Overview of ABWR Safety Features INPRO Dialogue Forum November 19-23, 2013 J. Alan Beard Principal Engineer Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved GE Hitachi nuclear alliance and businesses Wilmington, NC Tokyo, Japan Wilmington, NC Wilmington, NC Peterborough, ON USA USA Yokosuka, Japan Canada •Nuclear Power Plants: ABWR, •Uranium •Nuclear Fuel Fabrication ESBWR and PRISM Enrichment ….BWR and CANDU •Nuclear Services … Third •CANDU Services •Advanced Programs … Generation •Fuel Engineering and Support Recycling Technology Services •GENUSA European Fuel Joint Venture Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 2 BWR legacy around the world Dodewaard - Netherlands KKM - Switzerland K6/K7 - Japan Dresden 1 – USA KRB - Germany Lungmen - Taiwan Santa María de Garoña - Spain Vallecitos – USA Garigliano - Italy Laguna Verde - Mexico Tarapur 1&2 – India Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 3 Recent project experience Kashiwazaki-Kariwa 6/7 ABWR COD 1996/1997 Hamaoka-5 ABWR COD 2005 Shika-2 ABWR Continuously building for 58 years COD 2006 Images copyright TEPCO, Hokuriku Electric Power, Chugoku Electric Power, and J-Power; Provided by Hitachi GE Nuclear Energy Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 4 Current project status Ohma ABWR Ohma 1 • 38% complete Shimane 3 • 94% complete Under Construction • Approaching fuel load Shimane-3 ABWR Lungmen 1&2 • 94% complete • Startup and Pre-Op testing Under Construction Lungmen-1/2 ABWR Continuously building for 58 years Under Construction Images copyright TEPCO, Hokuriku Electric Power, Chugoku Electric Power, and J-Power; Provided by Hitachi GE Nuclear Energy Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 5 GE Hitachi’s new reactor portfolio ABWR ESBWR PRISM Revolutionary technology Operational Gen III Evolutionary Gen III+ technology technology with a rich, 40-year heritage • Lowest core damage frequency • Lowest core damage frequency • Passive air-cooling; no operator of any Generation III reactor of any Generation III+ reactor or mechanical actions needed • Extensive operational • Passive cooling for >7 days w/o • The answer to the used fuel experience since 1996 AC power or operator action dilemma - can reduce nuclear • Licensed in US, Taiwan & Japan • Lowest projected operations, waste to ~300-year radiotoxicity2 maintenance and staffing costs1 while generating electricity • 25% fewer pumps, valves and motors than active safety plants 1 Claims based on the U.S. DOE commissioned ‘Study of Construction Technologies and Schedules, O&M Staffing and Cost, and Decommissioning Costs and Funding Requirements for Advanced Reactor Designs’ and an ESBWR staffing study performed by a leading independent firm 2 To reach the same level of radiotoxicity as natural uranium Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 6 ABWR Basic Parameters 3,926 Megawatt core thermal power ~1,360 MWe gross • Nominal summer rating Reactor Recirculation with Internal Pumps • External recirculation piping eliminated Active safety systems • 72 hours automated capability Operating cycle length of 12 to 24 months Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 7 BWR Evolution Dresden 1 KRB Dresden 2 Oyster Creek ABWR ESBWR Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 8 Containment Evolution Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 9 ABWR Overall Flowchart Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 10 ECCS Systems Evolution Typical Typical ABWR BWR/4 BWR/5 BWR/6 RCIC HPCS LPCF/RHR HPCI LPCS LPCS ADS HPCF HPCF LPCI LPCI LPCI/RHR LPCI/RHR RHR RHR LPCI LPCI LPCS LPCI LPCF/RHR LPCF/RHR ADS ADS High pressure capacity 5000 1900 2800 Low Pressure capacity 42000 29000 19000 No. of large pipes below core 12 12 0 Peak clad temperature (App K), °F 1600 1100 No uncovery Operator action Required Required Automated >72 hours Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 11 Emergency Core Cooling System Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 12 Emergency Core Cooling HPCF LPCF/RHR ADS HPCF RCIC LPCF/RHR LPCF/RHR Core is always under water Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 13 ABWR Reactor Core Isolation Cooling (RCIC) Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 14 ABWR High Pressure Core Flooder (HPCF) Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 15 ABWR Residual Heat Removal (RHR) Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 16 Automatic Depressurization System (ADS) Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 17 ABWR Key Design Features – Onsite AC Power Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 18 Severe Accident Features ABWR passive features which mitigate severe accidents: • Inerted Containment • Lower Drywell flood capability • Lower Drywell special concrete & sump protection • Suppression pool - fission products scrubbing & retention • Containment overpressure protection Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 19 AC Independent Water Addition (ACIWA) Hard piped fire water connections Seismic Category 1 On-site fire protection system connection Truck connection • Ties to RHR C Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 20 References ABWR Design Certification Document, Rev. 4: http://www.nrc.gov/reactors/new-reactors/design-cert/abwr.html#dcd Safety Evaluation Report, NUREG-1503 and NUREG-1503 Supplement 1: http://pbadupws.nrc.gov/docs/ML0806/ML080670592.html Design Certification Rule, 10CFR52 Appendix A: http://www.nrc.gov/reading-rm/doc-collections/cfr/part052/part052- appa.html Revision 5 of the ABWR DCD can be found here: http://pbadupws.nrc.gov/docs/ML1100/ML110040323.html Reference BWR (Grand Gulf NPP) NUREG-1150 http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1150/ Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 21 .