UK EPR - Generic Design Assessment (GDA)
SSER
Introduction to the Safety, Security and Environmental Report (SSER)
The Safety, Security and Environmental Report (SSER) for the proposed UK EPR™ design addresses the requirements of the ONR and EA Generic Design Assessment process. It provides design, safety and environmental information wich has supported the detailed assessment of the UK EPR™ design against UK safety and environmental standards. The SSER, on this website, comprises two main documents: the Pre-Construction Safety Report (PCSR) and the Pre-Construction Environmental Report (PCER)`. A number of supporting documents, provide further information in a number of areas.
Other UK EPR™ GDA Submissions
Design Reference Configuration defines the main technical requirements for the UK EPR™ design and the reference design configuration supporting the GDA submission, including design changes introduced during the GDA process. It also lists items which are outside the scope of GDA.
The UK EPR™ GDA Submission Master List defines the documents underwriting the UK EPR™ design and which are included in the scope of the Generic Design Assessment submission.
PCSR
The Pre-Construction Safety Report (PCSR)
The Pre-Construction Safety Report (PCSR) presents a detailed description of the architecture of the UK EPR™ systems and components, their safety functions and reliability and availability requirements, and an explanation of the codes and standards that have been used in the design. The PCSR aims to demonstrate that sufficient analysis and engineering substantiation has been performed to give high confidence that the UK EPR™ design meets its declared safety objectives. The PCSR has undergone detailed assessment by ONR.
Contents
The Pre-Construction Safety Report is divided into 21 chapters. A full list of the chapters and associated sub-chapters is available in the PCSR Table of Contents.
Chapter 1 - Introduction and General Description
- Sub-Chapter 1.1 - Introduction
- Sub-Chapter 1.2 - General Description of the Unit
- Sub-Chapter 1.3 - Comparison with reactors of similar
- Sub-Chapter 1.4 - Compliance with regulations
- Sub-Chapter 1.5 - Safety assessment and international practice
Chapter 2 - Genric Site Envelope and Data
- Sub-Chapter 2.1 - Site Data used in the Safety Analyses
- Sub-Chapter 2.2 - Site environmental characteristics
Chapter 3 - General Design and Safety Aspects
- Sub-Chapter 3.1 - General Safety Principles
- Sub-Chapter 3.2 - Classification of structures, equipment and systems
- Sub-Chapter 3.3 - Design of Category 1 Civil Structures
- Sub-Chapter 3.4 - Mechanical systems and components
- Sub-Chapter 3.5 - Safety Related Interfaces
- Sub-Chapter 3.6 - Qualification of electrical and mechanical equipment for accident conditions
- Sub-Chapter 3.7 - Conventional Risks of Non-Nuclear Origin
- Sub-Chapter 3.8 - Codes and standards used in the EPR design
- Appendix 3 - Computer codes used in Chapter 3
Chapter 4 Reactor and Core Design
- Sub-Chapter 4.1 - Summary description
- Sub-Chapter 4.2 - Fuel System Design
- Sub-Chapter 4.3 - Nuclear Design
- Sub-Chapter 4.4 - Thermal and hydraulic design
- Sub-Chapter 4.5 - Functional design of reactivity control
- Appendix 4 - Computer codes used in Chapter 4
Chapter 5 - Reactor Coolant System and Associated Systems
- Sub-Chapter 5.0 - Safety Requirements
- Sub-Chapter 5.1 - Description of the Reactor Coolant System
- Sub-Chapter 5.2 - Integrity of the Reactor Coolant Pressure Boundary (RCPB)
- Sub-Chapter 5.3 - Reactor Vessel
- Sub-Chapter 5.4 - Components and Systems Sizing
- Sub-Chapter 5.5 - Reactor Chemistry
Chapter 6 - Containment and Safeguard Systems
- Sub-Chapter 6.1 – Materials
- Sub-Chapter 6.2 - Containment Systems
- Sub-Chapter 6.3 - Safety Injection System
- Sub-Chapter 6.4 - Habitability of the Control Room
- Sub-Chapter 6.5 - In-Service Inspection Principles (excluding main primary and secondary systems)
- Sub-Chapter 6.6 - Emergency Feedwater System
- Sub-Chapter 6.7 - Extra Boration System
- Sub-Chapter 6.8 - Main steam relief train system
- Appendix 6 - MER Calculations - BDR Results
Chapter 7 - Instrumentation and Control
- Sub-Chapter 7.1 - Design principles of the Instrumentation and Control systems
- Sub-Chapter 7.2 - General architecture of the Instrumentation and Control systems
- Sub-Chapter 7.3 - Class 1 Instrumentation and Control systems
- Sub-Chapter 7.4 - Class 2 Instrumentation and Control systems
- Sub-Chapter 7.5 - Class 3 Instrumentation and Control systems
- Sub-Chapter 7.6 – Instrumentation
- Sub-Chapter 7.7 - IandC Tools Development Process and Substantiation
Chapter 8 - Electrical Supply and Layout
- Sub-Chapter 8.1 - External Power Supply
- Sub-Chapter 8.2 - Power Supply to the Conventional Island and Balance of Plant
- Sub-Chapter 8.3 - Nuclear Island Power Supply
- Sub-Chapter 8.4 - Specific Design Principles
- Sub-Chapter 8.5 – Installation
- Sub-Chapter 8.6 - Prevention and protection against common cause failure
Chapter 9 - Auxiliary Systems
- Sub-Chapter 9.1 - Fuel Handling and Storage
- Sub-Chapter 9.2 - Water Systems
- Sub-Chapter 9.3 - Primary System Auxiliaries
- Sub-Chapter 9.4 - Heating, Ventilation and Air-Conditioning Systems
- Sub-Chapter 9.5 - Other Supporting Systems
Chapter 10 - Main Steam and Feedwater Lines
- Sub-Chapter 10.1 - General Description
- Sub-Chapter 10.2 - Turbo-generator Set
- Sub-Chapter 10.3 - Main Steam System (safety classified part)
- Sub-Chapter 10.4 - Other Features of Steam and Power Conversion Systems
- Sub-Chapter 10.5 - Integrity of the main steam lines inside and outside the containment
- Sub-Chapter 10.6 - Main Feedwater System
Chapter 11 - Discharges and Waste - Chemical and Radiological
- Sub-Chapter 11.0 - Safety Requirements
- Sub-Chapter 11.1 - Sources of radioactive materials
- Sub-Chapter 11.2 - Details of the Effluent Management Process
- Sub-Chapter 11.3 - Outputs for the operating installation
- Sub-Chapter 11.4 - Effluent and waste treatment systems design architecture
- Sub-Chapter 11.5 - Interim storage facilities and disposability for UK EPR
Chapter 12 - Radiation Protection
- Sub-Chapter 12.0 - Radiation Protection Requirements
- Sub-Chapter 12.1 - Radiation Protection approach
- Sub-Chapter 12.2 - Definition of radioactive sources in the primary circuit
- Sub-Chapter 12.3 - Radiation protection measures
- Sub-Chapter 12.4 - Dose uptake optimisation
- Sub-Chapter 12.5 - Post accident accessibility
Chapter 13 - Hazards Protection
Chapter 14 - Design Basis Analysis
- Sub-Chapter 14.0 - Assumptions and Requirements for the PCC Accident Analyses
- Sub-Chapter 14.1 - Plant Characteristics taken into account in the Accident Analyses
- Sub-Chapter 14.2 - Analysis of the Passive Single Failure
- Sub-Chapter 14.3 - Analyses of PCC-2 events
- Sub-Chapter 14.4 - Analyses of the PCC-3 events
- Sub-Chapter 14.5 - Analyses of the PCC-4 events
- Sub-Chapter 14.6 - Radiological consequences of design basis accidents
- Sub-Chapter 14.7 - Fault and Protection Schedule
- Appendix 14A - Computer codes used in Chapter 14
- Appendix 14B - 4900 MWe safety analyses used in Chapter 14
- Appendix 14C - Analysis of single failure for main steam line break
Chapter 15 - Probabilistic Safety Analysis
- Sub-Chapter 15.0 - Safety requirements and PSA objectives
- Sub-Chapter 15.1 - Level 1 PSA
- Sub-Chapter 15.2 - PSA for internal and external hazards
- Sub-Chapter 15.3 - PSA of accidents in the spent fuel pool
- Sub-Chapter 15.4 - Level 2 PSA
- Sub-Chapter 15.5 - Level 3 - PSA Assessment of off-site risk due to postulated accidents
- Sub-Chapter 15.6 - Seismic Margin Assessment
- Sub-Chapter 15.7 - PSA Discussion and Conclusions
Chapter 16 - Risk Reduction and Severe Accident Analyses
- Sub-Chapter 16.1 - Risk Reduction Analysis (RRC-A)
- Sub-Chapter 16.2 - Severe Accident Analysis (RRC-B)
- Sub-Chapter 16.3 - Practically eliminated situations
- Sub-Chapter 16.4 - Specific Studies
- Sub-Chapter 16.5 - Adequacy of the UK EPR™ design regarding functional diversity
- Sub-Chapter 16.6 – Analysis of Extreme Beyond Design Basis Events Carried Out in Response to Fukushima
- Appendix 16A - Computer codes used in Chapter 16
- Appendix 16B - 4900 MW safety analyses used in Chapter 16
Chapter 17 - Compliance with ALARP Principle
- Sub-Chapter 17.1 - Explanation of ALARP Requirement
- Sub-Chapter 17.2 - Demonstration of Relevant Good Practice in EPR Design
- Sub-Chapter 17.3 - EPR Design Optioneering
- Sub-Chapter 17.4 - Review of PSA Results: Comparison with Numerical Risk Targets
- Sub-Chapter 17.5 - Review of Possible Design Modifications to Confirm Design meets ALARP Principle
- Sub-Chapter 17.6 - Conclusions of EPR ALARP Assessment
Chapter 18 - Human Factors Operational Aspects
- Sub-Chapter 18.1 - Human Factors
- Sub-Chapter 18.2 - Normal Operation
- Sub-Chapter 18.3 - Abnormal Operation
Chapter 19 – Commissioning
- Sub-Chapter 19.0 - Commissioning Safety Requirements
- Sub-Chapter 19.1 - Plant Commissioning Programme
Chapter 20 - Design Principles related to Decommissioning
- Sub-Chapter 20.1 - General Decommissioning Principles – Regulations
- Sub-Chapter 20.2 - Decommissioning - Implementation for the EPR™
Chapter 21 - Quality and Project Management
PCER
The Pre-Construction Environmental Report (PCER)
The Pre-Construction Environmental Report (PCER) provides the information requested by the Environment Agency in its guidance Process and Information (P&I) Document, to allow their detailed assessment of the UK EPR™ reactor environmental impact.
Contents
The Pre-Construction Environmental Report is divided into 12 chapters. The full list of the chapters and associated sub-chapters is available in the PCER Table of Contents.
Chapter 1 - Introduction and General Description
- Sub-Chapter 1.1 – Introduction
- Sub-Chapter 1.2 – General Description of the Unit
- Sub-Chapter 1.3 - Comparison with reactors of similar design
- Sub-Chapter 1.4 - Compliance with regulations
- Sub-Chapter 1.5 - Safety assessment and international practice
Chapter 2 - Quality and Project Management
Chapter 3 - Aspects having a Bearing on the Environment during Operation Phase
Chapter 4 - Aspects having a Bearing on the Environment during Construction Phase
Chapter 5 - Design principles related to decommissioning
Chapter 6 - Discharges and Waste - Chemical and Radiological
- Sub-Chapter 6.0 – Safety Requirements
- Sub-Chapter 6.1 – Sources of radioactive materials
- Sub-Chapter 6.2 – Details of the Effluent Management Process
- Sub-Chapter 6.3 – Outputs for the operating installation
- Sub-Chapter 6.4 – Effluent and waste treatment systems design architecture
- Sub-Chapter 6.5 – Interim storage facilities and disposability for UK EPR™
Chapter 7 - Measures for Monitoring the Discharges
Chapter 8 - Best Available Techniques
Chapter 9 - Principles and Methods used for Environmental Approach at the Design Stage
- Chapter 9 - Principles and Methods used for Environmental Approach at the Design Stage
Chapter 10 - Site Environmental Characteristics
Chapter 11 - Radiological Impact Assessment
Chapter 12 - Non-radiological Impact Assessment
Supporting Documents
Supporting Documents
As part of the UK EPR GDA submission, a number of supporting documents have been provided which supplement the information provided in the Safety, Security and Environmental Report (SSER). The topics covered are largely in the waste and decommissioning topic area and include: waste and spent fuel management options; interim storage facilities for spent fuel and Intermediate Level Waste; decommissioning waste inventory; arrangements for monitoring of liquid and gaseous discharges; the longer term proposed storage facilities for Intermediate Level Waste and spent fuel; the EPR™ integrated waste strategy; and the application of Best Available Techniques. A comparison of the EPR™ design against the HSE/NII Safety Assessment Principles has also been provided.
- BAT Demonstration
- Case for Disposability of Spent Fuel and ILW
- Comparison with HSE_NII SAPs
- Critique of the NDA RWMD Disposability Assessment
- Decommissioning
- Decontamination
- Dry Interim Storage Facility for ILW
- EPR UK Decommissioning Waste Inventory
- Form D1 Application UK EPR Project
- GDA Disposability Assessment of Wastes and Spent Fuel Part 1
- GDA Disposability Assessment of Wastes and Spent Fuel Part 2
- GDA Summary of Disposability Assessment for Wastes and Spent Fuel
- Integrated Waste Strategy Document
- Interim storage facility for spent fuel
- Longer Term ILW ISF
- Longer Term Spent Fuel ISF
- Monitoring of liquid and gaseous discharges
- PPC application - diesel generators
- RWMC Mapping
- Solid Radioactive Waste Strategy Report
- UK EPR LLWR Disposability Assessment - Preliminary D1 Form Information
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