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Name	Category	Date	Size
Appendix 14C - Analysis of single failure for main steam line break.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	1.67 MB
Appendix 14C contains an analysis of a main steam line break during power operation with a break size greater than the area equivalent to a diameter of 50 mm (20 cm²), which is classified as a PCC-4 event. The objective of this analysis is to determine the most conservative single failure for this event in terms of departure from nucleate boiling. This single failure is used in the PCSR analysis of a main steam line break during power operation performed in section 2.1 of Sub-chapter 14.5. Download
Appendix 14B - 4900 MWe safety analyses used in Chapter 14.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	4.65 MB
Appendix 14B contains sections from the generic EPR™ Basic Design Report 99 corresponding to accident analyses which are necessary to support some sections of the Pre-Construction Safety Report, but where all or some of the transient has not been specifically analysed for the UK EPR™. The cases reported include: small, intermediate and large break loss of coolant accidents from power operation; inadvertent closure of all/one main steam isolation valves; loss of non-emergency AC power to the plant auxiliaries; loss of condenser vacuum; full or partial loss of forced reactor coolant flow; uncontrolled rod cluster control assembly bank withdrawal from power operation; excessive increase in secondary steam flow, or steam system piping failure; and feedwater system pipe break; and steam generator tube rupture (1 or 2 tubes). Download
Appendix 14A - Computer codes used in Chapter 14.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	617.82 KB
Appendix 14A contains brief descriptions of the computer codes used within the framework of the accident analysis of plant condition category events (Chapter 14), risk reduction analysis sequences (Sub-chapter 16.1) and overpressure protection analyses (Sub chapter 3.4). The computer codes used for each event are shown, including the use of coupled computer codes. Also included here are computer codes used in transient calculations taken from the generic EPR™ Basic Design Report 99, which are presented in Appendix 14B. Download
Sub-Chapter 13.2 - Internal Hazards Protection.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	755.61 KB
Sub-chapter 13.2 presents the requirements, the design basis and the design verification methods for the internal hazards taken into account in the UK EPR™ design: pipework leaks and breaks (including breaks of both high energy and moderate energy pipework); failure of tanks, pumps and valves; internal missiles; dropped loads; internal explosions; fire; and internal flooding. Internal hazard protection is provided to ensure that the safety related functions required to meet the safety objectives discussed in Chapter 3 of this PCSR are not unacceptably affected as the result of a hazard. In addition the methodology and principles for development of the Hazard Fault Schedule are presented with reference to an example for internal flooding. Download
Sub-Chapter 13.1 - External Hazards Protection.pdf		20-06-2023	863.87 KB
Sub-chapter 13.1 presents the requirements, the design basis and the design verification method for the external hazards taken into account in the UK EPR™ design: earthquake, aircraft crash, hazards associated with the industrial environment and transport routes (external explosion, off-site fire, movement of toxic or corrosive gases), external flooding, extreme weather conditions (snow and wind, wind generated missiles, low ambient temperatures, frazil and ice, high ambient temperatures, drought), and lightning and electromagnetic disturbances. The completeness of this list will need to be confirmed for each specific site, further site-specific assessments will be provided at that stage. For the external flooding hazard the design is fully site-dependent; in this case, and in the framework of the generic design assessment, the presentation is reduced to general principles. In addition the methodology and principles for development of the Hazard Fault Schedule are presented with reference to an example for external explosion. Download
Sub-Chapter 12.5 - Post accident accessibility.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	97.99 KB
Sub-chapter 12.5 defines the systems and components to which access is required in long term post-accident situations, and specifies the associated accessibility conditions in terms of individual dose. Post-accident accessibility is defined for the systems used to maintain long-term cooling of the plant (over a year) and long term cooling of the fuel pool. The statutory requirements covering intervention personnel qualified to access rooms and operate systems are also outlined. This chapter only covers radiation protection issues; information on emergency arrangements is given in Sub-chapter 18.2 of the PCSR. Download
Sub-Chapter 12.4 - Dose uptake optimisation.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	281.96 KB
Sub-chapter 12.4 describes the design measures adopted in the UK EPR™ to optimise operator dose in normal plant operation, and gives predictions for the level of collective doses expected to be achieved. The dose received by individual workers is also considered with reference to the dose target for an individual worker that has been adopted as a safety design objective for the UK EPR™. Download
Sub-Chapter 12.3 - Radiation protection measures.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	591.07 KB
Sub-chapter 12.3 provides details of the radiation protection measures implemented on the UK EPR™ including: radiation protection classification and zoning, and rules for the design (and installation) of equipment and rooms; shielding provisions, including materials and measures for the main buildings; design of the ventilation systems to minimise worker exposure to any contamination; monitoring, both of dose rates in rooms and of workers for potential contamination; and the plant radiation monitoring system which monitors the integrity of the containment barriers and initiates the actions needed to control the activity levels, including system functional flow diagrams.< Download
Sub-Chapter 12.2 - Definition of radioactive sources in the primary circuit.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	140.97 KB
Sub-chapter 12.2 provides details of the specific activities of the fission and corrosion products in the primary coolant, both in normal operation and shutdown conditions. Additionally, specific concentrations and deposited activity of important nuclides in the main loops are identified, based on measurements taken in French power stations. The system and chemistry measures, implemented on the UK EPR™ to control and optimise the primary circuit inventory levels, are also outlined. Download
Sub-Chapter 12.1 - Radiation Protection approach.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	88.58 KB
Sub-chapter 12.1 outlines the basic principles applying to radiation protection, as specified by the International Commission on Radiological Protection (ICRP) and the radiation protection strategy implemented on the UK EPR™, including optimisation of the plant radioactive inventory and shielding provisions, and compliance with individual and collective dose limits. Download
Sub-Chapter 12.0 - Radiation Protection Requirements.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	102.78 KB
Sub-chapter 12.0 aims to define the regulatory framework relating to radiation protection on which the design of the UK EPR™ is based. Legislative requirements, taken from international, European and national regulations, are given together with an overview of the regulatory bodies and the main radiation protection requirements, including the definition of radiation protection zoning and cleanliness / waste zoning. Download
Sub-Chapter 11.5 - Interim storage facilities and disposability for UK EPR.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	285.14 KB
Sub-chapter 11.5 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 11.4 - Effluent and waste treatment systems design architecture.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	3.36 MB
Sub-chapter 11.4 describes the 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 11.3 - Outputs for the operating installation.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	2.7 MB
Sub-chapter 11.3 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 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