23rd iaea twg-nppic · bop controls npcs pp&lcs fwcs sbcs dps pcs rrs rpcs ... non-safety...

23rd IAEA TWG-NPPIC24-26 May 2011, Vienna

Hang Bae Kim (hbkim@kepco-enc .com)

1

Nuclear Safety

Brand Power Leading Role Financing Capability Global Experience

Leading CompanyRegulatory Body

LicensingInspection

Operation andManagement

Design and Engineering Nuclear Fuel Maintenance

and ServicesEquipment Manufacturing

Construction

Ministry of Education, Science & Technology

Research and Development

2

KNSKorea Nuclear

Society

1. Nuclear Industry in Korea1. Nuclear Industry in Korea

Four Units of APR1400 to be Constructed in UAE

Contract Award : Dec. 27, 2009

Completion : Unit #1 by May 1, 2017

Units #2,3,4 : 1 Unit / Year

3

Nuclear Power Plants Export

2. Nuclear Power Plant Status 2. Nuclear Power Plant Status

4

Nuclear Power Plants

Kori 1, 2, 3 , 4Shin-Kori 1, Shin-Kori 2, 3 & 4(Under Construction)Shin-Kori 5&6(Planned)

Wolsong 1, 2, 3 & 4Shin-Wolsong 1 & 2 (Under Construction)

Ulchin 1, 2, 3, 4, 5 & 6Shin-Ulchin 1&2

(Under Construction)

Yonggwang 1, 2, 3, 4, 5 & 6Yonggwang Wolsong

Ulchin

Kori

Seoul

Gyeongju

Radioactive Waste Disposal Facility

(under construction)

In Operation

Under Construction

Planned

21units(18,716 MW)

7units(8,600 MW)

2 units(2,800 MW)

5

21 NPPs supply 35- 40% of electricity

Construction Schedule (5th long term plan)

No. of Units

SWN 1&2SKN 1&2

UCN 5&6YGN 5&6

WSN 2,3&4UCN 3&4

YGN 3&4UCN 1&2

YGN 1&2KORI 3&4

KORI 1

‘72 ‘75 ‘78 ‘81 ‘84 ‘87 ‘90 ‘93 ‘96 ‘99 ‘02 ‘05 ‘08 ’11 ’14 ’18 ‘23

UnderConst-ruction

Opera-tion

SUN 1&2

SKN 3&4

SKN 5&6

PlanPWRPHWR

WSN 1KORI 2

28

20

9

3

TMI Chernobyl

6

Fukushima

SUN 3&4SKN 7&8

3438 NPPs supply 59% of electricity by 2030

7

World Best Operational Performance

1970s

Completion of First APR1400 (’13)

Units complete: 8 unitsFirst Unit complete

1980s 1990s 2000s

Units complete : 5 units

Units under construction:7 units

Units export (UAE) : 4 units

Introduction of Nuclear Power

TechnologyAccumulation

Developmentof OPR1000

Developmentof APR1400

Completion of Kori Unit1 (’78)

Completion of First OPR1000 (’95)

Units complete : 7 units

Nuclear Power Development

※ Source : KHNP

8

9

Nuclear Technology

Power : 1,000 MWeLife Time : 40 yearsConst. : 51 monthsSeismic : 0.2g



• Advanced multi-purpose small sizereactor- Electricity generation- Desalination

• Power : 330MWt

OPR1000Optimized Power

Reactor 1000

APR1400Advanced Power

Reactor 1400

APR+Advanced Power

Reactor plus

SMARTSystem-integrated

Modular Advanced ReacTor

3. Design Characteristics of APR1400 MMIS3. Design Characteristics of APR1400 MMIS

10

I&C System Design Features

Microprocessor based digital I&C technology- PLC platform for Safety I&C and DCS platform for Non-Safety I&C

Four (4) channel redundancy for Safety I&C

- Installed in separate channelized I&C equipment room

Multiplexed I/O and redundant communication network - From field areas to I&C equipment rooms and MCR

Diverse Actuation System to cope with the CMF of Safety I&C

Complete electrical, physical and communication isolation− Between redundant safety channels / between safety system and non-safety system

MCR Features

12

I&C System Overview

ProgramServer

GatewayServer

Control & Monitoring Network

QIAS-N(C, D)

Non-safety Components(Sensors, Txs, Pumps, Valves, etc.)

FIDAS NIMSALMSIVMSLPMS

RCPVMS

P-CCSBOP

Controls

NPCSPP&LCSFWCSSBCS

DPS PCSRRS

RPCSDRCS

Remote I/O

ICI Sensors

ENFMSStartup/Control

Safety

FissionChamber

Data LinkServer

Dedicated H/W switchesESFAS

InitiationRT

InitiationMinimumInventory

DMASwitches

DISQIAS-P

PPS/CPCS OM QIAS-N

Operator Console

Safety Console Large Display Panel

Protection System

PPS(4 Ch)

ESF-CCS(4 Ch)

QIAS-P(A, B)

CPCS(4 Ch)

Safety Components (Sensors, Txs, Pumps, Valves, etc.)

Channelized Safety Bus

MTP ITP

CIM

AlarmServer

DBServer

APC-S : Auxiliary Process Cabinet – Safety, CIM : Component Interface Module, CPCS : Core Protection Calculator System, DIS : Diverse Indication System, DMA : Diverse Manual ESF Actuation, DRCS : Digital Rod Control System, ENFMS : Ex-core Neutron Flux Monitoring System, FIDAS : Fixed In-core Detector Amplifier System, ICI : In-Core Instrumentation, NIMS : NSSS Integrity Monitoring System, NPCS : NSSS Process Control System, OM : Operator Module, P-CCS : Process Component Control System, PCS : Power Control System, QIAS-P/N : Qualified Indication & Alarm System - PAMI / Non-safety

APC-S(4 Ch)

DIS

SafetySoft Control

Non-safetySoft Control

Ch. ConfirmSwitches

Control & Monitoring System

APC-S

Common platform for Safety I&C

Common platform for Non-safety I&C

Dedicated equipment for its function

Computer server, monitor & peripherals

Conventional H/W components

Legend

Safety related networkNon-safety networkHardwired Connection

Protection System Overview

DPS (2 CH)

MG set

DRCS

RTSS

PPS (4 CH)

Dedicated Safety Sensors (4 channels)

ESF-CCS (4 CH)

S

ESF Actuation Signals

ESFAS Initiation Signals

Ch A Ch B Ch C Ch D

Ch C Ch D

RT Initiation Signals AFAS

Ch BCh A

Ch N1 Ch N2

RT

ENFMS(4 CH)

CPCS(4 CH) S Non-safety Sensors

(2 channels)

C A

D B

M

MG

G

480 Vac139/240 Vac

AFAS : Auxiliary Feedwater Actuation SignalDRCS : Digital Rod Control SystemENFMS : Excore Flux Monitoring SystemRTSS : Reactor Trip Switchgear System

N2

N1

Soft Control Overview

Non safetySoft Control

PCS NPCS P-CCS

P-CCS FPDs

Control & Monitoring Network

SafetySoft Control

CCG

ESF-CCS

CPM

Soft Control Network

A B C D

Ch. Confirm Switches

ESF-CCS FPDs

PPS

Channelized Safety Bus

Hardwired

CPM : Control Panel MultiplexerCCG : Control Channel Gateway

Serial Data Link

ESF-CCS CIM

Rx Trip on High Containment Pressure

ESF components

Position 4 Display

CPM

ESFASInitiation

RTInitiation

MinimumInventory

DMASwitch

DISQIAS-PPPS/CPCS

OM QIAS-N

Safety Console

Dedicated H/W switches

PPS

DPSAFAS

Isolator

DMA : Diverse Manual ESF Actuation

MG set

RT

APC-S

RTSS

Provisions to cope with CCF

CPM : Control Panel Multiplexer

CIM : Component Interface Module

Protection & Control System Platforms

PLC for Protection System (POSAFE-Q by POSCO-ICT)

DCS for Control System (EXOS by WOORI)

17

4. Major I&C Modernization Projects4. Major I&C Modernization Projects

18

1. Rod Control System (RCS)2. Diverse Protection System (DPS)3. Automatic Seismic Trip System (ASTS)4. Excore Neutron Flux Monitoring System (ENFMS)5. Main Control Room (MCR)

19

- Old system supplied by Westinghouse in 1978 and 1983- New system supplied by KEPCO-E&C and Doosan- Project period : 2008. 3 – 2011. 6

1. Rod Control System (KORI 1&2)

Replacement : Maintain :

RCU : Reactor Control Unit, PAS : Plant Annunciator System PCS : Plant Computer System, BIM : Bank Insertion Monitor

Logic Cabinet Power Cabinets

MG-Set

Power Cables

RCU, PAS, PCS, BIM(*)

Lift Coil Disconnect SW

CRDM

MCB MMI


21

1. Rod Control System (KORI 1&2)Old Cabinets MCB

New Cabinets

22

1. Rod Control System (KORI 1&2)Rod Control Display Cabinet MTP Display

Digital Modules

23

Disconnect cables Remove modules Remove old cabinet

Install channel base Install new cabinet Connect cables


Dismantling and Installation

2. Diverse Protection System (OPR1000)

24

- Objective• To replace PLC-based DPS with FPGA-based DPS

- Project scope• To design and install FPGA-based DPS Cabinet Assembly for

OPR1000 (8 units)

- Project schedule • 2011. 3 – 2015. 3

- Contract participants• Plant Owner : KHNP• System Designer : KEPCO E&C• Supplier : To be determined later


25

- DPS Block Diagram & ReplacementReplacement

PROCESSSENSORS

PZRPRESS

CNTPRESS

SGLVL

TURBINETRIP

ENABLE

MANUALREACTOR

TRIP

TRUBINETRIP

INPUT

120 VacVITAL

POWER

ANALOGINPUT

DISCRETEINPUT

POWERSUPPLY

PROGRAMMABLE

LOGIC

CONTROLLER

OPERATION&

TEST

DPS CABINET

DISCRETEOUTPUT

ANALOGOUTPUT

INITIATIONCIRCUIT

INDICATORSON MCB

MG SET

PLANTCONTROLSYSTEM

PDAS

VALVE&

PUMP

PLANTANNUNCIATOR

SYSTEM

* U5&6 only


26

DPS CABINET

CHANNEL N1

CHANNEL N2

FLAT PANEL DISPLAY

P/S N1 P/S N2

Cabinet Assembly by Supplier

Display Programming by KEPCO E&C

FPGA Programming by KEPCO E&C

3. Automatic Seismic Trip System

27

1. Objective• Trip the reactor at severe seismic event• Enhance the safety of NPP and improve public acceptance

-Project scope• Design and install ASTS for all operating NPPs

• Project schedule • 2009. 9 – 2013. 1

• Hardware• Non-safety grade, Seismic class I• 2 channel 2 out-of 2 energized actuation


28


29

TRIP LOGIC CHANNEL N1

TRIP LOGIC CHANNEL N2

30

4. ENFMS Improvement (UCN 1&2)

- 950 MWe PWR supplied by Framatome in 1983- Project period : 2009.2 – 2012.7

ENFMS(Ex-core Neutron Flux Monitoring System)

To measure reactor power level by monitoring the neutron flux leakage from the reactor vessel

Purpose of improvement project Lower drift and higher reliability by upgrading the old system

Cost savings by means of the reduced inventory of spare parts

The use of single type detector (Fission Chamber)

No replacement of detectors for the lifetime of the plant

B10 for SR and IC for IR are required to replace due to the limited life time

New FC detectors have a 40-year design life

31


32


33

Now To be

The use of signal type of detector SR : B10 FC / IR : CIC FC (SR and IR shares the detector (FC)) PR : UIC FC

The configuration of detector assemblies


5. MCR Upgrade (KORI 1)

34

- Plant • 587 MWe PWR supplied by Westinghouse in 1978• life extension from 30 to 40 years in 2008

- Project scope• replace all MCR equipment • HSIs improvement required by PSR (periodic safety review)

- Project schedule • phased upgrade : 2006. 5 – 2013. 9

- Feasibility study• recommended hybrid type MCR

35

MCR Layout


36

Hybrid MCBNow To be



37

Upgrade Scope

Reduction of numberof Alarm tiles

Compliance toHF guidelines

BISI

New Cable Terminal Board

Recorders IndicatorsSwitch

Standardization M/AStations

Improvementof cable terminals

PlantComputer

Reduction of cables

Needs

Req’t

Review

New :

Advanced:

Present :

Alarm System

VDUs

SafeguardCabinet

ProcessControlCabinet

MCC/SWGR/ETCESFAS

GovernorControlCabinetBISI

Cabinet

MGovernor

Component

OACS

System Integration

PSR Action

ReactorProtection

Cabinet


38

Switch Recorder Indicator

Now

To be


39

Now (Conventional)

To be (Hybrid)

MCR End Point Vision

5. Recommendations5. Recommendations

40

1. Licensing requirements for automatic seismic trip system2. Application of universal (safety+control) soft control3. Harmonization of licensing requirements and process4. Safety critical software development methodology5. Application of new technology (FPGA, wireless …)

End of presentation

23rd iaea twg-nppic · bop controls npcs pp&lcs fwcs sbcs dps pcs rrs rpcs ... non-safety...

Documents