaseous discharges, doses associated with the potential build up of radionuclides in the local environment over the station lifetime, and collective doses to wider populations from atmospheric and liquid discharges are also presented. Sub-chapter 11.2 describes the methodology used to assess the impact from radioactive discharges on non-human species and presents calculated doses to both terrestrial animal and plant, and marine organisms. Sub-chapter 11.3 outlines the uncertainties associated with the methods used for the assessment of radiological impacts on human health and non human species. Sub-chapter 11.4 outlines the methods and options available for radiological monitoring and sampling, covering both the terrestrial and marine environments. Sub-chapter 11.5 summarises the results of the radiological assessments presented in this chapter. Download
Chapter 10 - Site Environmental Characteristics.pdf	Pre-Construction Environmental Report (PCER)	20-06-2023	260.46 KB
Chapter 10, Site Environmental Characteristics, comprises 6 sub-chapters. It should be noted that most of the sub chapters are currently largely templates which will be completed for a specific site. Sub-chapter 10.1 provides a short introduction and outlines where information can be found within Chapter 10. Sub-chapters 10.2 and 10.3 outline the information required to characterise the terrestrial and aquatic ecosystems beyond the influence of the nuclear power station. Sub-chapter 10.4 outlines the information required to facilitate the identification of designated sites, sensitive habitats, and protected species. Sub-chapter 10.5 outlines the information required to characterise the human reference state, including regional demographics, agriculture, food intake, recreational fishing and leisure activities, noise, access and traffic. Sub-chapter 10.6 outlines the information required to characterise the radiological reference state, including: radio-ecological studies to provide the baseline occurrence of natural and artificial radionuclides in the terrestrial and marine environments. Download
Chapter 8 - Best Available Techniques.pdf	Pre-Construction Environmental Report (PCER)	20-06-2023	668.15 KB
Chapter 8, Best Available Techniques (BAT), comprises 4 sub-chapters. Sub-chapter 8.1 outlines the scope and objectives, and gives an overview of the concept of BAT, together with an outline of the OECD decision-aiding strategy for effluent discharges and solid waste options based on optimisation factors which demonstrate the application of BAT. Sub chapter 8.2 outlines the EPR™ design process, demonstrating how optimisation of effluent management has been an integral part of the design process from the earliest design stage. The main optimisation measures are assessed in the context of the OECD optimisation factors. The expected environmental performance of the UK EPR™ is evaluated, and compared with existing facilities. Sub-chapter 8.3 describes the application of BAT standards and good practices within the UK EPR™ design. Information is also provided on compliance of the effluent treatment systems with relevant safety classifications; minimisation of unplanned emissions to groundwater; and management and disposal of non-radioactive liquid waste streams over the lifetime of the facility. Sub-chapter 8.4 presents a justification that the monitoring methods implemented for the UK EPR™ radioactive discharges (including the discharge and environmental monitoring programme) represent the best available techniques. Download
Chapter 7 - Measures for Monitoring the Discharges.pdf	Pre-Construction Environmental Report (PCER)	20-06-2023	383.86 KB
Chapter 7, Measures for Monitoring Discharges, comprises 4 sub-chapters. Sub-chapter 7.1 provides a general introduction and gives an overview of the discharge control and environmental monitoring programme to be implemented. Sub-chapter 7.2 describes the UK legislation covering both radioactive and non-radioactive discharges and the associated monitoring principles. Sub-chapter 7.3 describes the approach to the monitoring of radioactive releases both to water and to atmosphere from the UK EPR™. It identifies the methods, including sampling arrangements, techniques and systems/devices used to measure and assess discharges. In particular, it specifies methods used to determine discharges of groups of radionuclides and substances that are subjected to a permit and provides information on the efficiency of abatement plant. Sub-chapter 7.4 describes the approach to the monitoring of chemical discharges both to water and to atmosphere from the UK EPR™. It describes the types of discharges expected, and identifies the methods used to measure and assess discharges. Download
Sub-Chapter 6.5 – Interim storage facilities and disposability for UK EPR™.pdf		20-06-2023	289.7 KB
Sub-chapter 6.5 discusses the UK EPR™ designs for interim storage facilities, for the radioactive Intermediate Level Waste (ILW) operational waste, and the spent fuel, produced during the UK EPR™ 60 years of operation. The need for plans to demonstrate when facilities will be developed and constructed is also addressed. Additionally, the current status of the discussions with the NDA, with respect to the disposability of UK EPR™ solid radioactive waste, and spent fuel arising during the operational period, and the discussions with LLW Repository Ltd with regard to Low Level Waste disposability, are described. This sub-chapter and supporting documents provide a basis for a potential UK EPR™ operator to develop radioactive waste management cases for both ILW and spent fuel. Download
Sub-Chapter 6.4 – Effluent and waste treatment systems design architecture.pdf	Pre-Construction Environmental Report (PCER)	20-06-2023	3.39 MB
Sub-chapter 6.4 describes the UK EPR™ effluent and waste treatment systems for liquid, gaseous and solid waste. The role of the effluent treatment systems, in normal operation, involves: collecting effluent produced in the unit and site facilities, which may come from draining, bleeding, venting or leaks from systems that are normally or accidentally contaminated; treating, if necessary, the effluents, i.e. reducing the level of contamination in order to meet regulatory discharge limits; and discharging effluents outside the site following monitoring and accounting of the levels of activity discharged under regulatory conditions. In some accident situations which could lead to significant transfer of contamination to the buildings adjacent to the reactor building, the effluent treatment systems operate to ensure any contamination is contained, in order to limit release of radioactivity to the environment. For each system, the safety functions, functional and design requirements, the design criteria, system design description, system parameters and operating conditions, safety assessment, and specific testing arrangements, are provided as appropriate. Download
Sub-Chapter 6.3 – Outputs for the operating installation.pdf	Pre-Construction Environmental Report (PCER)	20-06-2023	1.61 MB
Sub-chapter 6.3 presents the quantitative estimate of the effluents discharged and the waste produced by the operation of the UK EPR™ reactor. The estimates cover: spent fuel arisings, solid waste arisings, liquid and gaseous radioactive effluent discharges, and chemical effluent discharges, whether associated with liquid radioactive effluent or arising from operation of non-nuclear parts of the plant. The expected performance discharges are derived from recent operational feedback, taking credit for design features and expected quantifiable gains. Maximum additional annual discharges are provided, together with estimates of monthly discharges of gaseous and liquid radioactive waste. Download
Sub-Chapter 6.1 – Sources of radioactive materials.pdf	Pre-Construction Environmental Report (PCER)	20-06-2023	122.95 KB
Sub-chapter 6.1 provides details of the activity levels of the main primary system when the reactor is in normal operation (both steady-state power operation and shutdown transient). The concentrations of fission, corrosion and activation products provided are based on realistic operational data, therefore they may be used in a generic way as interface data for effluent discharges, radiological protection and assessment of realistic dose uptake, and radiological protection requirements. Source terms used for the design and sizing of the EPR™ structures, rooms, systems, shielding and the effluent treatment systems are also defined. Download
Sub-Chapter 6.0 – Safety Requirements.pdf	Pre-Construction Environmental Report (PCER)	20-06-2023	68.27 KB
Sub-chapter 6.0 describes the safety functions, and functional and design requirements, of the waste management systems, which include the liquid and gaseous waste processing systems, and the solid waste treatment system. Download
Chapter 5 - Design principles related to decommissioning.pdf	Pre-Construction Environmental Report (PCER)	20-06-2023	174.42 KB
Chapter 5, Design Principles related to decommissioning, comprises 2 sub-chapters. Sub-chapter 5.1 provides an overview of the dismantling process which results in the regulatory delicensing of the site, the approach to reduction of risk to the public during dismantling, the documentation required, and outlines the UK EPR™ design principles which ensure that both radioactive doses and radioactive waste are reduced to as low as reasonably practicable. The baseline principles and objectives that should be adopted during decommissioning are outlined, together with the need for records of information pertinent to decommissioning. Sub-chapter 5.2 describes how the principles and regulations have been followed at the early UK EPR™ design stage to ensure future decommissioning in a safe and environmentally acceptable way. It describes the measures adopted at the EPR™ design stage to facilitate decommissioning, such as minimisation of radioactive waste and contamination. An estimate of the volumes of low and intermediate level waste is also given, together with a discussion of the disposability thereof. Finally, the baseline decommissioning strategy currently envisaged is presented. Download
Chapter 4 - Aspects having a Bearing on the Environment during Construction Phase.pdf	Pre-Construction Environmental Report (PCER)	20-06-2023	489 KB
Chapter 4, Aspects having a Bearing on the Environment during Construction Phase, comprises 3 sub-chapters. Sub-chapter 4.1 provides a brief introduction. Sub chapter 4.2 outlines the activities that take place during the EPR™ construction phase, including site preparation activities, preliminary works, the EPR™ plant construction, and commissioning. Sub-chapter 4.3 focuses on the aspects of the construction phase that have a potential impact on the terrestrial and aquatic environments; i.e. the interface of the plant construction, erection and commissioning with the environment in terms of requirements for natural resources and outputs that might impact the existing environment. In particular water abstraction, discharge of contaminants and the non-radioactive waste strategy are highlighted. Download