November 7, 2018ners2018.jmm.cz/download.php?file=11_Kim_NERS_2018_ENG.pdf · materials of the containment Emergency Reactor Depressurization System Preventing high pressure molten

Copyright © 2018. All rights reserved by KHNP.

November 7, 2018


1 Safety & Licensability of Proposed Design

4 Closing Remarks

Compatibility for Czech Nuclear New-Build2

Longterm Partnership with Czech Nuclear Industry3

2


1Safety & Licensability of Proposed Design

3


Overview of APR1000

1,000Mw class design of APR series for Czech nuclear new-build,

complying with WENRA, IAEA, EUR Proven design through high performance operation of reference plant

Verified Advanced Design Features through various experiments and

International Design Certification

4

OPR1000

1,000 MWe

12 units operatingfrom 1995

APR1400

1,400 MWe

• SKN 3 in operation• 9 units under construction

4

Adopting ADFs &complying with IAEA, WENRA

EU-APR

1,500 MWe

Complying with NRC requirement

US-APR

1,400 MWe

Adopting ADFs &complying with IAEA, WENRA

APR1000

1,000 MWe


US NRC Approval

EUR CertificationEU-APR

US-APR

International Design Certification

5


Experiments for Advanced Design Features

6

Passive Aux. FW System

Fluidic Device in SIT : VAPER

Safety Injection System

Integral Test : ATLASMMI : Dynamic Mockup

Core Catcher

PCCT

11m


Safety Philosophy

7

DiD design concept in line with IAEA, WENRA and Czech ISARLevel of DiD Objective Essential means

Level 1 Prevention of abnormal operation and failures

Conservative design and high quality

Level 2 Detection of failures and control of abnormal operation

Control, limiting and protection systems and surveillance

Level 3 Level 3a: Control of Accidents

Level 3b: Control of Design Extension Conditions

Engineered Safety Features

Diverse (Additional) Safety Features

Level 4 Mitigation of Severe Accidents Dedicated (Complementary) Safety Features

Level 5 Emergency preparedness Off-site emergency response


DiD Architecture

8


Layout and Structure Design

Secondary containment and physically separated arrangement of

safety buildings against intentional airplane crash

Physically separated quadrant arrangement to prevent the

propagation of fire, flood, interaction seismic movement, pipe whip

9

Double Containment

Ventilation Stack

Quadrant Arrangement ofFully 4-train Safety

Systems

Severe Accident Mitigation Systems

Diversity Design for Shutdownand Decay Heat Removal


Safety System DesignRedundancy N+2 Design : SC-2 systems to mitigate DBC 3 & 4 accidents

N+1 Design : SC-3 systems to mitigate DBC 2, DEC and Severe Accidents

Diversity System or component level alternative measures against CCFs of systems

performing safety functions in the event of AOO & DBC 3

10


Passive Auxiliary Feed-water SystemPassive safety feature completely substituting conventional active

Aux-Feedwater System

Remove core residual heat using natural force for at least 72 hours

in the extremely rare events such as Fukushima Accident

11

Steam Generator

Vent

Feed Water

System

MSIV

Main Steam System

MFIV

Vent

Containment

Passive Condensate Cooling Tank(PCCT)

Aux. BldgEL. 199'

14"

10"

Economizer Nozzle

FE

TE

AL


Severe Accidents Dedicated Mitigation SystemSAs dedicated mitigation systems to preserve the containment

integrity independent of safety systems for Design Basis Conditions

System Function

Passive Corium Cooling System

Preventing interaction between molten core and pressure-bearing materials of the containment

Emergency Reactor

Depressurization System

Preventing high pressure molten ejection

Containment Spray System

Preventing containment over-pressurization

Passive Hydrogen

Control System

Maintaining hydrogen concentration in containment below 10 v/o

Instrument System Monitoring status of plant condition

Electrical System

Supplying power to SAs dedicated systems by using battery and AACs

12


2 Compatibility for CzechNuclear New-Build

13


Major Equipment TransportationMain route for major equipment transportation to Dukovany/Temelin- Hamburg > Elbe (Labe) river > Týnec nad Labem > Dukovany

- Hamburg > Elbe (Labe) river > Vltava river > Tyn nad Vltavou > Temelin

General transportability of Major Equipment was confirmed during consultation meeting(’17.2)

Detailed transportation plan is being developed considering critical places such as bridge, steep/narrow road and required permit

[Route to the Dukovany Site] [Route to the Temelin Site]

* Limit - Length: 35m (APR1000 MSR 21.75m, SG 21.5m), Width: 8.5m (SG 6.2m), Height: 7.5m (SG 6.6m), Weight: 750t (SG 590t)

14


Compatability with Site Requirement

Open recirculating system with natural draft wet cooling tower

adopted in APR1000 complies with site requirement

Site NameItems Dukovany Temelin APR1000

Law water consumption, m3/year

50.0 mil. m3/year

33.5 mil.m3/year

25.9 mil.m3/year

Number of Tower 1/ unit 1~2/unit 1/unit

Height of Tower Lower than180 m

Lower than185 m 175m

15

APR1000 was developed based on EUR standard site condition and

Czech nuclear new build site condition can be satisfied without major

change


Major Milestone of the APR1000

The proposed construction schedule can be met thanks to the

standard construction technique and advanced design

16

2111 10

4 4 721

APR1400: 57 Months

EU Requirement: 60 Months

21 9 10 4 4 7

FC SET RV ENERGIZE CHT HFT FL Operation



APR1000(Target): 55 Months 16

2311 11

4 4 722


3Longterm Partnership With Czech Nuclear Industry

17


Longterm Partnership: Financing

18


Longterm Partnership: Localization

19

Localization Strategy (Engineering)

- Technical exchange program for technology familiarization

- Consulting with Czech engineering company for Czech requirement

(Major Equipment)

- Turbine to be supplied by Skoda Power

- Other major equipment to be supplied by Czech company under review

(BOP)

- Identified more than 150 suppliers for mechanic, electric, I&C etc

- Based on developed localization plan & identified suppliers, localization

to be enlarged and expanded

(Construction)

- Korean construction company to have cooperation with Czech

construction company for NPP construction


4 Closing Remarks

20


Closing Remarks

Highly reliable and proven design complying with the latest European

and site requirements in CR and through reference plant operation

Successful project implementation is assured through complete

construction readiness(transportation, site condition, schedule

analysis)

Partnership with Czech Republic through financial participation,

localization, win-win relationship with local community

21

KoreaCzech Longterm Cooperation

Copyright © 2018. All rights reserved by KHNP.2222

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November 7, 2018ners2018.jmm.cz/download.php?file=11_Kim_NERS_2018_ENG.pdf · materials of the containment Emergency Reactor Depressurization System Preventing high pressure molten