Country Report. I&C application status in NPPs in China. Wang Yanjun. Jiang Hong, Tang Yi IAEA TWG NPPIC 25 rd Meeting, Vienna, May 27, 2015.

Transcription

1 Country Report I&C application status in NPPs in China Wang Yanjun Jiang Hong, Tang Yi IAEA TWG NPPIC 25 rd Meeting, Vienna, May 27, 2015.

2 Contents 一 二 3 三 Status of nuclear power plants in China Introduction of I&C design and implementation in NPPs Recommendations to IAEA

3 Contents 一 二 3 三 Status of nuclear power plants in China Introduction of I&C design and implementation in NPPs Recommendations to IAEA

4 NPPs distribution in China Fangchenggang NPP

5 NPPs in commercial operation Projects Province Total Capacity (MW) C.O Qinshan Ⅰ(unit 1) Zhejiang 1x Qinshan Ⅱ (unit 1,2) Zhejiang 2x /2004 Qinshan Ⅱ ext.(unit 3,4) Zhejiang 2x /2012 QinshanⅢ(unit 1,2) Zhejiang 2x700(CANDU) 2002/2003 Tianwan Ⅰ(1,2) Jiangsu 2x1000(VVER) 2007 Daya Bay (1,2) Guangdong 2x Lingao Ⅰ(1,2) Guangdong 2x /2003 Lingao Ⅱ(3,4) Guangdong 2x /2011

6 NPPs in commercial operation Projects Province Total Capacity (MW) C.O Hongyanhe(unit 1,2,3) Liaoning 3X /2014/ Ningde(unit 1,2,3) Fujian 3X /2014/ Yangjiang(unit 1,2) Guangdong 2X / Fuqing (unit1) Fujian Fangjiashan (unit 1,2) Zhejiang 2x /2015./1

7 NPPs under construction Projects Province Total Capacity (MW) FCD Hongyanhe(unit 4-6) Liaoning 3X Ningde(unit 4) Fujian Yangjiang (unit 3-6) Guangdong 4x Fangchengang Guangxi 2x Taishan(unit 1,2) Guangdong 2x1700(EPR) Fuqing(unit 2-4) Fujian 3x Changjiang (unit 1,2) Hainan 2x Sanmen I(1,2) Zhejiang 2x1250(AP1000) Haiyang(unit 1,2) Shandong 2x1250(AP1000) Rongcheng(HTR-PM) Shandong 200(HTR-PM) Tianwan Ⅱ(3,4) Jiangsu 2x Fuqing(unit 5-6) Fujian 2xACP1000(HL)

8 China NPPs development process Imported units: Dayabay 1/2 lingao 1/2 Self-development: Qinshan II 1/2 CNNC selfdevelopment 600MW PWR Qinshan Ⅱ 1/2 Self-reliance: Qinshan II 3/4, Lingao Ⅱ Hongyanhe Ningde Fangjiashan Fuqing Yangjiang Self design and localized equipments manufacturing, Standardized, series, DCS, Improvement in safety and economics. Self-Innovated PWR: CP1000 New design on reactor core and system based on 10 years R&D, 177 fuel assemblies single unit layout and double containments, etc (CDF < /y, LERF< /y) Further Improvement in safety & economics. Imported Gen Ⅲ: AP1000, EPR Advanced reactor design, Passive safety technology Severe accident prevention and mitigation technology Single unit layout Double containments Prevent aircraft hazards Gen Ⅱ Gen Ⅱ+ Gen Ⅱ++ Gen Ⅲ Self-develop: ACP1000 ACPR1000 (HL) CAP1400 Adopt new Gen Ⅲ NPP design philosophy Comply with latest code and standard requirement, Take into account all improvement after Fukushima accident Active and passive safety measures Proven and Reliable tech. and equipment.

9 ACP1000 Active & Passive Advanced PWR A safe, reliable technology with economic competitiveness Evolutionary design based on proven technology Satisfying the latest nuclear safety codes and standards Fulfilling the utility requirements for advanced light water reactor Integrating the feedback of Fukushima accident

10 ACP1000 Active & Passive Advanced PWR 3 rd Generation PWR Satisfying latest nuclear safety codes and standards with advanced technology 3 Design Features 177-fuel-assembly core Single unit layout Double shell containment 3 Active + Passive Systems Residual heat removal from secondary side Containment heat removal Cavity injection and cooling 3 Enhanced Protection Capabilities against Seismic Commercial aircraft crash Plant emergency

11 Post-Fukushima Improvements Emergency water makeup and power supply Flood Protection Spent fuel pool monitoring and cooling Extension of nonintervention period Radiation environmental monitoring and emergency response Severe accident hydrogen concentration monitoring Habitability and availability of emergency facilities

12 IAEA Safety Review ACP1000 Active & Passive Advanced PWR December 2013, CNNC and IAEA signed agreement on Generic Reactor Safety Review (GRSR) of ACP1000 May 2014, CNNC delivered ACP1000 Reactor Safety and Environmental Analysis Report (over 4000 pages) to IAEA IAEA review panel composed of 13 experts from 7 countries two rounds of face-to-face exchange and communication between CNNC experts and IAEA review panel December 2014, ACP1000 accomplished GRSR

13 Demonstration project of ACP1000 Fuqing 5,6 will be the demonstration project of ACP1000 Fuqing 1,2 Fuqing 3,4 Office area Fuqing 5,6: Authorized for pre-phase work in April 2009, ACP1000 demonstration project after Fukushima, NEA approving HL-1 deployed in Fuqing Unit 5&6 on Nov. 3,2014 FCD : 2015/5/7 Rendering of Fuqing NPP site

14 CAP1400 Passive NPP One of the National Science & Technology Key Projects approved by the State Council. Self-developed large Passive NPP with Own IPR, ~1500MWe (gross). Better safety and economic performance, improved environment harmonization and more convenience of O& M. Standard Design, fulfilling with the advanced safety standards.

15 CAP1400 Passive NPP Compact, integrated and advanced Control Room Research Objective Integrate Human Factors Engineering principles. Provide advanced Human- System Interfaceresources under a well designed operation concept: Wall Panel Information Displays Soft Controls Dedicated Switches Alarm System Computerized Procedure Nuclear Application Programs

16 HTR-PM Project FCD: May 2012 Features: inherence safety, economic viability, high efficiency in power generation and fuel utilization. Ball fuel production line construction in March 2013 Key technology provided by the Institute of Nuclear and New Energy Technology (INET) of Tsinghai University Full scope digital control system and reactor protection system with localized platform Full scope simulator for MCR design and validation.

17 ACP100 SMR ACP100 Main Design Characteristics(1/2) Integration Canned motor primary pump connected to RPV once-through type steam generator Integrated reactor head package design Passive Passive core cooling system Secondary passive residual heat removal system Containment passive heat removal system Severe accident prevention and mitigation measures Passive reactor cavity flooding system Passive hydrogen recombiner system Primary side automatic depressurization Reactor top vent system

18 ACP100 SMR ACP100 Main Design Characteristics (2/2) Diverse Application Easily connected to small and medium sized power grid Urban Regional Heat Supply (Co-production of heat and power ) Industrial Process heating (Co-production of steam and power ) Seawater Desalination(Coproduction of water and power) Demonstration Project : Capacity: 2 100MWe nuclear power unit, co-generation of electricity, steam and water. The site is located at Putian City, Fujian province. Prepare Generic Reactor Safety Review (GRSR) of ACP100.

19 Contents 一 二 3 三 Status of nuclear power plants in China Introduction of I&C design and implementation in NPPs Recommendations to IAEA

20 ACP1000 I&C Design As the nerve system of NPP, ACP1000 I&C design is consistent with the whole plant design goals and philosophies: Latest code and standard requirement Active and passive design philosophy Complete SA prevention & mitigation measures Single unit layout Double containment shell Improved configurations of engineering safety features Reinforced protection against external hazards Feedback from Fukushima accident etc. 20

21 Defense in Depth ACP1000 design follows the defense in depth requirement in HAF which is technically equivalent with IAEA NS-R-1 Safety of Nuclear Power Plants: Design. In HAF102, five levels of defense are required for preventing accidents and ensuring appropriate protection in the event that prevention fails. Beside the fifth level which is for on-site and off-site emergency response, I&C system design will cover the first to fourth level of defense. Control system Protection system/reactor trip and PAMS Diverse protection system/reactor trip and boron injection Protection system/esfas and PAMS Diverse protection system/esfas Severe accident monitoring instrumentation Severe accident related control system LEVEL I LEVEL II LEVEL III LEVEL IV 21

22 Overall architecture 22

23 CAP1400 I&C Design Architecture Distributed I&C Configuration DAS Panel Dedicated Safety Panel Wall Panel Operator Console (MCR) Operator Console (RSR) Local Control Stations HSI Level High speed network Network Level Diverse Actuation & ATWS Function Protection and Safety Monitoring Function Plant Control Function Other Functions Process Level Filed Equipment Plant Interface Level

24 CAP1400 I&C Design Function Assignment Safety Function Protection and Safety Monitoring System Diverse Actuation & ATWS Function Control & Information Function Diverse Actuation System Plant Control System Data Display and Processing System Operation and Control Centers System (Note) Other Functions Main Turbine Control & Diagnostic System In-core Instrumentation System Radiation Monitoring System Special Monitoring System Seismic Monitoring System NOTE: The OCS also contains Class 1E HSI. Earthquake scram system

25 CAP1400 I&C Design Digital I&C Systems Reliability Analysis and Assessment Qualitative and Quantitative Reliability Analysis of Digital I&C Risk-informed Assessments of Digital I&C Plant Reliability/ Availability Goals distribute satisfy Cyber Security for Digital NPP Cyber Security Strategy Cyber Security Risk Analysis Cyber Security Controls Plant Security Management and Operation I&C Systems Reliability/ Availability

26 CAP1400 I&C Design Human Factors Engineering Comply with NUREG-0711, Rev.3 Operating experience review on domestic/international sources and very recent cases Function-based task analysis and operational sequence analysis, Expanded engineering tests Design verification along with the full process of HSI design Intelligent Diagnostic System Oriented for Operational Safety and Performance of Digital NPP Operation Support Systems Diagnostic and Prognostic Technologies for Equipments Operational Status Plant Operational Safety and Performance Monitoring Accident Consequence Analysis Emergency Response/Decision

27 HTR-PM Protection system Digital protection system dedicate developed for HTR-PM; Software has been strictly V&V; Full scale engineering prototype has been passed through qualification test in July of 2014; It s the first digital protection system used for NPP by domestic company. HTR-PM Process control system Domestic company s platform; Including reactor power control, NI and CI process control, etc.; INET has finished all critical control logic validation. HTR-PM Computer based MCR INET has finished the Mutil-mudules control room and HMI design; INET has finished engineering prototype manufacture and HSI validation.

28 Series of Products Series 1: Nuclear Digital Control System(DCS) NicSys 2000: Non-Safety platform ofnuclear power plants digital control system platform With the application of cage-type structure, NicSys 2000 incorporates with the latest large-scale networking technology, field-bus technology and field management techniques. It meets the requirements of high reliability and high security in nuclear engineering. NicSys 8000N: FPGA based Safety platform ofnuclear power plants digital control system platform CNCS China Nuclear Control System Engineering Co., Ltd.

29 CNCS China Nuclear Control System Engineering Co., Ltd. Series of Products Series 2: Specific I&C System for Nuclear Power Plant Series 3: Nuclear Detectors Series 4:General Nuclear I&C Instruments Neutron Ionization Chamber Scintillator Detector Semiconductor Detector Sodium Iodide Detector Thermo luminescence Detector Photomultiplier Tube

30 CNCS has successfully grow up as the contractor of K23 NPP I&C, through the localization process of FF,CJ and FQ34/56 project. CNCS China Nuclear Control System Engineering Co., Ltd. V&V V&V software tools with copyright Main editor company for China energy industry standard Guidance of Generating SVVP for Nuclear Power Plant Participate in generating IEEE-1012 standard Apply to FJS PMC project and C3C4 measurement system of core neutron fluence rate project. Human Factor Engineering CNCS has the capabilities of HMI design, NPP process analysis, display design, computerized operation procedure design & analysis, advance alarm engineering, control room and panel design. Implement HFE design task for Hainan 1&2 DCS project and Fuqing 3&4 DCS project.

31 CNCS China Nuclear Control System Engineering Co., Ltd. NicSys2000 and NicSys8000 solution based on ACP1000 Reactor

32 Nu serial products of SNPAS SNPTC State nuclear power automation system engneering company

33 CAP1400 I&C Delivery Detailed design FAT PDR CDR 1:1 Prototype one division test 1:1 prototype test Requirement review RPS 1:1 Prototype Mission review Safety Platform NuPAC is being reviewed by NRC and NNSA presently.

34 CAP1400 I&C :1 prototype test :1 prototype production Principle prototype System design of engineering prototype Software test of principle prototype Test of turbine control system Production of engineering prototype Control system Prototype

35 NPIC New type of incore instrumentation system used for HL has been developed, including flux measurement and subcooling monitoring systems; Develop safety platform NASPAC Computer based technology, is under certification by TUV for SIL3. Prototype is being construction. New type of rod control and indication system has been developed and has been used in Fuqing 3&4. Some 1E sensors, electrical connector, etc.

36 The 3rd China (International) I&C Technology Conference in Nuclear Power Field in Shanghai, China (2015.4) Organized by CNS and CIS Support by IAEA and CAEA Host by SNPTC cosponsored by CNCS, CTEC, and SIPAI

37 Subject including: NPP I&C system operation, maintenance and renovation; NPP I&C system design and verification; NPP I&C system and equipments installation and commission; I&C equipments manufacture and qualification; Digital platform development ; MRC and HSI design and validation; Industry safety, cyber security and physical protection; Code, standard and experience feedback on I&C ; Simulator and simulation technology.

38 Contents 一 二 3 三 Status of nuclear power plants in China Introduction of I&C design and implementation in NPPs Recommendations to IAEA

39 Recommendations Provide more detail and clear instruction on equipment qualification under severe accident and the availability requirement for the instruments, Suggest to establish guidance on method and approach of HFE design and review, hope the guidance could be more maneuverability, Suggest IAEA to establish guidance on cyber security of computer based I&C system in NPP,

40 Recommendations Hope IAEA could establish guidance on the requirements of diversity actuation system design for ESFAS, Suggest more and more I&C seminars or meetings could be hold in China, due to the reason of fast speed NPP construction in China. Then more engineers could have the chance to discuss with experts from other countries to share experience with them.

41 Special Thanks to the Experts & Contributors: China Nuclear and Radiation Safety Center Mr. Wang zhongqiu, SNPTC Shanghai Nuclear Engineering Research & design Institute Mr. Wangxu, Institute of Nuclear Energy Technology(INET), Tsinghua University Prof. Li Duo, Nuclear Power Institute of China(NPIC) Mr. Wang Yuanbing, I&C division, CNNC Jiangsu Nuclear Power Co. Ltd. Ms. Ren Chunxiang, State Nuclear Power Automation System Engineering Company Dr. Zenghai, Some information some from the 3rd China (International) I&C Technology Conference material.

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