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Name	Category	Date	Size
Sub-Chapter 7.1 - Design principles of the Instrumentation and Control systems.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	171.66 KB
Sub-Chapter 7.1 - Design principles of the Instrumentation and Control systems</H3>Sub-chapter 7.1 presents the design principles of the overall I&C system, including the safety, functional and design requirements; classification of the I&C systems and equipment; and design criteria for the I&C system architecture, including the concept of defence in depth and general priority rules. An outline of the management and quality procedures covering the design and development of the I&C systems is provided as well as a summary of Claims, Arguments and Evidence for I&C systems. Download
Sub-Chapter 6.8 - Main steam relief train system.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	206.96 KB
Sub-chapter 6.8 presents the safety and functional requirements, design criteria, system design description, system parameters and operating conditions, preliminary safety analysis, and testing, inspection and maintenance details, for the main steam relief train system. The main steam relief train system is part of the main secondary cooling system and is used for dumping heat from the steam generators into the atmosphere when the condenser is unavailable. Download
Sub-Chapter 6.7 - Extra Boration System.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	518.7 KB
Sub-chapter 6.7 presents the safety and functional requirements, design criteria, system design description, system parameters and operating conditions, preliminary safety analysis, and testing, inspection and maintenance details, for the extra boration system. The extra boration system is a safety system which ensures boration of the reactor coolant, under fault conditions, to enable the core to be brought to a controlled or safe shutdown state. Download
Sub-Chapter 6.6 - Emergency Feedwater System.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	293.44 KB
Sub-chapter 6.6 presents the safety and functional requirements, design criteria, system design description, operating parameters, preliminary safety analysis, and testing, inspection and maintenance details, for the emergency feed water system. The emergency feed water system is a safety system which, in the event that normal operational feed water systems become unavailable, supplies the necessary feed water to the steam generators. Download
Sub-Chapter 6.5 - In-Service Inspection Principles (excluding main primary and secondary systems).pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	121.7 KB
Sub-chapter 6.5 presents the principles covering in-service inspection on the nuclear island pressurised equipment, including pressurised accessories, safety accessories and the parts welded to the pressurised containments. In-service inspection is preventive maintenance, consisting of non-destructive examinations and checks on equipment, which is systematically scheduled and implemented during planned outages. Included here are the safety requirements, areas of applicability, and scope, nature and frequency of inspections. Download
Sub-Chapter 6.4 - Habitability of the Control Room.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	82.42 KB
Sub-chapter 6.4 covers the habitability of the main control room during all events that might result in a radioactive release. This includes all the equipment, supplies and procedures necessary to enable the operators to remain in the main control room and take actions required to operate the plant safely in normal conditions, and to maintain it in a safe condition following an accident. The safety requirements, design criteria, system design description and operating parameters are given. Download
Sub-Chapter 6.3 - Safety Injection System.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	1.4 MB
Sub-chapter 6.3 provides a description of the safety injection/residual heat removal system and the in-containment refuelling water storage tank, including the safety and functional requirements; system description; system parameters and operating conditions; design criteria and assumptions; preliminary safety evaluation; testing, inspection and maintenance details. Download
Sub-Chapter 6.2 - Containment Systems.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	1.95 MB
Sub-chapter 6.2 provides a description of the containment systems and components, including as appropriate: safety and functional requirements; system description; relevant operating conditions; design criteria to be applied; materials and material properties; design details and calculations; preliminary safety analysis; and testing, inspection and maintenance details. The systems covered include: the annulus ventilation system, containment isolation system, combustible gas control system, leak rate control and testing system, core melt stabilisation system and containment heat removal system. Download
Sub-Chapter 6.1 – Materials.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	80.32 KB
Sub-chapter 6.1 defines the standard requirements for metallic and non-metallic materials used for the equipment in the nuclear island of the EPR. Download
Appendix 6 - MER Calculations - BDR Results.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	377.44 KB
Appendix 6 contains the sections from the generic EPR™ Basic Design Report 99 which describe calculations of mass and energy release into the containment which have not been specifically analysed for the UK EPR™ Pre-Construction Safety Report. The cases reported are: rupture of the pressuriser surge line; double-ended guillotine break at the cold leg of main coolant line; and double-ended guillotine break of a main steam line inside the containment building. Download
Sub-Chapter 5.5 - Reactor Chemistry.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	743.38 KB
Sub-chapter 5.5 provides a description of the primary and secondary side chemistry, including the chemistry of auxiliary systems. The choice of materials for primary and secondary systems is a key parameter to ensure the safe operation of the unit. Taking this into account, the chemistry is optimised to ensure the integrity of materials and to reduce radiation fields. The main chemistry parameters are described and justified in this chapter, including the design optimisation which provides the means to achieve the objectives of nuclear safety, radiation protection, material and equipment integrity, minimisation of environmental impact, hazard protection (explosion risk) and operational performance. Download
Sub-Chapter 5.4 - Components and Systems Sizing.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	2.22 MB
Sub-chapter 5.4 provides a description of the main reactor coolant systems and components, including as appropriate: the relevant operating conditions and interfaces; the design criteria to be applied; materials and material properties; design details and calculations; safety evaluation to demonstrate that primary components and piping meet High Integrity Component requirements, including assessment of mechanical integrity in accident conditions, the qualified manufacturing inspections proposed as well as fracture toughness proposals. The systems and components covered include: the reactor coolant pumps, the steam generators, the reactor coolant piping, the pressuriser and pressuriser relief line, valves associated with the reactor coolant pressure boundary, pressuriser pressure safety relief valves and severe accident depressurisation valves, and the primary component supports. Download
Sub-Chapter 5.3 - Reactor Vessel.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	839.83 KB
Sub-chapter 5.3 describes the reactor pressure vessel, including the design operating conditions, design requirements, materials used, and applicable mechanical design rules. A safety evaluation is provided to demonstrate RPV meets High Integrity Component requirements, including a description of the fracture mechanics analyses performed to assess the margins to fast fracture, qualified manufacturing inspections and fracture toughness proposed for RPV. Materials ageing mechanisms and materials irradiation monitoring are described. Download
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