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Name	Category	Date	Size
Sub-Chapter 5.2 - Integrity of the Reactor Coolant Pressure Boundary (RCPB).pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	296.15 KB
Sub-chapter 5.2 describes how the integrity of the reactor coolant pressure boundary is ensured. The design rules and material specifications applicable to the reactor coolant pressure boundary are summarised. A description of the requirements applied to High Integrity Components is given for 'non-breakable'; components based on specific requirements applied to the design, manufacture, inspection and in service surveillance. In addition, the design principles applied to non-breakable components are compared with the requirements conventionally applied to Incredibility of Failure Components in UK power reactors. The design criteria for the over-pressure protection system are given and an outline of the in-service inspection requirements is presented. Download
Sub-Chapter 5.1 - Description of the Reactor Coolant System.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	654.44 KB
Sub-chapter 5.1 describes the functional role of the reactor coolant system, together with the design assumptions, fluid characteristics and design description of the key components (reactor vessel, pressuriser, reactor coolant pumps and steam generators). System parameters are given for both normal operating conditions and standard shutdown states. The main control functions are outlined: reactor coolant system pressure control, pressuriser level control, reactor coolant system loop level control, steam generator level control, and reactor coolant pump standstill seal system actuation. Download
Sub-Chapter 5.0 - Safety Requirements.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	96.57 KB
Sub-chapter 5.0 describes the safety functional requirements and design criteria used in the functional design of the reactor coolant system and its auxiliary systems, together with a brief outline of testing requirements. Download
Sub-Chapter 4.5 - Functional design of reactivity control.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	91.84 KB
Sub-chapter 4.5 describes the safety functional requirements and design criteria used in the functional design of the reactivity control systems, including the control rod drive system, the chemical and volume control system, the extra boration system and the safety injection system. Download
Sub-Chapter 4.4 - Thermal and hydraulic design.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	794.52 KB
Sub-chapter 4.4 describes the safety functional requirements and design criteria used in the thermal hydraulic design of the reactor core. Details are provided of the various limiting physical phenomena, such as departure from nucleate boiling, and flow instability. The thermal hydraulic characteristics of the reactor core are given, together with a description of the transient analysis methodology, tools and design data. A description of the core instrumentation requirements is also provided. Download
Sub-Chapter 4.3 - Nuclear Design.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	718.93 KB
Sub-chapter 4.3 describes the safety functional requirements and design criteria used in the nuclear design of the fuel and reactivity control system. It provides an overall description of the core, together with a definition of the calculated power distributions, the fuel and moderator reactivity coefficients, the core control requirements and principles, and means by which these are achieved, the calculation of shutdown margins, the preliminary criticality design criteria and assumptions, and the residual heat characteristics. A brief review of the methods and tools used to determine neutron and gamma ray flux attenuation between the core and the pressure vessel is also given. Download
Sub-Chapter 4.2 - Fuel System Design.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	163.41 KB
Sub-chapter 4.2 lists the safety requirements to be met in the design of the fuel and control rod assemblies, and includes a design description and evaluation of both the fuel and control rod assemblies. Download
Sub-Chapter 4.1 - Summary description.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	154.18 KB
Sub-chapter 4.1 provides a summary description of the core, fuel and reactivity control, and presents the main parameters used in the core design, the assumptions considered at the present stage of the UK EPR™ design concerning the mechanical characteristics of the fuel assemblies, and the objectives of the nuclear and thermal-hydraulic design. Download
Appendix 4 - Computer codes used in Chapter 4.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	84.77 KB
Appendix 4 provides an outline description of the computer codes used in the analyses presented in Chapter 4. Download
Sub-Chapter 3.8 - Codes and standards used in the EPR design.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	464.66 KB
Sub-chapter 3.8 gives an overview of the codes and standards used in the EPR™ design. The set of codes and standards is part of the French regulatory regime, therefore a general description of the structure of French safety regulation is provided. This is followed by a description of the main content of the codes: the technical code for mechanical equipment (RCC-M), the technical code for critical defect size calculations for mechanical components (RSE-M Appendix 5.4), the technical code for electrical equipment (RCC-E), the EPR™ Technical Code for Civil Works (ETC-C), and the EPR™ Technical Code for Fire Protection (ETC-F), including comparisons with international practice e.g. ASME and IAEA standards. Download
Sub-Chapter 3.7 - Conventional Risks of Non-Nuclear Origin.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	125.54 KB
Sub-chapter 3.7 covers conventional risks of non-nuclear origin on the site, i.e. risks potentially induced by the presence of non-nuclear facilities and human activities on the site. The proposed methodology, outlined in this sub-chapter, aims to demonstrate that all potential 'conventional' risks have been identified and dealt with and that their consequences are acceptable for the environment, and especially for members of the public off-site. The methodology also considers the consequences of non-nuclear origin on safety-related installations located on the site. Download
Sub-Chapter 3.6 - Qualification of electrical and mechanical equipment for accident conditions.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	328.13 KB
Sub-chapter 3.6 outlines the qualification of equipment for accident conditions, including severe accidents. The purpose of qualification is to demonstrate that the equipment can fulfil its required function during accident conditions. The functions to be qualified (based on analyses of both functional requirements and requirements relating to post-accident operation) and their associated requirements are described. The design data required for qualification, primarily environmental conditions (pressure, temperature and irradiation) are described, together with the qualification methods, standards and practices used, and the arrangements made to maintain qualification during manufacturing and operation (qualification maintenance). Download
Sub-Chapter 3.5 - Safety Related Interfaces.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	129.91 KB
Sub-chapter 3.5 describes safety related interfaces in three areas: mechanical equipment and civil structures in the nuclear island; electrical equipment and civil engineering; and the interfaces between nuclear and non nuclear plant. In each area, the Interfaces, their functions and design, and the specific requirements for the systems and structures are given. Download
Sub-Chapter 3.4 - Mechanical systems and componentsz.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	5.63 MB
Sub-chapter 3.4 describes the safety requirements applied to the design of the mechanical systems and components. It defines the operating conditions upon which the equipment design is based; the nature of the loads to be considered for all the pressurised equipment, in particular the primary and secondary pressure system boundaries; the rules for combining the loads and the criteria to be used; and the analytical methods used. A structural analysis of the reactor coolant pressure boundary is presented, together with analysis of hydraulic loading on the main steam system. Analyses are presented demonstrating that the criteria relative to overpressure risks for the primary and secondary pressure boundaries are met. A discussion of vibration testing and analyses is included. The specific mechanical systems considered in detail here are: the control rod drive mechanism and the reactor pressure vessel upper core support structures and lower internals. Download
Sub-Chapter 3.3 - Design of Category 1 Civil Structures.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	1.64 MB
Sub-chapter 3.3 sets out the requirements applicable to the design of the safety-classified civil structures in the UK EPR™. The safety requirements have been established as follows: a review was carried out of the relevant structures, identifying the various components of the structures to which particular requirements would apply; the various load cases applicable to the structures were specified, covering both normal reactor operation and fault conditions (including internal and external hazards), to which the structures may be subjected; the load cases applicable to particular components of the civil structures, and the associated safety requirements, were identified. The safety requirements were then incorporated into the design of the civil structures and into the definition of their associated behavioural requirements. The C1 and C2 requirement levels, as defined in Sub-chapter 3.2, apply to the safety classified civil structures, which include: the steel lined inner containment, the containment penetrations, the concrete and steel structure internal to the reactor building, seismically classified buildings in the nuclear island, and the foundation raft. Download
Sub-Chapter 3.2 - Classification of structures, equipment and systems.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	717.68 KB
Sub-chapter 3.2 presents the classification approach adopted for the EPR™ design, the aim of which is to utilise a deterministic approach for ensuring that the plant is designed, manufactured, constructed commissioned and operated so that the appropriate level of reliability and integrity is achieved for all structures, systems and components (SSCs). The classification process involves the systematic assessment of the importance to nuclear safety of each SSC, its allocation to a Safety Feature Group (SFG) and Safety Feature (SF) and to a safety class on the basis of this safety significance. The safety class allocated to an SSC defines the design, testing and maintenance measures to be applied in its design, construction, commissioning, and operation. The link between the safety classification and the SSC design requirements is explained (Components, Structures); the different types of requirements are defined and an explanation is given of how they are applied. The methodology for utilising a Probabilistic Safety Assessment (PSA) approach for performing verification of the deterministically derived classification of SSCs is explained and supported by example applications of the UK classification approach. Download
Sub-Chapter 3.1 - General Safety Principles.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	462.88 KB
Sub-chapter 3.1 describes the safety approach implemented in the UK EPR™ plant design, which is based on the concept of defence in depth. It provides a summary of the main EPR™ design requirements and a description of the technical approach adopted to meet these requirements. It refers to other chapters in the PCSR in which the applicable safety requirements are set out in more detail. Although the sub chapter is concerned mainly with design principles adopted to meet requirements of the French Safety Authority, reference is also made to supplementary "UK EPR™ safety design objectives" that would be demonstrated for an EPR™ operating in the UK to address UK specific safety principles. Download
Appendix 3 - Computer codes used in Chapter 3.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	328.51 KB
Appendix 3 contains brief descriptions of the computer codes used in the analyses presented in Chapter 3, including the structural analysis of the main civil structures (Sub chapter 3.3) and the mechanical analysis of the reactor coolant pressure boundary (Sub chapter 3.4). Download
Sub-Chapter 2.2 - Site environmental characteristics.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	209.38 KB
Sub-chapter 2.2 presents the site data which need to be considered when assessing the environmental impacts of the UK EPR™ design (e.g. terrestrial and aquatic characteristics, habitats data). The sub chapter outlines the information and methodologies to be used for the baseline studies during the site specific phase. The sub chapter also includes a set of site parameters appropriate for the UK, i.e. representative of a range of potential coastal and estuarine locations, in order to carry out environmental impact studies for Generic Design Assessment (GDA). It will be necessary to further update this sub-chapter to include site specific details and to utilise available site-specific data. Download
Sub-Chapter 2.1 - Site Data used in the Safety Analyses.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	142.12 KB
Sub-chapter 2.1 presents a summary of the site data used in the safety analysis presented in the PCSR. The data are considered to be typical of UK coastal sites in England and Wales on which nuclear power stations have been sited. The data include: the external heat sink and the power supply (grid connections), the bounding site data used for the off-site consequence risk assessment and external hazards assessment, and the assumptions used in evaluation of the accidental radiological consequences of accidents. It will be necessary to further update this chapter to include site specific details and to utilise the available site-specific data. Download