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

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SUB-CHAPTER : 16.2PRE-CONSTRUCTION SAFETY REPORTCHAPTER 16: RISK REDUCTION AND SEVEREACCIDENT ANALYSESPAGE : 281 / 295Document ID.No.UKEPR-0002-162 Issue 042.2.3.4. Temperatures in the Primary System2.2.3.4.2. Risk of Creep Rupture in RCS Pipes in case of Delayed Depressurisation[Ref][Ref]P Gandrille. EPR RF002. Severe Accidents. Dedicated Reactor Coolant SystemDepressurisation. Functional requirements. NFEPD DC 0091 Revision C.Framatome ANP. August 2004. (E)J Heliot, G Azarian. EPR BD. Severe Accidents. Assessment of steam generator tuberupture risk induced by a core melt scenario. ETSS DC 0782 Revision A.Framatome ANP. February 1999. (E)SECTION 16.2.2.2 - TABLES 1 TO 2[Ref]J Heliot, G Azarian. EPR BD. Severe Accidents. Assessment of steam generator tuberupture risk induced by a core melt scenario. ETSS DC 0782. Framatome ANP.December 1994.SECTION 16.2.2.2 - FIGURES 2 TO 15[Ref]J Heliot, G Azarian. EPR BD. Severe Accidents. Assessment of steam generator tuberupture risk induced by a core melt scenario. ETSS DC 0782 Revision A.Framatome ANP. February 1999. (E)SECTION 16.2.2.2 – FIGURE 16[Ref]Dolleans. FA3. Severe accident. Thermo-hydraulic loads on vessel support and reactorpit in case of lower head failure at 20 bar. FRA1 Contract A. AREVA Report NEPDFDC22. February 2008. (E)2.3. ASSESSMENT OF HYDROGEN CONTROL2.3.1. Approach to the verification of the efficiency of the Combustible GasControl System[Ref][Ref][Ref]A Caillaux. EPR RF002. Severe Accident. 5.5.2 In-vessel analysis. Hydrogen SourceTerm. NFEPD DC 0059 Revision B. Framatome ANP. January 2004. (E)W Hering, Ch Homann, J-S Lamy. ISP 45-OECD Comparison Report on the BlindPhase of the OECD International Standard Problem n o 45 exercise (QUENCH06).Report FZKA-6677. March 2002. (E)U Schwarz. PAR Qualification Report. General Description.PESB-G/2011/en/1001 Revision A. AREVA NP. January 2011. (E)
SUB-CHAPTER : 16.2PRE-CONSTRUCTION SAFETY REPORTCHAPTER 16: RISK REDUCTION AND SEVEREACCIDENT ANALYSESPAGE : 282 / 295Document ID.No.UKEPR-0002-162 Issue 04[Ref][Ref]M Hupp. Description of validation of AREVA recombiner modeling in computationalprograms based on extensive, international, qualificational testing.PEPA-G/2011/en/1001 Revision B. AREVA NP. January 2011. (E)M Bauer, M A Movahed, J Eyink. Prevention and mitigation of hydrogen risk impact ofthe two room concept and metallic liner, interface with civil work and layout.NGPS4/2006/en/1014 Revision D. Framatome ANP. June 2007. (E)2.3.2. Potential Pressure Loads2.3.2.2. Hydrogen Distribution[Ref]M A Movahed. Basic Containment Model for CFD Codes GASFLOW and COM3D.AREVA Report NESB-G/2008/en/0313, to be published. (E)2.3.2.3. AICC and Expected Combustion Pressure[Ref]J Eyink. Pressure and Temperature Loads for EPR with Steel Liner resulting fromHydrogen Combustion. NGPS4/2003/en/0020 Revision D. Framatome ANP.February 2004. (E)[Ref]J Eyink, M Movahed, K-G Petzold. Justification of the H2 mitigation concept: Directhydrogen release into the containment. Siemens Report KWU NA-T/1999/E/042Revision B. September 1999. (E)2.3.3. Assessment of the Combustion Mode2.3.3.3. Influence of the Activation of the Spray System[Ref]J Eyink, M Movahed. Effect of Spray Activation on the Reactivity of the Hydrogen-Air-Steam Mixture. NGES2/2002/en/0018 Revision B. Framatome ANP. (E)2.3.3.4. Dynamic Pressure Loads2.3.3.4.1. 5 cm (20 cm²) SB(LOCA) in the Cold Leg with Fast Secondary Cool-down[Ref]J Eyink. Pressure and Temperature Loads for EPR with Steel Liner resulting fromHydrogen Combustion. NGPS4/2003/en/0020. Framatome ANP. (E)2.3.3.4.2. 7.5 cm (46 cm²) SB(LOCA) in the Pressuriser with Fast Secondary Cool-down[Ref]J Eyink. Pressure and Temperature Loads for EPR with Steel Liner resulting fromHydrogen Combustion. NGPS4/2003/en/0020. Framatome ANP. (E)2.3.3.4.3. 5 cm (20 cm²) SB(LOCA) with Partial Cool-down and DelayedDepressurisation[Ref]J Eyink. Pressure and Temperature Loads for EPR with Steel Liner resulting fromHydrogen Combustion. NGPS4/2003/en/0020. Framatome ANP. (E)
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16.2 - Severe Accident Analysis (RRC-B) - EDF Hinkley Point

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