1.0 US-EPR Plant OverviewEPR Development Objectives Improved economics Reduce generation cost by at least 10% Simplify operations and maintenance 3 Safer Reduce occupational exposure

1.0 US-EPR Plant Overview

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Design HeritageThe U.S. Evolutionary Power Reactor (US-EPR) is a global product based on original U.S. technology and experience that has been advanced beyond existing plant designs.

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A mature design based on familiar technology

Evolutionary design based on existing PWR construction experience, R&D, operating experience, and “lessons learned.”

EPR Development Objectives

Improved economicsReduce generation cost by at least 10%Simplify operations and maintenance

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SaferReduce occupational exposure and low level wasteIncrease design marginsReduce core damage frequency (CDF)Accommodate severe accidents and external hazards with no long-term local population effect

Olkiluoto-3 (Finland)Construction started in 2005.Completion in 2012?

Flamanville-3 (EDF)Site preps started in 2006.Concrete pour started 12/2007.

UniStar (Constellation Energy + EDF)Calvert Cliffs 3 license application 07/2007 03/2008

EPRs Under Construction/Proposed

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Calvert Cliffs 3 license application 07/2007, 03/2008.China (agreement signed 11/2007)

Taishan 1 & 2, Guangdong provinceScheduled for completion in 2013/14.

AREVA (US-EPR design certification)DCD submitted 12/2007.

More U.S. License ApplicationsAmerenUE (Callaway), submitted 07/2008.UniStar (Nine Mile point), submitted 09/2008.PPL (Bell Bend), submitted 10/2008.

Elements of Design Philosophy

• Incorporate proven technology based on operating experience of existing PWRs.

• Make it cheaper & easier to operate & maintain

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maintain.• Make it safer: reduced exposure,

increased design margins, lower CDF.– N+2 (4 100% train) philosophy for some

safety-related systems.

Conventional 4-loop PWR design, proven by decades of design, licensing & operating experience

NSSS component volumes increased compared to existing

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co pa ed to e st gPWRs, increasing operator grace period for many transients and accidents

Reduced Equipment Quantities

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Study based on: RCS, PZR Spray, RCP seal and leakoff, SI/RHR, CVCS (including boration and demin/seal water, SFP cooling, CCW, FW, AFW/EFW/ and MS

U.S. Industry – Average Dose Per Reactor(1973 – 2004, Person-rem)

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Source: Nuclear Regulatory Commission Occupational Radiation Exposure at Nuclear Power Reactors and Other Facilities 2004Updated: 4/06

Improved Design Margins

9Increased power with improved margins

EPRI Utility Requirement

U.S. Nuclear Industry Safety Goals

U.S. NRCSafety Goal

Current U.S. LWR Plants

US-EPR

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1 X 10-4

Core Damage Frequency (yr-1)

5 X 10-5 1 X 10-5 4 X 10-7

General Plant Layout

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US-EPR vs. Current Unit Footprints

US-EPR1600 MWe

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4-Loop Unit1235 MWe

(similar to Callaway)

Major Design FeaturesNuclear Island

Proven Four-Loop RCS Design

Four-Train Safety Systems

No High Head ECCS

Double-Walled Containment

Electrical

Shed Power to House Load

Four Emergency D/Gs

Two smaller, diverse SBO D/Gs

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In-Containment Borated Water Storage

Severe Accident Mitigation

Separate Safety Buildings

Advanced Control Room

Site Characteristics

Airplane crash protection (military and commercial)

Explosion pressure wave resistance

Key Plant ParametersPARAMETER

Design LifeThermal Power, MWElectrical Power (Net), MWPlant Efficiency, %Hot Leg Temperature, °FCold Leg Temperature, °F

TYPICAL 4-LOOPPLANT (Uprated)

403587122034619559

US-EPR

604590160035

624563

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Increased power and thermal efficiency

g p ,Reactor Coolant Flow Per Loop, gpmPrimary System Operating Pressure, psiaSteam Pressure, psiaSteam Flow Per Loop, Mlb/hrTotal RCS Volume, ft3

Pressurizer Volume, ft3

SG Secondary Inventory at Full Power, lbm

100,500225010004.1

12,2651800

101,000

125,000225011095.17

16,2452649

182,000

EPR Heavy Reflector

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Reduces fuel cycle costProtects RPV shell against

irradiation embrittlement

Pressurizer Discharge Valve Arrangement3 Safety Relief Valves

• Held closed by PZR pressure• Each opened by:

• 1 spring-operated pilot valveOR

• 2 solenoid-operated pilot valves• 661,400 lb/hr each @ 2535 psig

2 Primary DepressurizationValves with block valves

•550 lb/sec each

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Three water-lubricated seals and a standstill seal

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RCP Shaft Seals

4-Train Systems:• Safety

Injection/RHR• Component

Cooling Water

Four-Train Safety Concept

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g• Essential

Service Water• Emergency

Feedwater

Each train of a 4-train safety system is independent and located within a physically separate building.

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ECCS• Suction from in-containment RWST; no switchover for

recirculation is necessary• No HHSI pumps; MHSI shutoff head is lower than

secondary reliefs– Can’t overfill an SG during an SGTR– SBLOCA response affected, so…

MSRT automatically actuated to reduce SG pressure to 870 psi in ~20 min. RCS pressure is then low enough for MHSI injection.

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“Partial Cooldown”

Severe Accident Mitigation:Molten Core Spreading Area

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Molten core leaves vessel and collects in spreading area, where it can be passively or actively cooled by water from IRWST.

Operator-Friendly Man/Machine Interface

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N4 Control Room EPR Control Room

Capitalizing on nuclear digital I & C operating experience and feedback

US-EPR Proposed Control Room

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Electrical Power

• 4 divisions of Class 1E power (one for each train of safety-related equipment), each with a backup EDG

• 2 SBODGs normally aligned to

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• 2 SBODGs normally aligned to nonsafety buses but capable of manual alignment to Class 1E buses

AREVA’s ConclusionsMost features are typical of operating PWRsFeatures included which help to

Improve SafetyIncrease redundancy & separationReduce core damage frequencyReduce large early release frequencyMitigate severe accident scenarios

Protect critical systems from external events

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yAircraft hazardExternal explosionFlood

Improve Human FactorsLower O & M Costs

Simplified systemsOn-line maintenanceUse of latest, proven technologyEconomy of scale

Summary of Major DifferencesCategory US-EPR Existing PWRs

RV Internals Neutron reflector Bolted baffle & former plates

RCS Pressure Control Feat res

3 PSRVs (auto & manual),2 primary

3 code safeties (auto),2 PORVs

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Features 2 primary depressurization valves(manual)3 spray nozzles (2 main, 1 auxiliary)

2 PORVs(auto & manual)

1 spray nozzle from all sources

RCP Seals Standstill seal No standstill seal

Safety Systems

4 100%-capacity trains 2 100%-capacity trains






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Safety Systems







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Safety Systems







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Safety Systems


Summary of Major DifferencesCategory US-EPR Existing PWRsECCS MHSI pumps have

highest shutoff headIn-containment RWST

HHSI & LHSI pumps

Outside RWSTSGTR Miti ti

Since MHSI pump di h ’t lift

Relatively prompt t ti d d

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Mitigation discharge can’t lift secondary relief valves, extended time for operator action

operator action needed to depressurize RCS to prevent SG overfill, radioactive release

SBLOCA Mitigation

Partial cooldown automatically initiated to promote MHSI injection

HHSI injects at high RCS pressures



HHSI & LHSI pumps




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SBLOCA Mitigation





HHSI & LHSI pumps




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SBLOCA Mitigation



Summary of Major DifferencesCategory US-EPR Existing PWRsSevere Accident Mitigation

Core melt stabilization system & severe accident heat removal system provide for ex-vessel cooling of molten core

Attempt to cool damaged core in-vessel by flooding reactor cavity

I & C M tl di it l A l

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I & C Mostly digitalWork stations + large-screen displays

AnalogPanels of switches, pushbuttons, status boards

Electrical 4 Class 1E EDGs2 SBODGs

2 Class 1E EDGsVariable AAC sources





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Documents

1.0 US-EPR Plant OverviewEPR Development Objectives Improved economics Reduce generation cost by at least 10% Simplify operations and maintenance 3 Safer Reduce occupational exposure