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Name	Category	Date	Size
Sub-Chapter 14.5 - Analyses of the PCC-4 events.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	9.02 MB
Sub-chapter 14.5 describes the analysis of the PCC-4 events listed in Sub chapter 14.0 (i.e. design basis accidents, or events where the estimated frequency of occurrence is between 1 in 10,000 and 1 in a million reactor years). For each transient analysed, a description of the typical or assumed sequence of events is given together with identification of potential causes of the transient; any transient specific methods and assumptions are defined, as are any impact on the design of the claimed safety systems. Download
Sub-Chapter 14.3 - Analyses of PCC-2 events.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	1.85 MB
Sub-chapter 14.3 describes the analysis of the PCC-2 events listed in Sub chapter 14.0 (i.e. design basis transients, events where the estimated frequency of occurrence is greater than 1 in a 100 reactor years). For each transient analysed, a description of the typical or assumed sequence of events is given together with identification of potential causes of the transient; any transient specific methods and assumptions are defined, as are any impact on the design of the claimed safety systems. Download
Sub-Chapter 14.4 - Analyses of the PCC-3 events.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	2.44 MB
Sub-chapter 14.4 describes the analysis of the PCC-3 events listed in Sub chapter 14.0 (i.e. design basis incidents, or events where the estimated frequency of occurrence is between 1 in 100 and 1 in 10,000 reactor years). For each transient analysed, a description of the typical or assumed sequence of events is given together with identification of potential causes of the transient; any transient specific methods and assumptions are defined, as are any impact on the design of the claimed safety systems. Download
Sub-Chapter 14.2 - Analysis of the Passive Single Failure.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	1.72 MB
Sub-chapter 14.2 presents the methodology and analysis of the consequences of passive single failures at the time of the initiating event for design basis (PCC-2 to PCC-4) events. The UK EPR™ is designed in compliance with the single failure criterion, which includes either an active single failure within the first 24 hours after the occurrence of an initiating event or a passive single failure at 24 hours after the event occurrence. This criterion is part of the assumptions made for the design basis fault studies of PCSR Sub-chapters 14.3 to 14.5. From a UK perspective, there is a need to review each PCC-2 to PCC-4 event, and to demonstrate that there are no passive single failures within 24 hours which could prevent the successful operation of the safety function that is provided to protect against the fault. The overall analysis shows that the UK EPR™ design is robust with respect to passive single failures. Download
Sub-Chapter 14.1 - Plant Characteristics taken into account in the Accident Analyses.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	464.16 KB
Sub-chapter 14.1 describes the generic plant characteristics that are applied to the accident analyses. Characteristics which are specific to a particular accident analysis are specified within the section describing that accident analysis. The plant characteristics assumed in the accident analyses cover: plant geometrical data, plant initial conditions, reactivity coefficients, residual (decay) heat, I&C signals related to reactor trip and safety systems operation, and safety system characteristics. The approach used in the accident analysis with regard to Departure from Nucleate Boiling (DNB) is also defined in this sub-chapter. Download
Sub-Chapter 14.0 - Assumptions and Requirements for the PCC Accident Analyses.pdf	Pre-Construction Safety Report (PCSR)	20-06-2023	226.24 KB
Sub-chapter 14.0 presents the assumptions and requirements for the Plant Condition Category (PCC) accident analyses. The standard reactor states, covering full power operation to cold shutdown, are defined, together with a list of the PCCs to be assessed. A set of 'PCC accident analysis rules'; are defined, which are used to demonstrate that the safety systems are designed in an appropriate manner. The rules include acceptance criteria, and the application of the single failure criterion. Download
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