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ABWR GDA Documents
AREVA /EDF - UK EPR - Generic Design Assessment - AREVA EDF

Hitachi-GE will make a significant number of submissions to the regulators. We are committed to supporting the comment process with as much information as possible and will make these publicly available, publishing increasingly detailed submissions as GDA progresses.

We believe that this supports an effective comment process, however these are technical documents, which in many cases are translations from foreign languages, and contain design details which remain subject to further consideration. We will leave each published document live throughout GDA, however as these are superseded by later versions, they will be moved to the submissions archive, with the most modern documentation across GDA scope shown under 'Latest GDA submissions'.

In line with UK regulation, sensitive nuclear information and information restricted under export control legislation has been removed from these publications, as has commercially sensitive content.

The ABWR has been subjected to rigorous assessment by nuclear regulators in Japan, US and elsewhere. The US Nuclear Regulatory Commission (NRC) certified the US ABWR design in 1997 and has published its Design Certification Rule (DCR) at http://www.nrc.gov/reactors/new-reactors/design-cert/abwr.html

The UK ABWR is being similarly subjected to a rigorous process of assessment in the GDA. A comprehensive guide to nuclear safety, security and environmental performance is provided through key submissions, including the Pre-Construction Safety Report (PCSR) and the Generic Environment Permit (GEP) which were submitted to the regulator and published in August 2014.These are updated as the GDA progresses, and an updated PCSR was published on 30 October 2015. They will continue to be further updated as the GDA progresses.

Latest GDA submissions

Published materials, 30th October 2015

Pre-Construction Safety report (PCSR) - Revision B

  • Master Table of Contents
  • Chapter 1 - Introduction
  • Chapter 2 - Generic Site Envelope
  • Chapter 3 - Site Characteristics (Not Included in Generic PCSR)
  • Chapter 4 - Safety Management throughout Plant Lifecycle
  • Chapter 5 - General Design Aspects
    • General Safety Design Bases
    • Definition of Operational Stages, Operational Conditions and Safe Shutdown Conditions of Nuclear Power Plant
    • Definition of Design Basis Faults and Beyond Design Basis Faults
    • Categorisation and Classification of Structures, Systems and Components (SSCs)
    • Qualification of SSCs
    • Applied Regulations, Code and Standards
    • Monitoring, Inspections and Testing
  • Chapter 6 - External Hazards
  • Chapter 7 - Internal Hazards
  • Chapter 8 - Structural Integrity
  • Chapter 9 - General Description of the Unit (Facility)
  • Chapter 10 - Civil Works and Structures
  • Chapter 11 - Reactor Core
  • Chapter 12 - Reactor Coolant Systems, Reactivity Control Systems
    and Associated Systems
    • Reactor Coolant Systems and Associated Systems
    • Reactivity Control Systems
  • Chapter 13 - Engineered Safety Features
    • Summary of Description of Engineered Safety Systems
    • Containment System
    • Emergency Core Cooling System
  • Chapter 14 - Control and Instrumentation
  • Chapter 15 - Electrical Power Supplies
    • Introduction
    • Safety Claims – CAE and approach to protection against CCF
    • Architecture - power supply and power distribution
    • Electrical Equipment and systems
    • Electrical Protection and Earthing
    • Panel and Raceway Layout
    • Quality Assurance and Management Systems
    • Smart Devices, Software Development and System Justification
  • Chapter 16 - Auxiliary Systems
    • Water Systems
    • Process Auxiliary Systems
    • Heating Ventilating and Air Conditioning System
    • Other Auxiliary Systems
    • Severe Accident Management Systems
  • Chapter 17 - Steam and Power Conversion Systems
    • Introduction
    • Turbine Generator
    • Turbine Main Steam, Turbine Auxiliary Steam and Turbine Bypass System
    • Extraction Steam System
    • Turbine Gland Steam System
    • Feedwater Heater Drain and Vent System
    • Condenser
    • Circulating Water System
    • Condensate and Feedwater System
    • Condensate Purification System
  • Chapter 18 - Radioactive Waste Management
    • Source Terms
    • Liquid Radioactive Waste Management System
    • Off-Gas Radioactive Waste Management System
    • Solid Radioactive Waste Management System
  • Chapter 19 - Fuel Storage and Handling
  • Chapter 20 - Radiation Protection
    • Introduction
    • Definition of Radioactive Sources
    • Strategy to Ensure that the Exposure is ALARP
    • Protection and Provisions against Direct Radiation
    • Radiation and Contamination Monitoring of Occupational Exposure
    • Dose Assessment for Public from Direct Radiation
    • Post Accident Accessibility
  • Chapter 21 - Human-Machine Interface
  • Chapter 22 - Emergency Preparedness
  • Chapter 23 - Reactor Chemistry
  • Chapter 24 - Design Basis Analysis
  • Chapter 25 - Probabilistic Safety Assessment
  • Chapter 26 - Beyond Design Basis and Severe Accident Analysis
  • Chapter 27 - Human Factors
  • Chapter 28 - ALARP Evaluation
  • Chapter 29 - Commissioning
  • Chapter 30 - Operation
  • Chapter 31 - Decommissioning
  • Chapter 32 - Spent Fuel Interim Storage

Published materials, 28th August 2014

Generic Environmental Permit (GEP)

  • Chapter 1 - Summary of the Generic Environmental Permit Applications
  • Chapter 2 - Generic Site Description
  • Chapter 3 - Approach to Optimisation
  • Chapter 4 - Radioactive Waste Management Arrangements
  • Chapter 5 - Demonstration of BAT
  • Chapter 6 - Approach to Sampling and Monitoring
  • Chapter 7 - Quantification of Discharges and Limits
  • Chapter 8 - Prospective Dose Modelling
  • Chapter 9 - Other Environmental Regulations
  • Chapter 10 - Consideration of and Compliance with the Radioactive Substances Regulation Environmental Principles (REPs)

Documents below have been updated, and are superseded by those published in Latest GDA Submissions, hence these are no longer the focus of this Comment Process

Published materials, 6th January 2014

  • A summary of design improvements since the early generation of BWRs to the current ABWR: Genesis of ABWR Design.
  • A summary of how the basic ABWR will cope with the unlikely extreme events: Resilience of Design Against Fukushima Type Events.
  • A high level summary of how the UK ABWR will cope with events of increasing levels of severity: UK ABWR Design Concept.
  • A strategy for the development of the PCSR: GDA PCSR Development Strategy.
    [ Update published on 31 March 2014 ]
  • For the development of the GEP: Summary of GEP Submission.
    [ Update published on 31 March 2014 ]

Published materials, 31 January 2014

  • A general systems level description of the Advanced Boiling Water Reactor design in Japan.

Published materials, 31 March 2014

A number of technically focused documents have been published, representing a further step towards the pre-construction safety report. The documents are preliminary safety reports (PSR) on the reactor design, some of which are updates to materials published previously:

  • Codes and Standards Report
  • Categorisation and Classification of Structures, Systems and Components
  • Fault Studies to Discuss Deterministic Analysis, PSA and Fault Schedule Development
  • Generic Site Envelope
  • C&I Design and Preliminary Safety Case
  • Internal Hazards Report
  • Definition of Design Reference Point
  • GDA PCSR Development Strategy
  • Initial Safety Case report on Spent Fuel Pool
  • Preliminary Safety Report on Civil Engineering and External Hazard
  • Preliminary Safety Report on Structural Integrity
  • Preliminary Safety Report on Electrical Engineering
  • Summary of the Generic Environmental Permit Applications
  • Generic Site Description
  • Approach to Optimisation
  • Radioactive Waste Management Arrangements
  • Demonstration of BAT
  • Approach to Sampling and Monitoring
  • Quantification of Discharges and Limits
  • Prospective Dose Modelling
  • Other Environmental Regulations
  • Consideration of and Compliance with the REPs
  • Preliminary Safety Report on Mechanical Engineering
  • Preliminary Safety Report on Radiation Protection Section 1 Definition of Radioactive Sources
  • Preliminary Safety Report on Radiation Protection Section 2 Strategy to ensure that the exposure is ALARP
  • Preliminary Safety Report on Reactor Chemistry
  • Preliminary Safety Report on Radioactive Waste Management System
  • Preliminary Safety Report on Decommissioning
  • Preliminary Safety Report on Spent Fuel Interim Storage
  • Preliminary Safety Report on Reactor Core and Fuels

Materials published, 4th June 2014

  • Preliminary Safety Report on Electrical Engineering
  • Preliminary Safety Report on Human Factors

Materials published, 28th August 2014

  • Master Table of Contents
  • Chapter 1 - Introduction
  • Chapter 2 - Generic Site Envelope
  • Chapter 3 - Site Characteristics (Not Included in Generic PCSR)
  • Chapter 4 - Safety Management throughout Plant Lifecycle
  • Chapter 5 - General Design Aspects
    • General Safety Design Bases
    • Definition of Operational Stages, Operational Conditions and Safe Shutdown Conditions of Nuclear Power Plant
    • Definition of Design Basis Faults and Beyond Design Basis Faults
    • Categorisation and Classification of Structures, Systems and Components (SSCs)
    • Qualification of SSCs
    • Applied Regulations, Code and Standards
    • Monitoring, Inspections and Testing
  • Chapter 6 - External Hazards
  • Chapter 7 - Internal Hazards
  • Chapter 8 - Structural Integrity
  • Chapter 9 - General Description of the Unit (Facility)
  • Chapter 10 - Civil Works and Structures
  • Chapter 11 - Reactor Core
  • Chapter 12 - Reactor Coolant Systems, Reactivity Control Systems
    and Associated Systems
    • Reactor Coolant Systems and Associated Systems
    • Reactivity Control Systems
  • Chapter 13 - Engineered Safety Features
    • Summary of Description of Engineered Safety Systems
    • Containment System
    • Emergency Core Cooling System
  • Chapter 14 - Control and Instrumentation
  • Chapter 15 - Electrical Power Supplies
    • Introduction
    • Safety Principles and Standards
    • Architecture
    • Electrical Equipment
    • Electrical Protection
    • Panel and Raceway Layout
    • Quality Assurance and Management Systems
    • Smart Devices, Software Development and System Justification
  • Chapter 16 - Auxiliary Systems
    • Water Systems
    • Process Auxiliary Systems
    • Heating Ventilating and Air Conditioning System
    • Other Auxiliary Systems
    • Severe Accident Management Systems
  • Chapter 17 - Steam and Power Conversion Systems
    • Introduction
    • Turbine Generator
    • Turbine Main Steam, Turbine Auxiliary Steam and Turbine Bypass System
    • Extraction Steam System
    • Turbine Gland Steam System
    • Feedwater Heater Drain and Vent System
    • Condenser
    • Circulating Water System
    • Condensate and Feedwater System
    • Condensate Purification System
  • Chapter 18 - Radioactive Waste Management
    • Source Terms
    • Liquid Radioactive Waste Management System
    • Off-Gas Radioactive Waste Management System
    • Solid Radioactive Waste Management System
  • Chapter 19 - Fuel Storage and Handling
  • Chapter 20 - Radiation Protection
    • Introduction
    • Definition of Radioactive Sources
    • Strategy to Ensure that the Exposure is ALARP
    • Protection and Provisions against Direct Radiation
    • Protection and Provisions against Radioactive Contamination
    • Radiation and Contamination Monitoring of Occupational Radiation Exposure
    • Dose Assessment for Public from Direct Radiation
    • Post Accident Accessibility
  • Chapter 21 - Human-Machine Interface
  • Chapter 22 - Emergency Preparedness
  • Chapter 23 - Reactor Chemistry
  • Chapter 24 - Design Basis Analysis
  • Chapter 25 - Probabilistic Safety Assessment
  • Chapter 26 - Beyond Design Basis and Severe Accident Analysis
  • Chapter 27 - Human Factors
  • Chapter 28 - ALARP Evaluation
  • Chapter 29 - Commissioning
  • Chapter 30 - Operation
  • Chapter 31 - Decommissioning
  • Chapter 32 - Spent Fuel Interim Storage

Next Steps

The GDA is a long-term iterative process, throughout which we will submit a range of documents to the regulators.

The initial submissions published alongside launch of this site have been further revised. Two revisions of our Pre-construction Safety Report (PCSR) have been published, as has our Generic Environmental Permit (GEP). Further revisions will be made available for each, as we progress through the GDA.

The GDA is a two-way process and the regulators will provide extensive feedback on our proposals. Where the regulators believe there is a potential regulatory shortfall they will raise a “Regulatory Observation” or a “Regulatory Issue”.  We expect these to arise over the course of GDA as a natural part of the process, each RO or RI will be published by the regulators on their web-site along with our Resolution Plans



ABWR GDA Documents
AREVA /EDF - UK EPR - Generic Design Assessment - AREVA EDF
Westinghouse UK New Nuclear Documentation


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