Introduction to GE Hitachi

State-of-the-art NPP technology

Nuclear Power Asia 2014

Patrick Looney Commercial Leader, Nuclear Plant Projects General Electric Hitachi Nuclear Energy

Wilmington, NC Tokyo, Japan Wilmington, NC Wilmington, NC Peterborough, ON USA USA Yokosuka, Japan Canada

• Nuclear Power Plants: • Uranium • Nuclear Fuel Fabrication ABWR, ESBWR and PRISM Enrichment ….BWR and CANDU • Nuclear Services … Third • CANDU Services • Advanced Programs … Generation • Fuel Engineering and Recycling Technology Support Services

Operational Gen III Evolutionary Gen III+ Revolutionary technology technology technology with a rich, 40-year heritage

• Lowest core damage • Lowest core damage frequency • Passive air-cooling with no operator frequency of any of any Generation III+ reactor or mechanical actions needed Generation III reactor • Passive cooling for >7 days • The answer to the used fuel • Extensive operational without AC power or operator dilemma - can reduce nuclear experience since 1996 action waste to ~300-year radiotoxicity2 • Licensed in US, Taiwan, • Lowest projected operations, while providing new electricity and Japan maintenance, and staffing generation costs1 • 25% fewer pumps, valves, and 1 Claims based on the U.S. DOE commissioned ‘Study of Construction Technologies and Schedules, O&M Staffing and Cost, and Decommissioning motors than active safety Costs and Funding Requirements for Advanced Reactor Designs’ and an ESBWR staffing study performed by a leading independent firm nuclear plants 2 To reach the same level of radiotoxicity as natural uranium Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 3 reserved Simplicity “Simplicity is the ultimate sophistication” - Leonardo da Vinci Dresden 1 KRB

Dresden 2 Oyster Creek

ABWR ESBWR

Simplicity improves safety

PRA of Core Damage Frequency PRA

U.S. PWRs U.S. BWRs APR1400 APWR EPR AP1000 ABWR ESBWR 2 E-5 (avg.) 8 E-6 (avg.) 2 E-6 1.2 E-6 2.8 E-7 2.4 E-7 1.6 E-7 1.7 E-8 III+ III+ Generation II Generation III References: Plant licensing DCDs and publically available information Note: PRA of CDF is represented in at-power internal events (per year) Note: NSSS diagrams are for visualization purposes only Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 5 reserved Simplicity reduces equipment and costs

ESBWR Steam Generator Some similarities • Natural circulation • Steam separators and dryers

Some differences • PWR heat exchange surfaces (steam generator tubes) wear out over 20-30 years o Replacing steam generators is costly and risky • ESBWR’s exchange is simply refueling o Routine maintenance for both

Source: U.S. NRC; Hitachi GE Copyright 2014 GE Hitachi Nuclear Energy – Americas, LLC - All rights 6 reserved Simplicity reduces equipment and costs All in one ESBWR vessel ESBWR Everything else is just extra that impacts: • Manufacturing • Construction/Installation • O&M • Decommissioning

ESBWR requires significantly fewer plant personnel than any other Generation III/III+ design. • A direct reflection of the ESBWR’s simpler design • Lower O&M costs • Reduced burden for human resource development

• BWR steam does go directly from reactor to turbine

• Operating radiation from N-16 (decays @ T1/2 7.1

seconds) is minimized with shielding

3 • N-16 is not an issue during maintenance … Year - minimal protection required 2.5 ESBWR dose reduction

2 rem) per MW - BWR PWR • Simplified design/reduced maintenance ABWR -No recirculation pumps/pipes 1.5 -No ECCS pumps • Reduction of Cobalt containing material 1 ->50% Co-60 reduction vs. Gen II BWR

0.5 Collective Collective Dose (person ESBWR 0 (projected)

Systems are eliminated, equivalent or simplified • 11 Systems eliminated • 25% fewer safety-related components

SLCS

• Fully passive – only requires gravity to function and starts automatically (fails in-service if DC power is lost) • 4 separate systems in reinforced concrete vaults • Limits reactor pressure (no SRV lifts) and temperature and conserves water inventory following containment isolation • Steam (heat) rises from reactor to the condenser pool, condenses, then gravity pulls the cool water down into the reactor passive (closed-loop) decay heat Removes heat removal Core cooling from containment

Passive systems working in harmony for a LOCA: PCCS Pool & Heat Exchanger 3 1. ADS – reduce pressure • Reactor pressure is reduced by 10 SRVs & 8 DPVs 2. GDCS – connect circuit & fill DPV • Squib actuated valves allows water to flow from 3 GDCS pools to reactor by gravity 1 3. PCCS – circulate & cool • Natural circulation loop hot steam rises from drywell, condensed in PCCS HX, drains to GDCS • 6 PCCS pool steams off, removing heat from containment 2

ADS - Automatic Depressurization System GDCS - Gravity Driven Cooling System PCCS - Passive Containment Cooling System SRV - Safety Relief Valve DPV - Depressurization Valve

Responses to extended loss of all AC power

EPR and Operator Electric Water GEN II Action Power 30 MIN. 2 HRS. 24 HRS.

ABWR

30 MIN. ~36 HRS.* DECAY HEAT

AP1000 72 HRS.

• Gen III+ passive plants allow for ESBWR a much longer coping time • Decay heat level impacts urgency >7 days

*ABWR DCD credits water addition at 8 HRS. References: AP1000: US DCD rev. 18 Section 8.5.2.1, EPR: US DCD Rev. 1 Section 8.4

Only 9kW/12HP pump needed for ICS pool refill OR OR

Simplification • Less equipment • Lower capital costs • Lowest staffing levels • Less maintenance costs “Simplicity is the • Lower dose ultimate sophistication” - Leonardo da Vinci • Safest (lowest CDF) The most advanced passive technology • Uses the forces of nature • >7 day passive cooling capability