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Name	Category	Date	Size
Sub-Chapter 11.2 - Details of the Effluent Management Process.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	378.09 KB
Sub-chapter 11.2 details the effluent management process (collection, processing, storage and disposal) for liquid and gaseous radioactive discharges and solid radioactive waste. It identifies the sources, nature, treatment and storage of liquid and gaseous effluent discharges. It discusses the chemicals associated with liquid effluent that could be discharged into the marine environment, including the purpose of each substance, the main circuits involved, the path from injection to discharge, and the proposed maximum amounts discharged. Information is also given regarding the UK EPR™ radioactive waste and spent nuclear fuel strategy, including waste treatment and interim storage and disposability. The strategy takes into account the UK EPR™ solid radioactive waste and spent fuel characteristics, and addresses the government and NDA policies for the assessment of disposability of radioactive waste. It includes the description of processes and interim storage facilities for managing the waste and spent nuclear fuel. Download
Sub-Chapter 11.1 - Sources of radioactive materials.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	162.86 KB
Sub-chapter 11.1 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 11.0 - Safety Requirements.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	67.39 KB
Sub-chapter 11.0 describes the safety functions, and functional and design requirements, of the radioactive waste management systems, which include the liquid and gaseous waste processing systems, and the solid waste treatment system. Download
Sub-Chapter 10.6 - Main Feedwater System.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	203.39 KB
Sub-chapter 10.6 describes the safety, functional and design requirements, the design criteria, system design description, system parameters and operating conditions, preliminary safety assessment, and specific testing arrangements for the main feedwater system. During normal power operation, the main feedwater system is used to provide the required water flow rate to the steam generators, and in certain conditions, to help isolate the steam generators. Download
Sub-Chapter 10.5 - Integrity of the main steam lines inside and outside the containment.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	129.26 KB
Sub-chapter 10.5 describes how the High Integrity Components (HIC) principle is applied to the main steam lines inside and outside the reactor building containment. The main steam lines from the steam generators up to the first terminal fixed points downstream of the Main Steam Isolation Valves (MSIV) and including the MSIV are HIC. The HIC requirements are set out in this sub-chapter together with further requirements related to levels of defence-in-depth. Download
Sub-Chapter 10.4 - Other Features of Steam and Power Conversion Systems.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	388.93 KB
Sub-chapter 10.4 describes the turbine bypass system, which discharges the steam flow to the condenser when the turbine is unavailable; the main feedwater pump, the start-up and shutdown feedwater system, the cooling water system (for a coastal site) and the steam generator blowdown system which is used to maintain the necessary quality of the water/steam cycle in conjunction with the nuclear sampling system. Information relating to the condenser and condensate extraction systems, the remainder of the feedwater plant, and turbine gland system, is operator and/or site specific, and is not included here. Download
Sub-Chapter 10.3 - Main Steam System (safety classified part).pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	756.11 KB
Sub-chapter 10.3 describes the safety, functional and design requirements, the design criteria, system design description, system parameters and operating conditions, instrumentation and control details, safety assessment, details of testing, and maintenance requirements for the main steam system. The main steam supply system is designed to ensure, a supply of steam to the turbine during normal power operation, and, in certain conditions, to protect the steam generators against overpressure. The main steam lines from the steam generators up to the first terminal fixed points downstream of the Main Steam Isolation Valves (MSIV) and including the MSIV are High Integrity Components (HIC) and details of the fast fracture analysis, manufacturing inspections and fracture toughness requirements are described. Download
Sub-Chapter 10.2 - Turbo-generator Set.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	82.77 KB
Information relating to the turbo-generator is both site and operator specific, and is therefore not included in the PCSR for generic design assessment. Download
Sub-Chapter 10.1 - General Description.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	206.84 KB
Sub-chapter 10.1 provides a general design description of the secondary cooling system, which converts thermal energy produced by the nuclear steam supply system into electrical power. Download
Sub-Chapter 9.5 - Other Supporting Systems.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	976.38 KB
Sub-chapter 9.5 describes the following systems: the fire protection systems and equipment, including the active methods of fire control, detection and extinguishing, and the design principles for the door monitoring system; the main and ultimate back-up/emergency diesel generators; the compressed air systems, including the compressed air production system and the instrument and service air distribution systems; the plant communication systems, including the alarm systems, paging and internal and external telephone communication systems; lighting systems including both normal and emergency lighting arrangements; gas distribution and storage systems, for distribution of nitrogen, oxygen, hydrogen and carbon dioxide. For each system, the safety and functional requirements, design criteria, system design description, system parameters and operating conditions, preliminary safety analysis, and testing, inspection and maintenance details, are provided. Download
Sub-Chapter 9.4 - Heating, Ventilation and Air-Conditioning Systems.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	3.31 MB
Sub-chapter 9.4 describes the main ventilation and cooling systems. Those systems which contribute to reducing radioactive discharges comprise: ventilation of the nuclear auxiliary building, the fuel building, and the waste treatment building; purging of the reactor building; and ventilation of the controlled areas of the safeguard buildings, the operational service centre and the access building. The systems that maintain the conditions required for the safety and habitability of the main control room include: air-conditioning of the main control room; ventilation of the containment, diesel buildings and the pumping station; and ventilation of the non-controlled area in the safeguard buildings. Also described here are the chilled water systems which produce and distribute chilled water to the ventilation systems. For each system, the safety and functional requirements, design criteria, system design description, system parameters and operating conditions, preliminary safety analysis, and testing, inspection and maintenance details, are provided. Download
Sub-Chapter 9.3 - Primary System Auxiliaries.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	1.2 MB
Sub-chapter 9.3 describes the following systems: the nuclear island physical and chemical sampling system, which comprises three separate sampling systems, one for the primary system, a second for the secondary side of the steam generators and a third system for the treatment systems located in the effluent treatment building; the chemical and volume control system and the reactor boron and water makeup system, both of which regulate the boron concentration in the reactor coolant; and the coolant storage and treatment system, which includes the coolant storage and supply, treatment, purification and degasification systems. For each system, the safety and functional requirements, design criteria, system design description, system parameters and operating conditions, preliminary safety analysis, and testing, inspection and maintenance details, are provided. Download
Sub-Chapter 9.2 - Water Systems.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	1022.68 KB
Sub-chapter 9.2 describes the water systems: the essential service water system, the component cooling water system, the demineralised water systems (for production, storage and distribution of demineralised water), the service water filtering system, the potable water system, and the ultimate cooling water system. For each system, the safety and functional requirements, design criteria, system description, system parameters and operating conditions, preliminary safety analysis, and testing, inspection and maintenance details, are provided. Download
Sub-Chapter 9.1 - Fuel Handling and Storage.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	2.14 MB
Sub-chapter 9.1 describes the fuel handling and storage systems: the new fuel dry storage rack, the underwater fuel storage rack, the spent fuel cooling and purification system, fuel and other handling systems, and the liners for the fuel handling and storage pools. For each system, the safety and functional requirements, design criteria, system design description, system parameters and operating conditions, preliminary safety analysis, and testing, inspection and maintenance details, are provided. Download
Sub-Chapter 8.6 - Prevention and protection against common cause failure.pdf		20-06-2023	199.04 KB
Sub-chapter 8.6 summarises the main features of the prevention and protection against Common Cause Failure (CCF). CCFs are failures on demand or during a system mission period that could affect and make several pieces of equipment or components within the same system or with the same function simultaneously unavailable, where the failures are due to the same cause. The sub-chapter sets out the arguments and evidence for the safety requirements which have been specified for CCF, including component failure, both external and internal hazards, and human error within the design of the electrical systems. The availability of an internal network and associated equipment is considered, including protection against over-voltage and high frequency range phenomena. Download
Sub-Chapter 8.5 – Installation.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	72.05 KB
Sub-chapter 8.5 summarises the main features of the civil installations in the nuclear island, conventional island and the balance of plant where the electrical distribution and instrumentation and control systems are installed, which contribute to the safety functionality and availability of the systems. Download
Sub-Chapter 8.4 - Specific Design Principles.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	146.95 KB
Sub-chapter 8.4 provides a general description of cabling design principles, including the requirements for separation between cableways and the various cable categories, and a description of the design principles applied to cable routing. The earthing and lightning protection systems, whose main function is to limit the risks of overvoltage on the electrical systems, and other electrical protection measures, are also described here. Download
Sub-Chapter 8.3 - Nuclear Island Power Supply.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	606.68 KB
Sub-chapter 8.3 describes power distribution systems and the emergency power supplies for the nuclear island. In the event of loss of off-site power, 10 kV main diesel generators restore the power supply or, in the event of loss of both off-site supplies and on-site normal emergency supplies, the 690 V ultimate emergency diesel generators restore power to two of the four divisions. The overall safety, functional and design requirements, and system architecture, are described. For each of the systems, the operating role, design criteria, system parameters and operating requirements are given. Details are also given of the safety requirements specified for equipment qualification. Download
Sub-Chapter 8.2 - Power Supply to the Conventional Island and Balance of Plant.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	99.98 KB
Sub-chapter 8.2 describes the role and main elements of the power supply to the conventional island and balance of plant, both the emergency and non-emergency power supplies. Download
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