An AREVA and Siemens Company

LING AO2 x 1000 MWe PWR

A success story

2

July 2002: Ling Ao Unit 1 inauguration ceremony chaired by Mr Li Peng

1 - LING AO PROJECT

2 - TECHNICAL DESCRIPTION

3 - SINO-FRENCH COOPERATION

4 - FRAMATOME ANP

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Framatome ANP is the world leader for the design and construction of nuclear powerplants and related equipment manufacture. Ling Ao 1 and 2 are the latest 1000 MWePWR units supplied by Framatome ANP. They were built by CGNPC, the nuclear powerutility of the Guangdong Province in China.

The two units were successfully commissioned in 2002, two months ahead ofschedule, and have been operating at full power since then: Unit 1 has recorded anoutstanding availability of 100% during the first year of operation. This performanceproves that the Ling Ao units have benefited fully from the evolutionary approachdeveloped in France which combines unique operating feedback with substantial R&Dand innovation programs.

The project was carried out in very close cooperation with the customer and Chinesepartners, thereby helping to enhance the self-reliance of the Chinese nuclear industry.

The outstanding success of this project illustrates the soundness of Framatome ANP'sprinciples:

■ Continuously improve plant design with innovative techniques and methods,■ Invest in intensive R&D programs and fully integrate the experience gained from

operation of a large number of Nuclear Power Plants,■ Be strongly committed to partnerships with its customers and local partners,■ Undertake to implement comprehensive technology transfer programs.

July 2003

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5

Ling Ao Nuclear Power Station is a2 x 1000 MWe PWR plant located atLing Ao Vil lage on the DapengPeninsula to the east of Shenzhen. ThePower Station is 1.2 km from the DayaBay Power Station, and 45 km fromdowntown Shenzhen. The Ling Ao sitecan accommodate two additional1000 MWe units. The owner is LANPC (Ling Ao NuclearPower Company), a wholly-ownedsubsidiary of CGNPC, created onOctober 4, 1995. Ling Ao Nuclear Power Station hasadopted internationally proven nuclearpower technology with Daya Bay as its

reference power station, whileincorporating substantial technicalimprovements to further enhance thesafety and reliability.The Nuclear Islands supplier isFramatome ANP France and theConventional Islands are supplied byAlstom, while BOP (Balance of Plant) isprocured by the owner directly fromboth domestic and internationalmarkets. LANPC is fully responsible for projectmanagement. All the civil constructionwork and most of the erection work isbeing undertaken by Chinesecompanies.

1 - LING AO PROJECT

Key Activities and Date Unit 1 Unit 2

• Signature of Main Supply Contracts October 1995 October 1995• Project Commencement (ATP) July 1996 July 1996• First Concrete Pouring May 1997 January 1998• Beginning of Nuclear Island Erection January 1999 September 1999• Initial Fuel Loading December 2001 July 2002• Initial Criticality February 2002 August 2002• Grid Connection February 2002 September 2002• Commercial Operation May 2002 January 2003

PROJECT SCHEDULE

SUPPLY & ERECTION CONTRACTS

The Framatome ANP scope of workincludes:

■ the supply of two Nuclear Islandsand the initial core fuel load,

■ erection of the Primary System,■ technical assistance to CNI 23rd

Company, the main erectioncontractor,

■ and a comprehensive transfer oftechnology.

Through the Nuclear Island SupplyContract, Framatome ANP hasdeveloped a localization program withChinese industry to progressivelyachieve Chinese self-reliance innuclear equipment manufacturing. Framatome ANP has also implementeda self-reliance program aimed attransferring knowledge and skil lscovering all Nuclear Island erectionactivities to the CNI 23rd Company.

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EVER-IMPROVED COMPETITIVENESS

Framatome ANP’s competitivenesshas been forged on more than 90 unitsbuilt around the world.

In France, the pace of commitmentsmade in the 70s for the domesticnuclear program required the design ofstandardized products. From series toseries, the design gradually evolved,integrating the experience feedbackgained during construction andoperation of all the preceding plants,while retaining enough flexibility to takeinto account the diversity of sites andchanges in safety regulations.

The economic advantages have beenmainly achieved by:

■ standardization (series effect),■ sustained pace of construction (low

manufacturing costs due to bulkorders, reduced construction time),

■ improved components and reactordesign (experience feedback, newtechnologies),

■ reduced generation costs (fuelcycle, maintenance, availability andradiation exposure).

For the Ling Ao project, the referencework schedule envisaged a period of62 months between first concrete andstart of commercial operation for bothunits. From fuel loading for Unit 1,work was ahead of schedule andcommercial operation occurred48 days early, on May 28, 2002. Unit 2,for which the planned work schedulewas eight months behind that of Unit 1,followed in the footsteps of Unit 1, andwas also well ahead of schedule:provisional take-over was signed bythe customer 3 months earlier thanplanned.

This outstanding achievement is theresult of close cooperation betweenLANPC and Framatome ANP. Specificmeasures, which were decided on thebasis of the experience gained duringthe construction of Daya Bay powerstation, contributed to the smoothimplementation of the project. For thispurpose, a technical liaison clauseallowed a direct link between the mainerection contractor, CNI 23rd company,and Framatome ANP as Nuclear IslandSupplier. All technical and workschedule issues were addressedthrough this direct link.

Another key point was theestablishment of an overall projectschedule by LANPC and FramatomeANP at the very beginning of theproject. This time schedule integrateddesign, supply, erection andcommissioning activities and took intoaccount the different interfaces andconstraints between the mainconstruction activities: equipmentsupply, civi l works, erection andtesting. This allowed the delivery onsite of the documents and equipmentin an order compatible withconstruction zone hand-over by thecivil works contractor and the erectionof subsystems in compliance with therequirements of the startup testschedule.

Framatome ANP developed acomprehensive time schedulesupported by powerful schedulingsoftware interfaced to the other projectmanagement tools, with more than15000 tasks and 3000 milestones.

PROJECT IMPLEMENTATION

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2 - TECHNICAL DESCRIPTION

PowerNSSS rated thermal output 2905 MWthGross electrical output 990 Mwe

Reactor ContainmentType Single Containment

Prestressed concrete + steel linerInside diameter 37 mWall thickness 0.90 mOverall height (from ground level) 59.4 mOverall internal volume 60000 m3

Overall internal free volume 50000 m3

Reactor CoreCore rated thermal output 2895 MWthCore damage frequency 5 x 10-6 reactor-yearNumber of fuel assemblies 157Total weight of Uranium 72.5 tRod cluster control available locations (equipped with CRDMs) 61

Main Primary SystemNumber of reactor coolant loops 3Number of CRDMs 61Reactor coolant system operating pressure 155 barReactor coolant temperature at RPV inlet 292.4°CReactor coolant temperature at RPV outlet 327.6°CSteam generator tube material Inconel 690Steam pressure at SG outlet at nominal power ≥ 67.1 barSteam flow rate 1614 kg/sSteam humidity at SG outlet < 0.25%Reactor coolant pump type Model 100Reactor coolant pump nominal flow 23790 m3/h

TECHNICAL DATA

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DESIGN BASIS

The design of the Ling-Ao plant isbased on Daya Bay Units 1 & 2. Itincludes improvements resulting fromoperating experience of FrenchNuclear Power Plants.The French Design and ConstructionRules (RCC) covering the systemdesign, mechanical components,electrical components, nuclear fuel, fireprotection, civi l works andSurveillance Rules for MechanicalComponents of PWR Nuclear Islandsin operation (RSEM) applied betweenthe owner, the designer and the

manufacturers enhance thestandardization effect and facilitate thetechnology transfer.Moreover, the model 55/19 steamgenerator, the model 100 primarypump, the advanced fuel assembliesand the advanced incore system,provide the reactor with importantdesign margins which guarantee safetyand performance targets.These margins may be used by theplant owner to increase fuel cyclelength, optimize power output andimprove the fuel management scheme.

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In accordance with the "defense indepth" concept, the design is based ona deterministic list of events, rangingfrom normal conditions to highlyunlikely accidents, including morestringent design criteria backed up byoperating experience.In addition, improvements wereintroduced at Ling Ao for core damageprevention. For example:■ preventive and mitigating features

in order to reduce risks in theshutdown state in the event of lossof the Residual Heat RemovalSystem or spurious increase inreactivity (boron dilution),

■ startup Steam Generator Feedwatersystem separate from EmergencyFeedwater system, reducing therisk of total loss of Steam Generatorfeedwater,

■ new reactor trip breaker design(improved Anticipated TransientWithout Trip - ATWT) increasing thereliability of the reactor trip systemfollowing a transient requiring itsactuation.

In 1999, a complete core damagefrequency analysis was reperformed onthe basis of the new equipmentreliability data bank accumulated onFrench Nuclear Power Plants up to theend of 1997, and taking into accountthe technical features of the Ling Aoproduct and Probabil istic RiskAssessment basic rules.The corresponding calculated core Thecorresponding calculated core damagefrequency was 5 x 10-6 per reactoryear.

SAFETY

Beyond design basis accidents

The Ling Ao design takes into accountthe total loss of redundant systemsand thus the probability of severehypothetical accidents resulting in coredegradation has been significantlyreduced by implementing:■ an improved man-machine interface,■ specific procedures (H procedures),

associated with specific items ofequipment, such as hydro-testpump turbine generator set,

reciprocal backup between safetyinjection pumps and containmentspray pumps,

■ futhermore, if al l implementedmeans fail to cope with an accidentwhich results in core melt, specificprocedures associated withdedicated hardware, such as sandbed filters, are provided to mitigatesuch highly improbable severeaccidents.

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Ling Ao 1 - Fuel loading authorization ceremony

REACTOR CORE

The core is composed of 157 fuelassemblies. Fuel management willevolve with the introduction of AFA 3G

fuel assemblies with a view toextending the fuel cycle to 18 months.

First Core Fuel Load Pattern First Core Control Rods Pattern

18-MONTH FUEL CYCLE FOR DAYA BAY

To improve the economics of plant operation and optimize fuelmanagement in reactor cores, GNPJVC made the decision to change from12-month to 18-month fuel cycles with improved fuel managementperformances.Long cycle operation requires higher fuel enrichment and performancelevels with improved cladding material and enhanced thermal-hydraulicperformances.The fuel selected for this advanced fuel management strategy was the mostadvanced and proven design, AFA-3G with mid span mixing grids and M5alloy as the cladding material.Today, all objectives set have been reached. Yibin Fuel Plant (YFP) in Chinamanufactured the AFA 3G assemblies for the 9th reload on time andcooperation with NPIC and GNPJVC in engineering self-reliance has beensuccessfully implemented.

R, N1, N2 : Black RCCAsG1, G2 : Gray RCCAsSA, SB, SC : Shutdown groups

AFA 3G fuel assembly

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The Ling Ao units incorporate the"mode G" reactor control capability forincreased and optimizedmanoeuvrability. The principle of thisreactor control mode is to compensatefor the effects of power variationsusing control rod movements only,whereas boration/dilution is only usedto compensate for longer termchanges in reactivity due to xenonpoisoning or fuel burnup changes.Dedicated "gray" control rod bankswith reduced absorption capacity are

used to l imit power distributiondisturbances and an independent highabsorbing rod bank provides the fineadjustment of core reactivity and axialpower shape.

With the high degree of f lexibil ityprovided by mode G, uti l it ies canbetter respond to grid power demandand can optimize the revenuegenerated when plants are operated ina deregulated electricity market.

Mode “G” for excellent operating flexibility

Fuel Assembly with Black Rods Fuel Assembly with Gray Rods

24 (B4C + Ag - In - Cd) rods

Instrumentation thimble16 steel rods

Instrumentation thimble

8 (Ag - In - Cd) rods

Operating Flexibility

Fuel assembly and shipment container

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The general layout of the Ling Ao plantis based on a twin-unit concept andtakes into account the applicablerequirements concerning radiologicalprotection and circulation of operatingpersonnel, fire protection, access formaintenance and other safety rules.The cylindrical reactor building, has asingle containment made ofprestressed concrete with an innermetal liner. A cylindrical structureinside the reactor building supports themain reactor coolant system, protectsand separates redundant trains, andforms protective bunkers forequipment such as steam generators,reactor coolant pumps, reactorpressure vessel and feedwater lines.The design also includes recirculationsumps with a large filtration capacity.The reactor building has an equipmenthatch located at operating floor level,used for bringing heavy componentsinto the building during construction,using the polar crane.The electrical building houses, on theupper floor, the Instrumentation andControl Systems and the main controlroom.From a safety standpoint, the designof the entire nuclear island ensuresphysical separation between units andbetween redundant trains of each unit,protection against internal flooding,division into fire protection areas, andprotection against external explosion,airplane crash, earthquakes andtornados.The adjacent fuel building houses thefuel handling and storage systemequipment. The safeguard auxiliariesare housed on the lower floor.The nuclear auxiliary building housesthe reactor auxil iary systemsequipment. It also contains radioactivewaste storage and treatment facilitiesas well as the required ventilation andhandling equipment.The nuclear pumping station isconnected to the nuclear island by anunderground seismic-resistant gallery.The balance of plant includes all otherbuildings and facilities necessary foroperation.

OVERALL ARCHITECTURE OF LING AO

Reactor building

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Reduction in radiation exposure

Improved maintainability with reducedradiation exposure is an importantfeature of Ling Ao design withimprovements such as:

■ plant layout,■ extended design life of critical parts

by improved equipment design,■ reduction in the number and

duration of maintenance andinspection tasks, by reducing thenumber of welds.

The layout improvements involveextensive separation betweenradioactive and non-contaminated

systems, easy access to steamgenerator channel heads and reactorcoolant pumps, and optimization offacilities and areas used during unitshutdown.The improvements made to equipmentto reduce radiation doses includegeometrical modifications to facilitatedecontamination and the use ofmaterials that release very fewcorrosion products. All Nuclear SteamSupply System components arepassivated on the primary side surface.

Plot plan

TWIN-UNIT CONCEPT

The twin-unit concept applied by Framatome ANP for its 1000 MWe units consists in having twounits share a single nuclear auxiliary building. As well as reducing the quantity of civil works, someequipment and systems such as waste processing and boron acid production are common to thetwo units. This particular design reduces construction and maintenance costs and contributes to thecompetitiveness of Framatome ANP’s 2 x 1000 MWe units.

Reactor Internals

The reactor internals guide the reactorcoolant flow from the inlet nozzles ofthe reactor vessel downwards, then upthrough the reactor core. The reactorcore is housed in the lower reactorinternals.

The upper internals incorporate the"inverted hat design" for the guide tubesupport plate. The control rod clusterguide tubes incorporate improvedlatest generation guide tube pins.

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REACTOR COOLANT SYSTEM

Reactor Vessel

The reactor coolant system consists ofthe reactor pressure vessel, reactorinternals, vessel head equipped withCRDMs and three loops. Each loop

comprises a steam generator, a reactorcoolant pump and reactor coolantpipes. The pressurizer is connected toone of the loops.

Consistent with the core size, the innerdiameter of the reactor vessel is 4m.The reactor vessel is built with anumber of welded forged parts cladinternally with two layers of stainlesssteel.The reactor vessel houses the reactorinternals and reactor core.The Ling Ao reactor vesselincorporates the followingimprovements:■ use of forged hollow ingots to

improve the metallurgical properties

of the material in the vicinity of thereactor vessel cladding,

■ base material with lower impuritycontent, resulting in significantreduction in reference nil ductilitytransition temperature (RNDTT) atthe end of life, thus increasing themargin with respect to britt lefracture,

■ upper head adapters and bottomhead penetrations made of Inconel690 alloy for better resistance tostress corrosion.

Ling Ao 1 Reactor vessel transportation Lower internals

The Ling Ao pressurizer, provided withthree separate relief lines, is equippedwith the overpressure protectionupgraded system (OPUS), developedby Framatome ANP to address the TMIissue.When inventory makeup of the reactorcoolant system becomes necessary,the valve lines can be forced open bythe operator using electromagneticactuators to perform feed and bleed.OPUS consists of three tandems ofpilot-operated safety valves with thefirst valve serving as a safety or reliefvalve and the second in series as anisolation valve which closes in thehighly unlikely case of the safety valvefailing to close after opening.

OPUS provides comprehensivepressure relief and overpressureprotection for all types of PWRs.The main advantages of OPUS include:■ compliance with the single failure

criterion due to the tandemconcept,

■ remote manual opening and closingin post-accident conditions,

■ qualified feed and bleed operationand improved set-point accuracy,

■ rel iabil ity of valve closing andleaktightness,

■ capability for periodic testing of set-points and operability without valvedismantling.

More than 60 units currently operatewith OPUS.

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Control Rod Drive Mechanisms (CRDMs)

A control rod drive mechanismconsists of an electromechanical jackin which three magnetic coils, actingon latch arms, initiate step-by-stepmovement of the drive rod and cluster.The mechanism is seal-welded to anadapter, which is incorporated into thereactor vessel upper head. The coils

are enclosed in a housing and areeasily removable.Jeumont Industrie is the FramatomeANP fully owned subsidiary for CRDMand reactor coolant pumpmanufacture. Cumulated productionexceeds 4500 CRDMs and 220 reactorcoolant pumps.

Reactor Coolant Pumps

The model 100 pump for Ling Aoincorporates improvements such as:radial discharge, single piece casingand removable diffuser.The hydraulic design for the impellerdiffuser ensures improved efficiency.The thermal barrier enclosure is bolted

rather than welded, and is removable.The pump diffuser is also removable.The cartridge design of the shaft sealsystem has also been improved toprovide easier access duringinspection and maintenance and toreduce replacement time.

Over Pressure Protection Upgraded System (OPUS)

Pressurizer manufactured in China

OPUS valve

Lower internals

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Steam generator & pressurizer

Steam Generators

The Ling Ao Steam Generators are ofthe 55/19 type: 5500 m2 of heattransfer area and 19.05 mm outsidediameter tubes. Their designincorporates advanced features toprovide the owner with optimumperformance and enhanced reliabilityand availability: ■ reduced number of pressure vessel

welds using: ● a one-piece hot spin upper dome

including an integral steam outletnozzle,

● a one-piece forged conical shellwith cylindrical ends,

● a one-piece forged primary headwith integral nozzles andmanways,

■ enlarged heat transfer area ensuringa steam pressure of at least 67.1bar at the SG outlet,

■ ultra-efficient moisture separationequipment permitting a 0.10%moisture carry-over content to beobtained,

■ optimized flow velocities above thetop of the tubesheet minimizing low

flow velocities and boiling areas andthus precluding excessive sludgedeposits,

■ improved tube material, tubesupports and tube-to-tubesheetjunction precluding tube damageencountered in the past:

● thermally-treated alloy 690 tubingto avoid water stress corrosioncracking and provide the bestmargin against the various formsof potential secondary sidecorrosion,

● 13% chromium stainless steeltube support plates with quatrefoilflat lands broached corrosion-resistant holes minimizingdenting, dry-out and excessivewear,

● optimized anti-vibration bars(AVB) installed layer after layerallowing the tube-to-AVBclearances to be reduced andexcessive wear to be precluded,

● two-shot, high-pressure hydraulicexpansion reducing the residualstresses in the hydraulicexpansion transition zone.

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Installation in reactor building

Steam generator installationReactor vessel handling

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REDUNDANT SAFETY SYSTEMS

Safety Injection, Containment Spray and Auxiliary FeedwaterSystems

The general organization and design ofthe safety systems adhere to the "two-train" concept: each system includestwo totally separate 100% redundant

sub-systems or "trains", plusdiversified backups to handle beyond-design-basis accidents.

The main function of the safetyinjection system is to cool the core inthe event of a leak in the reactorcoolant system.The system consists of two identicaltrains, each with one high-head pumpand one low-head pump, capable ofinjecting cold borated water into allthree loops, together with threeaccumulators on the cold legs.The charging pumps of the chemicaland volume control system are safetyclassified and perform the high-headsafety injection function. Thecontainment spray system which, inthe event of an accident, removes heatfrom the containment to the heat sink,consists of two identical trains, eachwith one pump, one heat exchangerand two spray rings.

The hydrotest pump, which is sharedbetween two units, is also used toensure continuous water injection tothe reactor coolant pump seals in theevent of total loss of electrical power.The electrical supply to this pump isprovided by a turbine-generator set(one for each unit) fed from the steamgenerators.The containment spray and low-headsafety injection pumps are cross-connected to allow long-term mutualbackup in the event of total loss ofeither system.The auxil iary feedwater systemremoves heat from the reactor coolantthrough the steam generators via thesteam dump to atmosphere, in theevent of unavailability or failure of themain and startup feedwater system.

Reactor safety systems

ReactorCoolantSystem

Safety InjectionAccumulators

AuxiliaryFeedwater

System

Safety InjectionSystem (LP-HP)

Containment SpraySystem Containment Spray

Test Pump Turbo-Generator Post AccidentMonitoring Instruments

PumpCooling

Long-termBackup

Heat ExchangersCooling

SteamDump to

Atmosphere

Reactor Trip

Refueling WaterStorage Tank

Reactor ProtectionSystem

Sump

Steam GeneratorCooling

Hydro-test Pump

to PumpSeals

Reactor Containment

Reactor ProtectionSystem

Reactor ProtectionSystem

ComponentCooling System

HeatSink

HeatSink

ComponentCooling System

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NUCLEAR AUXILIARY SYSTEMS

Chemical and Volume Control System

The chemical and volume controlsystem ensures reactor coolantvolume, chemistry and reactivitycontrol during normal operation.Three safety-classified, physicallyseparated, redundant charging pumps(one for train A and two for train B) areprovided for charging and waterinjection to the reactor coolant pumpshaft seals. They also ensure high-

head safety injection during incidentsor accidents.The three-pump configuration allowsmaintenance to be carried out on onecharging pump while the unit is inoperation.The charging pump and boric acidpump power supplies are backed upby the diesel generator sets.

Residual Heat Removal System

The residual heat removal systemremoves residual heat from the coreduring normal shutdown or in certainaccident conditions, once a sufficientlylow pressure is reached. It consists oftwo 100% capacity pumps and two100% capacity heat exchangers.The system is installed in the reactorcontainment so that leakage isconfined in the event of pipe break.

The spent fuel pit cooling systemprovides an additional backup.Moreover, total loss of the residualheat removal function is considered inthe safety evaluation. If this happens,heat is removed either by the steamgenerators or by using the reactorcavity and spent fuel pit cooling andtreatment system.

Reactor auxiliary systems

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Waste Treatment Systems

Waste treatment systems, shared bytwo units, have been designed toprovide the most appropriate responseto environmental releases according tolaws, rules and regulations.Improvements made to French NuclearPower Plant waste treatment systemshave been introduced at Ling Ao. Theyare supplemented by improvements

resulting from operating feedback fromthe Daya Bay units. The waste handledby the liquid waste treatment systemhas been reduced by 3000 m3 per yearand the amount of liquid releases byabout 100 m3/year/unit due to reroutingof the aerated water from the primarysystem.

The fuel unloading/reloadingoperations constitute the critical pathof the plant outage. Particular attentionis paid to the fuel handling systemsince its performance contributesdirectly to reducing outage time. Thefuel handling system includes, notably,the fuel manipulator crane, the fueltransfer device and the spent fuelbridge. The Ling Ao units are equipped withhigh density storage racks capable ofstoring more than 1200 fuel elementsin two regions: region 1 for new fuel

and region 2 for spent fuel. Thearrangement of the racks and the lowpitch between the storage cells isoptimized. A powerful neutronabsorber is used for rack fabrication.The storage capacity permits storageof spent fuel elements for 20 years ofplant operation, plus one normal reloadof new fuel and one complete coreshould forced unloading be necessary.The fuel storage rack design is alsocompatible with 18-month cycle fuelmanagement and fuel enrichment upto 4.5%.

Fuel loading - Fuel manipulator crane

Fuel Handling and Storage System

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Intake

Outfall

Mussel Traps *

Physical Separation

Barrier

Redundancy

* Sea site only

Component CoolingWater System

Cont. SprayComponent

CoolingSafety Inj.

Pumps

RC PumpsCooling

HeatExchanger

CRDMCooling

HeatExchanger

RedundantNeeds

TRAIN A

TRAIN B

ContainmentSpray Heat Exchanger

ElectricalBldg.

Chilled WaterCharg. PumpEmergencyVentilation

ContainmentSpray Heat Exchanger

Cont. SprayComponent

CoolingSafety Inj.

Pumps

ElectricalBldg.

Chilled WaterCharg. PumpEmergencyVentilation

Residual HeatRemoval Heat

Exchanger

Residual HeatRemoval Heat

Exchanger

SpentFuel

Pit HeatExchanger

Chemical& VolumeControl

HeatExchanger

Chemical& VolumeControl

LetdownHeat

Exchanger

RedundantNeeds

Common Operational Needs

SGBlowdownAux. Steam

WasteHeat

Exchanger

EssentialServiceWater

System

Heat SinkWater Filtration

Mussel Traps *

Heat SinkWater Filtration

Inside Reactor Containment

Reactor Cavity and Spent Fuel Pit Cooling and Treatment System

This system removes residual heatfrom the spent fuel storage pit. Itcomprises two redundant pumps andtwo redundant heat exchangers.The necessary redundancy formaintenance/repair is ensured by the

thermal inertia of the spent fuel pitwater.This system can also providefunctional redundancy of the residualheat removal system.

Component Cooling and Essential Service Water Systems

The component cooling systemremoves heat from auxiliary and safetysystems. It consists of two redundantsafety trains comprising two redundantpumps and two heat exchangers.Maintenance can therefore beperformed on the active componentsat any time.The ultimate heat sink is ensured bythe essential service water systemwhich includes two redundant safetytrains comprising two redundantpumps.

Component coolingheat exchanger

Cooling water systems

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Construction of dome

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INSTRUMENTATION AND CONTROL SYSTEMS (I&C)

The Ling Ao instrumentation andcontrol system replicates the well-proven and reliable I&C organization ofthe reference plant. This means thatthe plant is mainly operated throughconventional control means and

automated systems. Significantimprovements have been introducedsuch as state-of-the-art computersystems which contribute to optimisedand ever safer operation of the plant.

Control Systems

In addition to the "mode G" reactorcontrol, the key features of the Ling Aocontrol functions include: ■ automatic turbine load shedding

from full to house load operationwithout reactor trip to reducedowntime after a grid fault,

■ automatic steam generator levelcontrol from 0 to 100% full power,

■ the feedwater system is not trippedafter reactor trip, preventing steamgenerator transients,

■ automatic operation for powervariation, including at low load, bysimultaneous operation of theturbine bypass and the controlrods.

Process Computer System

The system is designed to provide theoperators with assistance duringnormal plant operation but also withguidance during post-accident phases.The process data are collected byprogrammable controllers distributedin different buildings, processed andthen presented to the operator throughuser-friendly graphic workstationsintegrated into the control room desks.Numerous functions are available tothe operators, including:

■ synthetic overview of plant status,■ automated system surveillance,■ alarm reduction,■ historical data management,■ post-accident operating procedure

guidance.

High performances have beenachieved by using up-to-dateprocessing techniques based oninternationally recognised standardssuch as the Unix operating systemwith a window-based graphic interfaceand a fast Ethernet communicationbus. Redundant architecture has beenadopted at all levels of the system toensure uninterrupted operation of theprocess computer system. The serverand data acquisition controllers areorganized in a dual hot-standbyconfiguration and communicationnetworks comprising of redundant ringbuses that are automaticallyreconfigured in the event of loss ofcommunication.

Computer system during commissioning test

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Nuclear Instrumentation System

This system measures the reactor fluxlevel using ex-core neutron detectors.These measurements are used both bycontrol and protection systems andover the source, intermediate and

power operating ranges. The nuclearinstrumentation system is 1E qualifiedand intermediate range channels fulfilpost-accident adverse conditionrequirements.

Protection System

The protection system is designed toautomatically trip the reactor andactuate the engineered safety featureswhen plant parameters exceed the pre-determined operating l imits. Thesystem comprises 4 independentgroups of instrumentation, signalprocessing units which issue partialtrip signals when parameters exceedthreshold values.

Two independent coincidence triplogics combine the partial trip signals,generally in a 2-out-of-4 logic to issuethe reactor trip or safeguard systemactuation signals. This logic isimplemented in a maintenance-freesolid-state technology, recognized forits very high reliability.

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Rod Control System

The rod control system actuates theCRDM to position the control rodsinside the reactor core. Staticelectronic switching units that arecycled and sequenced by digitalcontrollers regulate the CRDM powersupply currents. These controllers havebuilt-in surveillance features to detectany internal malfunction of the rod

control system and then to take thecounter-measures to preventinadvertent rod drop.

The rod control system also includesthe rod position indication systemwhich is used to monitor the actual rodposition.

Nov. 7, 2001 - France’s Finance Minister, Chinese Authorities and the AREVA Chairman in the Ling Ao 1 Control Room

Power range detectors are multi-staged with thermal neutroncollimating features. The output signalsare then used by a digital processingunit to compute on-line LOCA

margins, from the axial distribution andactual rod position. A terminal locatedin the control room is used by theoperators for optimized plant operationwithin the safety limits.

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Control Room

The unit is normally operated from themain control room that is protectedagainst earthquakes, missiles,radiation, contamination, f ire andsabotage. In the unlikely event ofcomplete unavailability of the maincontrol room, a remote shutdownpanel allows the operators to bring theplant back to safe shutdownconditions.

The Ling Ao control rooms benefit fromergonomic studies and improvementsresulting from operating experience ofsimilar units. The human factor hasbeen considered in the design of thecontrol desk and computer screendisplay: clear color coding rules,consistent functional grouping ofcontrol means and indicators andoperator guidance through computerdisplays.

Comprehensive post-accidentmonitoring instrumentation is availableto the operator including: ■ reactor vessel level indication

system, ■ core cooling monitor using core exit

thermocouple,■ radiation monitoring system.

The process computer also providesthe operator with powerful guidance inthe implementation of the postaccident procedures. These functionswhich are referred to as the safetypanel, include: ■ assistance in selecting the

applicable procedures,■ identification of the initiating event,■ continuous surveillance of the plant

safety parameters,■ automatic surveillance of safeguard

system status, availabil ity andconfiguration,

■ automatic surveillance of electricalpower supply sources,

■ monitoring of the performance ofsafety injection.

The technical support centre located inthe vicinity of the main control room isdesigned to host a team of experts inthe event of an emergency to assist theoperating team. Any plant informationcan be accessed from computerterminals located in the technicalsupport centre to help the experts intheir diagnosis without disturbing theoperation.

TIANWAN

Framatome ANP is the supplier of the instrumentation and control systems of Tianwan nuclearpower station.Tianwan Nuclear Power Station, located in China (400 km north of Shanghai), includes two Russiandesigned VVER-1000 Model “NPP 91” units. Unit 1 is scheduled to go on line in December 2004,with Unit 2 following one year later.The plant owner, Jiangsu Nuclear Power Corporation (JNPC) decided to equip Tianwan exclusivelywith an advanced digital instrumentation and control system and in 1998 selected Framatome ANPand Siemens with the globalTELEPERM I&C platform. TELEPERMrepresents the most moderntechnology of its kind presentlyavailable on the market and alreadyhas numerous applications.All I&C systems requiring nuclearqualif ication, such as the reactorprotection system, are implementedusing the digital I&C platformTELEPERM XS. This platform benefitsfrom a generic qualification making it possible to reduce the licensing time and efforts. It has alsoreceived approval from the US Nuclear Regulatory Commission (NRC).Operational I&C is implemented using the TELEPERM XP process control platform. This system alsoprovides operation and monitoring functions and makes it possible to operate the plant directly froma computer workstation.

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3 - SINO-FRENCH CO-OPERATION

In 1986, Framatome ANP signed acontract with GNPJVC for the designand supply of nuclear islands for thetwo 1000 MWe PWR Daya Bay nuclearpower units. In addition to the supplycontract, Framatome ANP activelyparticipated in construction incollaboration with CNI 23rd Company,and provided the customer with majortechnical assistance for thecommissioning of the plant.

The official inauguration of Daya BayNuclear Power Plant took place inFebruary 1994. Since then, this planthas consistently recorded impressiveannual operating results year after yearand has already received severalawards.

The Daya Bay power plant is owned byGuangdong Nuclear Power JointVenture Co. Ltd. (GNPJVC), which wasestablished by China GuangdongNuclear Power Holding Co. Ltd.(CGNPC) and Hong Kong China Lightand Power Co. Ltd.

Construction of Daya Bay NuclearPower Plant constituted a majorsuccess in the development of nuclearenergy in China. For the second step,Ling Ao, the Chinese authorities andCGNPC wished to combine theexecution of the project with extensiveefforts focused on technology transferand acquisition of technical autonomyto facilitate China's future nuclearpower program.To meet these expectations,Framatome ANP undertook anambitious localization and self-relianceprogram within the framework of thenuclear island supply contract.

The localization program wasimplemented in various ways throughjoint ventures, technology transferagreements and technical assistance,and it focused particularly on thehighly technical nuclear equipment.The localization ratio targeted in thecontract was achieved, with all locallymanufactured equipment delivered onschedule and with quality levelsidentical to the highest nuclearstandards.

The Ling Ao supply contract alreadyincluded a self-reliance program to thebenefit of LANPC teams, mainly in thefield of project management,engineering work and startup activities.This was then extended in September1997 to technical assistance,combined with an ambitious self-reliance program for CNI 23rd

Company. The aim of this program,which focused on the development ofself-reliance capabil it ies, was totransfer to CNI 23rd Company,Framatome ANP's knowledge andknow-how in the area of nuclear islanderection including primary systemconstruction, so as to facilitate theimplementation of China's futurenuclear power program. Theassessments performed for this self-reliance program, together with theresults obtained during the Ling Aoproject implementation phase,demonstrate the full success of thisprogram.

Over the past 10 years, cooperationbetween the Chinese and Frenchnuclear industries has been developingwithin the framework of severaltechnology transfer agreements. Theseagreements cover a wide range oftechnologies relating to the design,construction, operation andmaintenance of nuclear power plants.Implementation of these technologytransfers has produced positiveresults:

■ design and construction of Qinshanphase 2,

■ fuel manufacturing factory in Yibin,

■ implementation of 18-month fuelmanagement at Daya Bay,

■ joint venture for maintenanceservices, etc.

The outstanding achievement of thelocalization, self-reliance andtechnology transfer programs provesthe abil ity of Framatome ANP tosupport the long-term policy of thecustomer and the Chinese Authoritiesand contributes to the sustaineddevelopment of the Chinese NuclearIndustry.

28

Steam generator tubing and installation of anti-vibration bars in China

The Ling Ao project represents a majorstep in the development of the Chinesenuclear industry manufacturingcapability. To help meet this objective,the localization program implementedby Framatome ANP has been focusingon major nuclear components with avery high technical content, mainly forthe second unit in order to make thenecessary investments and carry outthe required qualification programs.

As early as 1995, Framatome ANPbegan selecting Chinese suppliers onthe basis of their industrial capability,their potential for meeting the highestapplicable standards and theirwill ingness to establish long-termcooperation. This process wasconducted by Framatome ANPengineering and procurement groupsand its own manufacturingorganization was highly involved. Thelocalization program was thenimplemented in different ways throughtechnology transfer, joint ventures and

technical assistance, including directassistance from French factories toChinese factories.

The extensive industrial know-how andexperience of Framatome ANP as aplant and component designer, butalso as a component manufacturerwith its own factories, has played adetermining role in the successfulcompletion of the localization program.The Framatome ANP team has beenworking closely with Chinese workersand technicians to transfer thenecessary know-how, train them andassist them in the implementation andoperation of the quality organization.

All the components manufactured inChina were delivered to the site incompliance with the erection timeschedule and without compromisingthe quality of the manufacturedcomponents, by strictly applying thehighest nuclear standards.

Steam Generators and Pressurizer

Dongfang Boiler Group Co. Ltd. (DBC)is a subsidiary of Dongfang ElectricCorporation (DEC) located in Zigongand Deyang in Sichuan province. DBChas manufactured key components forthe second unit of Ling Ao including:

■ one complete steam generator,■ two SG upper parts and assembly

of upper part and lower part,■ one complete pressurizer,■ three accumulators, and ■ one complete boron injection tank.

LOCALIZATION OF EQUIPMENT MANUFACTURING IN CHINA

29

Reactor Internals

Fabrication of reactor internals in China

Shanghai No.1 Machine Tool Workshas manufactured a large part of thereactor vessel internals for the secondunit of Ling Ao including the lowersupport columns, lowerinstrumentation columns, tie plates andbase plates, formers and baffles. It alsoassembled the lower reactor internals

and the assembly of the upper andlower reactor internals. Shanghai No.1 Machine Tool Workshas also manufactured all the controlrod guide tube upper parts for Ling AoUnit 2 and carried out final assembly ofthe lower parts.

Fabrication of steam generators in China

Lower internals core support plate

Nuclear Power Plants

Framatome ANP office

Equipment localization

30

Cable trays Steam piping CRDMs

Localization of Equipment

Northwest Zircocladding Co.Manufacturing of Fuel Assembly Components

Shanghai Xian FengManufacturing of 61 Drive Rods for CRDMsand 61 Latch Assemblies (LA2)

Changzhou Electric Machinery & Repair(CEMR)Manufacturing of Steam and Feedwater Piping(LA1 & 2)

Sichuan Chemical Machinery Plant(SCMP)Manufacturing of Reactor Coolant PipingComponents (LA2)

China Xi’an 524 FactoryManufacturing of Fuel Transfer Device, FuelHandling Tools, Sipping Test Container (LA2)New Fuel Storage Cells and Tools (LA1 & 2)

China National Erzhong (CNE)Manufacturing of Steam Generator Supports,Reactor Coolant Pump Supports, ReactorVessel Lifting Ring, Reactor Internals Handlingand Supporting Equipment, PressurizerSupports and Reactor Coolant PipingSupports (LA2)

Shenyang

Beijing

Xi'an

Deyang

Chengdu

Zigong

Yibin

Tianwan

Shanghaï

Qinshan

Daya Bay 1&2Ling Ao 1&2

31

Accumulators Fuel assembly

Manufacturing in China

Shanghai Power Equipment Co LtdManufacturing of Tanks, Demineralizers andHeat Exchangers (LA1 & 2)

Shanghai Cable WorksManufacturing of Power and Control Cables(LA1 & 2)

NingBo Zhenzhua Electrical EquipmentFactoryManufacturing of Cable Trays (LA1 & 2)

Zhenjiang Electrical Equipment FactoryManufacturing of Cable Trays (LA1 & 2)

S&T joint venture - CNI 23rd Co & SPIE(France)Manufacturing of Stainless Steel AuxiliaryPiping (LA1 & 2)

Yibin Nuclear Fuel Element PlantManufacturing of Fuel Assemblies

Shanghai Gaotai Rare & Precious Metals(SGTC)Manufacturing of Fuel Assembly Components

32

The cooperation between the ChineseNuclear Industry 23rd ConstructionCorporation and Framatome ANPstarted more than 10 years ago, duringerection of the Daya Bay nuclearislands.

This cooperation was furtherdeveloped during erection of theLing Ao Nuclear Island. CNI 23rd

Corporation was the main erectioncontractor for the nuclear islands.Framatome ANP was responsible formain primary system erection andprovided technical support to the CNI23rd Corporation to make it completelyself-reliant in all erection and fielddesign activities. The self-relianceprogram was set up between thepartners for both scopes of work -Nuclear Island erection work (CNI 23rd

Corporation scope) and the primarysystem erection work (Framatome ANPscope), and focused on the followingactivities: ■ technical management:

field design, delegations to the CNI23rd Corporation for the engineeringworks, procedures and end-of-erection reports,

■ project coordination: preparing,updating and managing thedifferent project schedules, externalsite coordination with civil works(room hand-over),

■ implementation of the works withspecific technology as well asequipment parts and materialmanagement, documentationmanagement, quality control andschedule control.

Framatome ANP's expatriates wereintegrated into the CNI 23rd

corporation organization with assignedChinese counterparts. Regular andimportant technical exchanges wereestablished throughout the projectimplementation period throughcorrespondance, technical meetings,documentation exchanges andtechnical audits.

The long-term cooperation relationshipand the technical liaison establishedbetween CNI 23rd Corporation andFramatome ANP made it possible tosolve all technical issues rapidly andresulted in smooth progress of theerection work ahead of schedule.

SELF-RELIANCE

Erection

33

34

35

In July 1992, Framatome ANP signed aCooperation Agreement with CNNC,transferring the Nuclear Islandtechnology implemented for the DayaBay nuclear power plant to Chinesedesign and engineering institutes. BINEand NPIC were the two institutesdesignated to receive the nuclearisland technology.

This Cooperation Agreement wasimplemented through two successivework orders signed in 1992 and 1996.More than 110000 pages ofdocumentation and 7000 drawings, aswell as computer codes, weretransferred to the Chinese institutes. Inaddition, Framatome ANP welcomedabout 220 Chinese engineers to Francefor training and meetings and providedtechnical assistance services in China.The direct application of thistechnology transfer agreement is thedesign and construction of theQinshan 2 plant which consists of two600 MWe units built in Hayan inZhejiang Province.

Extended Nuclear IslandCooperation Agreement

In October 1995, Framatome and EDFsigned a technical transfer agreementwith CGNPC which gives the ChineseNuclear Industry access to all theFramatome ANP and EDF technologyused to build plants in France, up tothe latest N4 plant series.

TECHNOLOGY TRANSFER

Nuclear Island Design: Qinshan phase 2

Qinshan phase 2: 2 x 600 MWe

36

Nuclear Fuel Technology Transfer to China

The first cooperation agreement in thefuel area was signed in May 1991between China Nuclear EnergyIndustry Corporation (CNEIC), asubsidiary of the China NationalNuclear Corporation, and FramatomeANP and involved several institutesand companies under the authority ofthe China National NuclearCorporation. The Nuclear PowerInstitute of China (NPIC), located inChengdu, was commissioned todesign the fuel assemblies andreloads, and the Yibin Fuel Plant wasput in charge of operating the AFA 2Gfuel assembly production andfabrication facilities.

As a result of this technology transfer,the Yibin Fuel Plant has beensuccessfully manufacturing all the fuelreloads needed by the two Daya Bayunits since 1994, with NPIC performingthe engineering work for the fuelmanagement and safety assessmentsof the reloads. Furthermore, in 2001and 2002, the Yibin Fuel Plantdelivered the first cores for both unitsof Qinshan Phase 2.

In order to reduce the kWh cost,GNPJVC decided, at the end of 1998,

to shift from 12-month to 18-monthfuel cycles. A new fuel technologytransfer for the localization in China ofAFA 3G fuel assembly design andmanufacture was set up between NPICand the Yibin Fuel Plant andFramatome ANP. NPIC carried out alarge part of the engineering studies forDaya Bay’s 18-month fuel cycles withadvanced AFA 3G fuel assemblies andthe Yibin Fuel Plant now deliversAFA 3G reloads for Daya Bay andLing Ao.

Framatome ANP is transferring itscladding tube fabrication technologyto two Chinese companies, ShanghaiGaotai Rare & Precious Metals (SGTC)and Northwest Zircocladding Co. Ltd.(NWZ) with final qualification scheduledfor 2003. Framatome ANP'ssubsidiaries, FBFC and CEZUS, areparticipating actively in thetransmission of their technology totheir Chinese counterparts.

This proves the huge amount of workand the progress made by Chineseinstitutes and industries in a space offew years to master nuclear fueltechnology.

Fuel assembly

37

NUCLEAR SERVICES

From the first maintenance servicescontract signed between GNPJVC andFramatome ANP in 1993, one yearprior to commercial operation of DayaBay Unit 1, the approach to self-reliance in the field of outage work wasbased on carrying out operationsjointly. Supplemented by theappropriate training, it involved anumber of simple principles:

■ GNPJVC would progressively takemore responsibility for the work,

■ shadow training of Chinesespecialists during work performedin France by Framatome ANPteams,

■ priority given to training in real-lifesituations ("on-the-job training"within integrated teams) overtheoretical teaching.

The objective of the programestablished was to allow GNPJVC to:■ carry out general maintenance

operations,■ manage all aspects of plant

outages: planning, time schedule,human resources, materialresources, dosimetry, etc.,

■ achieve self-reliance in allunforeseen maintenance situations.

This program started with the firstoutage of Daya Bay Unit 1 inDecember 1994. The effectiveness ofthe transfer of knowledge can bemeasured by comparing the situationduring the first outage in December 1994and the latest outage in early 2003:

■ for the first plant outage, more than100 Framatome ANP specialiststook part in the work and managedthe maintenance operations,

■ for the latest outage, only about40 Framatome ANP specialistswere present to provide technicalassistance and GNPJVC managedthe operations.

Other facts show that the knowledgetransfer objectives were achieved:■ the time schedules were met and

outage duration is decreasing,■ no major technical diff iculties

occurred during plant restarting,■ GNPJVC has considerable

autonomy in the resolution oftechnical difficulties,

■ the dosimetry l inked tomaintenance operations issatisfactory,

■ availability, averaged for both units,was more than 89% in 2001.

This clearly illustrates that Chinesemaintenance personnel have fullyunderstood and are able toimplement all general maintenanceoperations.

In the future, Framatome ANP willcooperate with CNI 23rd company andwill transfer its technology in the fieldof Nuclear Services to localize overallgeneral maintenance even further.Framatome ANP is also cooperatingwith Chinese Institutes in the field ofengineering services (BINE, NPIC) andin-service inspection (RINPO).

Fuel LoadingEquipment welding control training

38

PLANT PERFORMANCE

Since the start of commercialoperation, the Daya Bay plant hascontinuously recorded impressiveannual operating results year afteryear. In 2001, for the two units, theLoad Factor and Capacity Factorreached an average of 86.8% and89.5% respectively, and the total netelectrical output sent to the gridreached 14365 million kWh, the highestlevel since the start of commercialoperation.

In 1999 and 2000, the Daya Bay plantcame first in the "Safety Challenge"competition organized by EDF forFrench Nuclear Power Plants, at thesame time ranking seventh for overallcompetitiveness in comparison with

106 Nuclear Power Units in operationin the United States.

In 1998 and 1999, both units setexcellent records of "zero unplannedshutdown"and afterwards less thanone unplanned shutdown per unit.

Daya Bay has achieved a constantincrease in economic return every year.In 2000, the two units generated14063 billion kWh with an off-takerevenue of US$ 842 million and foreignexchange earnings from the electricityexport market reachedUS$ 590 million, thereby making aconsiderable contribution to China’seconomy.

China - Daya Bay 2 x 1000 MWe

39

4 - FRAMATOME ANP

Framatome ANP, an AREVA and Siemenscompany, is dedicated to nuclear poweraround the world. Framatome ANPprovides comprehensive engineering,instrumentation and control, nuclearservices, heavy component manufacture,modernization, fuel assemblies for manyreactor designs, including those suppliedby other vendors, and the developmentand construction of nuclear power plantsand research reactors. Framatome ANP isheadquartered in Paris with principalsubsidiaries in the U.S. and Germany. Inthe company, AREVA has a 66 percentshare and Siemens 34 percent.Framatome ANP has a total workforce ofapproximately 14,000 worldwide.

For further information,visit: http://www.framatome-anp.com

FRAMATOME ANP - 14 000 EMPLOYEES WORLDWIDE

Plants18%

Fuel37%

Services21%

Equipment11%

Corporate13%

FranceBelgium

52%Germany

21%

United States27%

WorkforceBreakdown by sector & by country

40

FRAMATOME ANP WORLDWIDE

41

01-03

96 NUCLEAR POWER PLANTS

42

Ling Ao 2 x 1000 MWe PWR

ATUCHA

ANGRA 2

KOEBERG

BRAZIL

ARGENTINA

SOUTH AFRICA

ULJIN

DAYA BAY / LING AO

SOUTH KOREA

CHINA

PWR in operationPWR under constructionPHWR in operationPHWR under constructionBWR in operation

FNR in operation

FLAMANVILLE

GRAVELINES

PENLY

CHOOZ

DOEL

BORSSELE

UNTERWESERSTADE

BROKDORFBRUNSBÜTTEL

KRÜMMEL

GROHNDEEMSLAND

BIBLIS

OBRIGHEIM

GRAFENRHEINFELD

NECKARWESTHEIMISAR

GUNDREMMINGENPHILIPPSBURG

CATTENOM

GÖSGEN

BUGEY

CRUAS

TRICASTIN

ST ALBAN

BELLEVILLE

DAMPIERRE

NOGENTST LAURENT

PALUEL

CHINON

CIVAUX

LE BLAYAIS

GOLFECH

TRILLO 1

FESSENHEIM

TIHANGEBELGIUM

NET

HER

LAN

DS

GERMANY

FRANCE

SPAIN

SWITZERLAND

ANGRA 3

PHENIX

NUCLEAR POWER PLANTS BUILT BY FRAMATOME ANP WORLDWIDE

43

Fra

mato

me A

NP

illu

stratio

ns

July

2003

AREVA, the world leader in nuclear power and connectors, is present in more than 30

countries.

The group’s employees provide customers with a full range of products and services for

electricity generation and develop connector products and interconnect systems mainly for

the communications and data markets.

AREVA brings expertise and technologies for better living to meet the challenges of the 21st

century: generalized access to energy and information, preservation of the planet, and

responsible stewardship of resources for future generations.

Projects and Engineering FranceHead Office: Tour AREVA - 92084 Paris La Défense Cedex - FrancePhone: +33 (0)1 47 96 00 00 - Fax: +33 (0)1 47 96 36 36

LING AO2 x 1000 MWe PWR

A success story