16.2 - Severe Accident Analysis (RRC-B) - EDF Hinkley Point

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Title: PCSR – Sub-chapter 16.2 – Severe accident analysis(RRC-B)Page No.:UKEPR-0002-162 Issue 04II / IIICopyright © 2011AREVA NP & EDFAll Rights ReservedThis document has been prepared by or on behalf of AREVA NP and EDF SA in connection with theirrequest for generic design assessment of the EPR TM design by the UK nuclear regulatory authorities.This document is the property of AREVA NP and EDF SA.Although due care has been taken in compiling the content of this document, neither AREVA NP, EDFSA nor any of their respective affiliates accept any reliability in respect to any errors, omissions orinaccuracies contained or referred to in it.All intellectual property rights in the content of this document are owned by AREVA NP, EDF SA, theirrespective affiliates and their respective licensors. You are permitted to download and print contentfrom this document solely for your own internal purposes and/or personal use. The document contentmust not be copied or reproduced, used or otherwise dealt with for any other reason. You are notentitled to modify or redistribute the content of this document without the express written permission ofAREVA NP and EDF SA. This document and any copies that have been made of it must be returned toAREVA NP or EDF SA on their request.Trade marks, logos and brand names used in this document are owned by AREVA NP, EDF SA, theirrespective affiliates or other licensors. No rights are granted to use any of them without the prior writtenpermission of the owner.EPR TM is an AREVA Trade Mark.Trade MarkFor information address:AREVA NP SASAn AREVA and Siemens CompanyTour AREVA92084 Paris La Défense CedexFranceEDFDivision Ingénierie NucléaireCentre National d'Equipement Nucléaire165-173, avenue Pierre BrossoletteBP90092542 MontrougeFrance
Title: PCSR – Sub-chapter 16.2 – Severe accident analysis(RRC-B)Page No.:UKEPR-0002-162 Issue 04III / IIITABLE OF CONTENTS0. SAFETY OBJECTIVES0.1. GENERAL1. APPROACH TO SEVERE ACCIDENT CONTROL1.1. BASIC STRATEGY1.2. SPECIFIC DESIGN MEASURES1.3. SPECIAL ISSUES2. ANALYSIS OF CORE MELT SEQUENCES2.1 IN-VESSEL ACCIDENT PROGRESSION AND SELECTION OF RELEVANTSCENARIOS2.2 ASSESSMENT OF PRIMARY SYSTEM DEPRESSURISATION2.3. ASSESSMENT OF HYDROGEN CONTROL2.4. ASSESSMENT OF MELT STABILISATION2.5. CONTAINMENT PRESSURE AND CONTAINMENT TEMPERATURE3. RADIOLOGICAL CONSEQUENCES OF CORE-MELT SEQUENCES3.1. SAFETY REQUIREMENTS3.2. REFERENCE SOURCE TERM3.3. CALCULATION OF RADIOLOGICAL CONSEQUENCES3.4. EVALUATION OF THE POTENTIAL RADIOLOGICAL CONSEQUENCESUSING FRENCH NPP ASSESSMENT METHOD
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16.2 - Severe Accident Analysis (RRC-B) - EDF Hinkley Point

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