National Report on Nuclear Power Plant IC in the Republic of Korea

1. IAEA TWG-NPPCI MEETING May. 23 - 25, 2005, Vienna by Hang Bae Kim KOREA POWER ENGINEERING COMPANY, INC. National Report on Nuclear Power Plant I&Cin the Republic of Korea

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3. 3 NPP Overview(1) Nuclear Power Plants

4. 4 NPP Overview(2)

5. 5 NPP Overview(3)

6. 6 NPP Overview(4) Projection of Electricity Generation

7. 7 I&C Overview (1) I&C Programs (2003-2005) New Construction APR1400 MMIS (Shin-Kori 3&4) Core Protection System for OPR1000+ Research and Development KNICS (Korea Nuclear I&C System) Automatic Spec. and Code Generation Ultrasonic Flow Meter Upgrade I&C Upgrade Strategic Plan

8. 8 I&C Overview(2) 1st Generation: use of relay technology Implemented by various relays Kori unit 1: Reactor Protection Systems (RPS), etc. 1st upgraded with digital modules in Korea(1998) 2nd Generation: use of solid-state technology Implemented by analog Integrated Circuit (IC) chips Kori 2,3&4, Yonggwang 1&2, Ulchin 1&2: RPS, ESFAS, etc. 3rd Generation: use of hybrid technologies Implemented by microprocessor-based and relay components Wolsong 1,2,3&4, Yonggwang 3,4,5&6, Ulchin 3&4: RPS, ESFAS, PCS, etc.

9. 9 I&C Overview(3) 4th Generation: use of PLC-based computer technologies Implemented by digital PLC-based computers and software systems Ulchin 5&6, Shin Kori 1&2, Shin Wolsong 1&2: DPPS, DESFAS-AC, data communications, etc. 5th Generation: use of advanced HMI technologies Implemented by digital computers and software systems Integrating advanced human-system interfaces into main control room and remote shutdown stations Shin Kori units 3&4(APR-1400): DPPS, ESF-CCS, MCR, Soft Controls, Graphic Display Systems, etc.

10. 10 I&C Overview(4)

11. 11 New Construction (APR1400 MMIS) (1)

12. 12 New Construction (APR1400 MMIS) (2) Computer-based Advanced MCR Compact workstation Large Display Panel Safety Console Soft Control Fully Digitalized NSSS and BOP I&C Systems PLC for safety and DCS for non-safety I&C Systems Human Factors Engineering Verification & Validation Computerized Operating Procedures

13. 13 New Construction (APR1400 MMIS) (3)

14. 14 New Construction (APR1400 MMIS) (4) Block Diagram for APR1400 I&C Systems

15. 15 New Construction (APR1400 MMIS) (5) Dynamic Mock up

16. 16 New Construction (APR1400 MMIS) (6) Soft Control Template

17. 17 Core Protection Calculator (CPC) Overview Safety system for DNBR, LPD trip Four independent channels CEA signals shared between CPC and CEAC using fiber optic isolation devices Problems Obsolete hardware Difficult maintenance of software Implemented with assembly language Single point of failures Two channels of CEAC (actuated by ½ logic) Failure of signal Isolators (CEA input signals to CEAC) New Construction (OPR1000+ CPC) (1)

18. 18 Hardware and Configuration PLC for safety function Color flat panel display for operator’s module Network for intra-channel communication Serial data communication for inter-channel data sharing Software Function block structure Customized function blocks for PLC using C language Independent verification and validation of software Preliminary software hazard analysis Requirement traceability matrix Code review Module, unit, system integration testing New Construction (OPR1000 + CPC) (2)

19. 19 SYSTEM BLOCK DIAGRAM New Construction (OPR1000 + CPC) (3)

20. 20 R&D (KNICS) (1)

21. 21 R&D (KNICS) (2) Major Activities Development of digital systems and equipment Localization and licensing of safety-grade PLC and digital RPS and ESF–CCS Safety-grade software qualification Development of Control Rod Control System Localization for existing & next-generation NPPs Development of Distributed Control System Localization of hardware platform for monitoring and control systems for NPPs

22. 22 R&D (KNICS) (3)

23. 23 R&D (Software Tool) (1) Main Purpose Develop the methodology to generate the automated software design specification and source code for the nuclear I&C systems. Software Engineering Tools Integrated into the System Requirements management and traceability analysis tool Modeling and auto-code generation tool Object oriented compiler such as C++ and JAVA Code auto testing tool Configuration management tool

24. 24 R&D (Software Tool) (2) Overall Scheme

25. 25 R&D (Software Tool) (3) Prototype

26. 26 R&D (UFM) (1) Background Utility concerned the power derating since 1998 Derating : 20 – 40 MWe Fouling was presumed as main cause Needs for alternative method to measure the feedwater flow Main Purpose Develop the technology for adopting UFM in feedwater flow measurement in Korea NPPs Measurement accuracy : < ±0.6% Prepare topical report Support licensing

27. 27 R&D (UFM) (2) Activities Develop the technology for application of UFM in feedwater measurement Select UFM vendor Perform performance and reliability tests Measure feedwater flow in operating plants and verify applicability of UFM Verifying actual measurement uncertainty Perform analyses Effects of application of flow correction factor Calculations of uncertainty of reactor power Prepare topical report for UFM application

28. 28 R&D (UFM) (3) Flow Measurement Using UFM

29. 29 I&C Upgrade (Plan) (1) Objective

30. 30 I&C Upgrade (Plan) (2) Overall Flow

31. 31 I&C Upgrade (Plan) (3) Process

32. 32 Conclusion

33. 33 Suggestions