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Name	Category	Date	Size
Sub-Chapter 8.1 - External Power Supply.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	99.72 KB
Sub-chapter 8.1 describes the role and main elements of the external power supply for the nuclear island: the main and auxiliary connections, and transformers, including their operating role and design criteria, and system description. Download
Sub-Chapter 7.7 - IandC Tools Development Process and Substantiation.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	384.68 KB
Sub-chapter 7.7 provides information on the I&C procedures and tools used for the design of the three I&C platforms: the Teleperm XS platform for the protection system, the reactor control surveillance and limitation system, and the severe accident I&C; the SPPA-T2000 platform for the process information and control system, process automation system safety automation system; and the RRC-B safety automation system and the UNICORN platform for the non computerised safety system. For each platform, details are provided of: the reliability, availability and functional requirements; the software and hardware programming design and configuration; system integration, installation, and commissioning; verification and validation; and an overview of arrangements for operation, maintenance and modifications. Details are also given of the substantiation approach for software based systems using the Teleperm XS, SPPA-T2000 and UNICORN platforms and for the SMART devices and programmable complex electronic component, including production excellence activities and confidence building. Download
Sub-Chapter 7.6 – Instrumentation.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	459.52 KB
Sub-chapter 7.6 describes the instrumentation used in the UK EPR™. It covers: conventional process instrumentation; accident and severe accident instrumentation; the process instrumentation pre-processing system; in core and ex core instrumentation; rod position measurement; reactor pressure vessel water level measurement; loose parts monitoring and vibration monitoring; radiation monitoring; and boron instrumentation. The overall safety, functional and design requirements are given, and the description of each system includes where appropriate: measurement principles; system interfaces: design rules and structure; and installation, calibration, maintenance and testing details. Download
Sub-Chapter 7.5 - Class 3 Instrumentation and Control systems.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	385.52 KB
Sub-chapter 7.5 describes the RRC-B safety automation system, the process information and control system, the process automation system, and the severe accident I&C system. For each system, the safety and functional requirements; system description; design criteria; architecture, technology, and power supply, and testing, and maintenance details are provided. Download
Sub-Chapter 7.4 - Class 2 Instrumentation and Control systems.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	487.27 KB
Sub-chapter 7.4 describes the safety automation system, the reactor control surveillance and limitation system, and the non-computerised safety system. For each system, the safety and functional requirements; system description; design criteria; architecture, technology, and power supply, and testing, and maintenance details are provided. Download
Sub-Chapter 7.3 - Class 1 Instrumentation and Control systems.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	999.33 KB
Sub-chapter 7.3 describes the protection system and the safety information and control system. For each system, the safety and functional requirements; system description; design criteria; architecture, technology, and power supply, and testing, and maintenance details are provided. These class 1 systems manage category A I&C functions and are required to attain a controlled state after a fault, or failure during normal power plant operation that would lead to a fault. Download
Sub-Chapter 7.2 - General architecture of the Instrumentation and Control systems.pdf		20-06-2023	643.26 KB
Sub-chapter 7.2 describes the general architecture of the overall I&C system, including the interfaces between the various system levels and operating conditions and explains how the I&C architecture fulfils the design requirements such as reliability, independence and diversity. The layout of the I&C equipment in different rooms (mainly in the safeguard and electrical buildings) is discussed. The qualification process and principles are defined, in order to demonstrate that the various instrumentation & control components and systems are capable of responding to design requirements for safety performance. Download
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