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1 [2010 동남권 IT 컨퍼런스, 울산 ] 원전 MMIS 와 IT 융합기술 권기춘

2 목차 서론원전 MMIS 원자력-IT 융합결론 2

3 서론 - 원자력발전소현황 NPP in Operation NPP under Construction NPP in Planning 울진 # 1, 2, 3, 4, 5, 6 싞울진 #1, 2 월성 # 1, 2, 3, 4 싞월성 #1, 2 영광 # 1, 2, 3, 4, 5, 6 고리 #1, 2, 3, 4 싞고리 #1, 2, 3, 4 싞고리 #5, 6 3

4 원전계측제어와 MMIS 원전계측제어 (I&C) 원전의두뇌와싞경망에해당 계측, 제어및보호, 감시기능담당 MMIS (Man-Machine Interface System) = I&C + MMI + HFE Instrumentation & Control (I&C: 계측제어 ) Man-Machine Interface (MMI: 주제어실 ) Human Factors Engineering ( 인갂공학 ) 4

5 원자력 IT 차별성 규제요건 외부홖경으로방사선누출과내부의방사선피폭을방지또는제핚하는최소핚의설계기준제시 자동 / 수동원자로정지 공학적안전설비 (ESF) 자동 / 수동조치및제어 디지털안전계통의상태및기능에대핚지속적인정보표시 규제개념 단일고장기준 (Single Failure Criteria) 다중성 (Redundancy) 공통모드고장 (Common Mode Failure) 심층방어 (Defense-in-Depth) 다양성 (Diversity) 5

6 원전 MMIS 원전계측제어시스템 (KNICS) 개발사업목표 원전디지털계측제어시스템개발및실용화 감시및운전지원기술개발로미래기술기반확보 사업종료시점에세계 3 강지위확보 AREVA, Westinghouse, KNICS 사업기갂 : ~ (7 년 ) 참여기관 : 원자력 ( 연 ), 전기 ( 연 ), 두산중공업, 포스코 ICT, 우리기술, 핚국전력기술 (KEPCO E&C), 우진, 학계 적용 APR1400 ( 싞울진 1&2 호기 - 상업운전 : 2015/2016) 적용위핚디지털계측제어시스템 가동원전노후화계측제어설비교체 6

7 원전 MMIS 개발완료 7

8 RSP EOF TSC RWC Safety Console LDP Controller APR1400 I&C Architecture Control Network VDU/Soft Controller Operation Device Network PPS/CPC Op. Module ESF-CCS Soft Controllers QIAS-P QIAS Network RO & TO Console CRS/SS/STA Console Information Network-Fast Ethernet 100Mbps VDU/Soft Controllers DBMS Alarm Serve r IPS CPS LDP Controller EWS & Other I/O Unit Level System Level Control Network-Ethernet Token 100Mbps ICCMS Digital signal Acquisition A/D Conversion Digital Signal Acquisition ESF-CCS Ch-A Safety Network Inter-ch. Profibus 12Mbps Reactor Protection Ch-A Safety Network Inter-ch. Profibus 12Mbps Field Network Profibus 6Mbps Safety Network Inter-ch. Profibus 12Mbps RCOPS Ch-A Field Network Profibus 6Mbps Power Control System RRS CEDMCS RPCS Field Network E-T 10Mbps NSSS Control System FWCS SBCS APS Field Network E-T 10Mbps NSSS Component Control PPCS PLCS CVCS Field Network E-T 10Mbps Electrical System Control Field Network E-T 10Mbps BOP Control System T/G & Protection Field Network E-T 10Mbps BOP Sys Component Control AUX. SYS. HVAC CCS Field Network E-T 10Mbps Gas Stripper Boronometer PRM RCPSSSS Digital Signal Acquisition A/D Conversion Digital Signal Acquisition NSSS Integrity Monitoring ALMS LPMS RCPVMS IVMS Process Process Conditioning Process Conditioning Conditioning ENFMS _A ENFMS _A ENFMS _A ENFMS _A Reactor Trip Switchgear Automatic Power Electronics Electrical System Logic Local Bus Generator & Transformer Protection To Control Systems Process Process Conditioning Process Conditioning Conditioning Local Level KNICS Scope Plant Field 8 : Multiplex Data Highway (Multi-drop) : Multiplex Data Link (Point-to-point) : Hard Wired

9 안전등급제어기기 (PLC) PLC: Programmable Logic Controller 디지털안전계통플랫폼 주요개발내용 프로세서모듈 통신모듈 (HR-SDL, HR-SDN, FMS) 입출력모듈 16 종, 버스확장모듈 2 종 응용프로그램개발도구 : pset 9

10 PLC 소프트웨어 Agent RTOS (pcos) Driver Network Interface Firmware Engineering Tool CPU Module Comm. Module I/O Modules Editor Compiler Linker 10

CHANNEL D TR TR COM TR TR COM TR TR COM TR TR COM BP 1 BP 2 ATIP BP 1 BP 2 ATIP BP 1 BP 2 ATIP BP 1 BP 2 ATIP CP 1 CP 2 CP 1

11 디지털원자로보호계통 이상상태감지하여원자로를안전하게정지 PLC 플랫폼을기반으로응용소프트웨어개발 Configuration of Single Channel Two Bistable Processors (BPs) Two Coincidence Processors (CPs) Automatic Test & Interface Processor (ATIP) Operator Module (COM) CHANNEL A CHANNEL B CHANNEL C CHANNEL D TR TR COM TR TR COM TR TR COM TR TR COM BP 1 BP 2 ATIP BP 1 BP 2 ATIP BP 1 BP 2 ATIP BP 1 BP 2 ATIP CP 1 CP 2 CP 1 CP 2 CP 1 CP 2 CP 1 CP 2 INIT. LOGIC INIT. LOGIC INIT. LOGIC INIT. LOGIC TRIP-A TRIP-A TRIP-A TRIP-A A B C D A B C D A B C D A B C D 11

12 공학적안전설비 - 기기제어계통 원자로정지시사고완화설비 PLC 플랫폼을기반으로응용소프트웨어개발 삼중화 GC( 그룹제어기 ): Improvement of safety and operability 이중화 LC( 루프제어기 ) 채택 온라인자가진단과자동시험기능강화 디지털기기의공통유형고장에대비한공학적안전설비수동작동기능보유 안전통신망적용 LC1 LC2 LC3 LC4 ETIP COM GC1 GC2 GC3 CCG 12

13 원자로노심보호연산기계통 RCOPS: Reactor COre Protection System PLC 플랫폼을기반으로응용소프트웨어개발 알고리즘개선 ( 운전여유도개선, 가변과출력정지방지, 예비정지경보추가, 제어봉위치오신호처리방법개선 ) 13

14 안전 - 필수소프트웨어개발및검증 원전안전 - 필수소프트웨어 원전안전등급계측제어계통 ( 예 : 원자로보호계통 ) 에탑재 (embedded) 되어운용되는소프트웨어 실행중오동작시막대한인명, 재산, 또는환경피해를초래하는소프트웨어 엄격한규제요건하에서개발 안전 - 필수소프트웨어개발프로세스확립 기술, 조직, 책임, 권한및재정적으로독립된소프트웨어검증프로세스가필수적임 소프트웨어안전성분석 심층방어및다양성 (Defense-in-Depth & Diversity) 개념적용 정형명세및정형검증기법도입 14

15 소프트웨어개발프로세스 Life Cycle Activity Groups Planning Activities Requirements Activities Design Activities Implementation Activities Integration Activities Validation Activities Installation Activities Operation & Maintenance Activities Software Management Plan Requirements Specification Design Specification Code Listings System Build Documents Operations Manuals Software Development Plan Software QA Plan Hardware & Software Architecture Installation Configuration Tables Integration Plan Installation Plan Maintenance Plan Training Plan Operations Plan Maintenance Manuals Training Manuals Design outputs Process implementation Software Safety Plan Requirements Safety Analysis Design Safety Analysis Code Safety Analysis Integration Safety Analysis Validation Safety Analysis Installation Safety Analysis Change Safety Analysis Software V&V Plan V&V Requirements Analysis Report V&V Design Analysis Report V&V Implementation Analysis & Test Report V&V Integration Analysis & Test Report V&V Validation Analysis & Test Report V&V Installation Analysis & Test Report V&V Change Report Software CM Plan CM Requirements Report CM Design Report CM Implementation Report CM Integration Report CM Validation Report CM Installation Report CM Change Report Process planning 15 Source: NUREG-0800

16 안전 - 필수적용기술기준및표준 10CFR 50.55a(h) (Safety sys. criteria) IEEE 603 (Safety sys.) RG CFR 50 App. A (GDCs) ANSI/IEEE RG CFR 50 App. B (QA) Codes IEC (General req.) LCP RG 1.28 (QA) RG (Development of LCP) IEEE (Life cycle Process) (CM guideline) (Quality metrics) (Risk management) Planning RG (CMP) (QA plan) (Manag. plan) (Safety plan) (CM plan) Standard Review Plan NUREG-0800 (Ch. 7 & BTP-14) Req. spec. RG (Req. spec.) (Req. spec.) Design(Coding) (Design Spec.) V&V RG (V&V, audit) RG (Test docum.) RG (Unit test) (Unit test) (Test docum.) (V&V) (Review&Audit ) Installation (Maintenance) Etc. Regulatory Guide 982.1& (SW Measures) (Anomalies class) (Reliability anal.) (Application guide) IEC (Safety S/W) IEC (Category B,C S/W) KEPIC Industrial Code & Std (QA plan guideline) (Design spec. gl) (V&V guideline) (Reliability anal.) NUREG/CR-6101 NUREG/CR-6880 NUREG/CR-6463 NUREG/CR-6421 EPRI NP-5652 (COTS Guideline) EPRI TR (Digital COTS evaluation) Guidance 16

17 비안전제어기기및제어계통 DCS: Distributed Control System 비안전제어계통을위한플랫폼 주요개발내용 주어진시간주기의결정론적제어 규모별확장성제공 : 소규모, 중규모, 대규모 강력한구성 / 로직 /MMI 도구제공 제어망과정보망의분리 이중화및연속운전 : CPU, I/O, 전원, 통신망, 데이터포함하는다중고장대처개념채택 Windows XP 운영체제및상용 Tool (ISaGRAF, ifix, ProSee 등 ) 채택으로로직, 화면처리용이 Power Control System CEDMCS: Control Element Drive Mechanism Control System RPCS: Reactor Power Cutback System RRS: Reactor Regulating System 17

정보통신망 Fast Ethernet switch 단자대및 Terminal Block 즉각적인연결확인및간편한배선 PDU: Power Distribution Unit 입력 :

18 DCS: Hardware 본체, Fan, 단자대등으로구성됨 제어기 (FCU: Field Control Unit) 기능 구성모듈 IO 데이터수집및처리 제어로직수행 CPM Module IO Module Power Module 규격 : 19 인치 x 6U 제어통신망 CSH( 중앙교환기 ), GSH( 그룹교환기 ), LSH( 현장교환기 ) 정보통신망 Fast Ethernet switch 단자대및 Terminal Block 즉각적인연결확인및간편한배선 PDU: Power Distribution Unit 입력 : AC110/220, 50/60Hz 출력 : DC48V(600W), DC24V(300W), DC12V(300W) 과전압 / 과전류보호회로및 Surge Protection 기능 18

19 DCS: Software System Builder EWS (Engineering Work Station) Graphic Builder Report Builder Logic Builder HDS (History Data Server) History Server Event Server Alarm Server OIS (Operator Information Station) System Config. Info. Tag/Graphic Info. ISaGRAF TM RDBMS 19

Monitoring System Qualified Indication and Alarm System- PAMI ICCMS 기능과 PAMI Reg. Guide 1.97 Category 1 변수표시 노심출구온도감시 원자로냉각재수위감시 냉각재포화여유도감시 RG 1.

20 Monitoring System Qualified Indication and Alarm System- PAMI ICCMS 기능과 PAMI Reg. Guide 1.97 Category 1 변수표시 노심출구온도감시 원자로냉각재수위감시 냉각재포화여유도감시 RG 1.97 Category 1 Qualified Indication and Alarm System- Non Safety 정상운전과사고상황시운전원에의해사용되는비안전계통관련주요핚운전파라메터감시 정보처리계통 (IPS) 에대핚다양성계통 Ch.A Ch.B 계통화면예 PAMI: Post Accident Monitoring Instrumentation ICCMS: Inadequate Core Cooling Monitoring System 20

21 Computerized Procedure System Monitor Pane Overview Pane Operation Procedure Plant Information Related Display Desk Pane 21

통합성능검증설비구조 Large Display Panel HSI in MCR

Full-scope Simulator I/O Interface Real-time

22 통합성능검증설비구조 Large Display Panel HSI in MCR Information Processing System Safety Console Control and Monitoring Network I/O Interface PLC Dummy Load DCS Dummy Load APR1400 Full-scope Simulator I/O Interface Real-time Executive Instructor Console Mathematical Modeling 22

23 통합성능검증설비 Tested prototype APR1400 Simulator APR1400 Simulator Safety console 23

24 하드웨어플랫폼 원자력 -IT 융합 하드웨어중심의 IT 산업세계최고수준 반도체, 디스플레이, 이동통싞단말기 원전 MMIS 국산화, 세계 3 강수준 PLC: Programmable Logic Controller DCS: Distributed Control System 소프트웨어, 컨텐츠분야 UAE 원전수주이후원자력 -IT 융합에큰관심 세계적글로벌경쟁력확보위해서는원자력 -IT 융합기술기반핚소프트웨어, 컨텐츠분야의원천 / 핵심기술개발필요성대두 우리의강점 IT 기술을원자력과융합세계기술선도 24

25 원자력 -IT 융합 대용량통싞망, Middleware Wireless technology 원전 ( 운전 ) 정보 스마트폮 운전요원, 규제요원 USN/RFID 원전운영요원위치추적, 자재 monitoring, 카메라이용이상상태파악, 핵물질이동추적 / 감시 25

26 원자력 -IT 융합 Virtual reality/augmented reality 가상현실시뮬레이터 Cyber security ( 26

27 원자력 -IT 융합 Data Mining: 진단시스템 DB NIMS(NSSS Integrity Monitoring System) Acoustic leak, Loose part monitoring Reactor Coolant Pump vibration monitoring 인공지능 (NN, HMM, GA) 패턴인식 기기또는프로세스이상진단 원전설계. 사업관리. 정보관리 3D기반설계시스템 수명주기통합정보관리시스템 프로젝트성과관리시스템 공급자통합자원관리시스템 27

28 원자력 -IT 융합 Web services Computational platforms: SoC, ASIC, FPGA Knowledge management: Ontology 실시갂시뮬레이터 (Real-time simulator) Software dependability 추적 : 요구사항명세 시스템테스팅 정형검증 Quantification of Software reliability BBN-Method (Bayesian-Belief-Network) 28

29 Middleware 원자력 -IT 융합 하드웨어플랫폼변경시에도응용 SW 홗용 정보. 통싞의고속도로역핛 29

30 원자력 -IT 융합 Conventional Alarm System Moderator Level AbnormalPL5-2 PZR Press Lo PZR Level Hi PZR Level Lo Alarm 경보원인추적시스템 RCS Temp Hi Valve 3211-PV32 Open Automated display of Logic diagram and Alarm procedure Alarm Cause Tracking System 30

31 원자력 -IT 융합 Cyber security 사이버보안취약성분석 IT 보안기술원전적용 Profibus-FMS 2 Plant 감시체계 (Ethernet) 3 UDP 6 디지털원자로보호계통 3 원격관리프로그램, 콘솔 4 COM (QNX) 5 BP 내부인가자 RS-232C 1 ATIP CP 내부비인가자 31

원자력 -IT 융합 Use of IT technology in the assessment process of application software Functional requirements Formal Verification cmp_code, rediff RETRANS etc.

32 원자력 -IT 융합 Use of IT technology in the assessment process of application software Functional requirements Formal Verification cmp_code, rediff RETRANS etc. Test Field Specification FBD LD Code generation TXS C code Compiling Loading check Validation by SIVAT System Engineer I&C Engineer Engineering system SPACE Target System 32

33 결론 원전 MMIS 국산화개발및싞울진 1,2 호기적용 UAE 원전수출프로젝트성사로원자력관심 우리의강점인 IT 를원자력과융합 : 명품원전 국산화 MMIS 하드웨어플랫폼을기반으로 IT 기술융합 최첨단 IT 기술의융합으로원자력분야 Cutting edge 역핛 IT 기술을원전설계, 엔지니어링, 건설, 운영, 유지ㆍ보수및원전폐기물처분등원전수명주기에적용 수출및원전선진국과의경쟁시우위확보 33

Microsoft PowerPoint - KNS 기술정보회의(070405)-김창회

Microsoft PowerPoint - KNS 기술정보회의(070405)-김창회 디지털계측제어계통의 PLC 설계방향 2007. 4. 5 원자력연구소 김창회 -1- Table of Contents 안전등급 PLC (POSAFE-Q) 특징 POSAFE-Q 제공모듈들 POSAFE-Q 설계기준 POSAFE-Q 설계방법및절차 POSAFE-Q 시험종류및절차 완제품제작과정 분석보고서 3자검증결과 TR 작성 결론 -2- 안전등급 PLC (FOSAFE-Q)