Country Report. I&C application status in NPPs in China. Wang Yanjun. IAEA TWG NPPIC 26 rd Meeting, Vienna, May 24, 2017.

Transcription

1 Country Report I&C application status in NPPs in China Wang Yanjun IAEA TWG NPPIC 26 rd Meeting, Vienna, May 24, 2017.

2 Contents Ⅰ Ⅱ Status of nuclear power plants in China Introduction of I&C design and implementation in NPPs 3Ⅲ Domestic digital platforms Ⅳ Recommendations to IAEA

3 Contents Ⅰ Ⅱ Status of nuclear power plants in China Introduction of I&C design and implementation in NPPs 3Ⅲ Domestic digital platforms Ⅳ Recommendations to IAEA

4 NPPs distribution in China CEFR 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 Qinshan Ⅲ (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 CEFR Beijing

6 NPPs in commercial operation Projects Province Total Capacity (MW) C.O Hongyanhe (unit 1,2,3,4) Liaoning 4x /2014/ / Ningde (unit 1,2,3,4) Fujian 4x /2014/ / Yangjiang(unit 1,2,3,4) Guangdong 4x /2015.3/ / Fuqing (unit 1,2,3) Fujian 3x / / Fangjiashan (unit 1,2) Zhejiang 2x /2015./1 Changjiang (unit 1,2) Hainan 2x / Fangchenggang (unit 1,2) Guangxi 2x /

7 NPPs under construction Projects Province Total Capacity (MW) FCD Hongyanhe (unit 5-6) Liaoning 2X Yangjiang (unit 5-6) Guangdong 2x Fangchengang (unit 3,4) Guangxi 2x Taishan (unit 1,2) Guangdong 2x1700 (EPR) Fuqing (unit 4) Fujian 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 Tianwan III (5,6) Jiangsu 2x Fuqing (unit 5-6) Fujian 2xACP1000(HL)

8 China NPPs development process Roadmap of PWR Domestically-development & Oversea-introduction Construction of the 1st NPP (300MW PWR) Construction of 650 MWe NPP CNP600 Construction of CNP1000 R&D of CP1000 ACP1000/ACPR1000+ HPR1000 CAP1400 Introduction of Daya Bay NPP Introduction of LingAo NPP Introduction of VVER Introduction of EPR Introduction of AP1000

9 HPR1000 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 HPR1000 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 HPR1000 Active & Passive Advanced PWR IAEA and NEA Safety Review December 2014, ACP1000(HPR1000) accomplished Generic Reactor Safety Review (GRSR) by IAEA experts. On August 22, 2014, ACP1000(HPR1000) passed through the technical review held by NEA and NNSA. Fuqing 5,6 is the demonstration project of ACP1000(HPR1000). On May 5, 2015, NNSA finished reviewing of the PSAR and signed Construction Permission for FUQING 5&6 NPP. FCD : 2015/5/7

13 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.

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

15 HTR-PM 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 Tsinghua University Full scope digital control system and reactor protection system with localized platform Full scope simulator for MCR design and validation.

16 HTR-PM Up to now, have finished most of the installation work; In October of 2016, inverse power transmission operation; In December of 2016,the MCR was available; Commission of equipments and systems is undergoing

17 ACP100-SMR History of R&D of ACP100 General Design Preliminary Design Concept Design Solution Verification Modify the Technology according to the feedback of Fukushima accident.

18 Multipurpose Applications Steam evaporated Turbine Generator Grid ACP100 Electricity Heating Sea Water Vaporization and cooling process Desalination Facility Freshwater Steam Supply

19 Safety Features Integration Canned motor pumps integrated into RPV; Integrated OTSGs; Integrated reactor head package design. Integrate Passive 1 Passive Core Cooling System; 2 Passive Residual Heat Removal System; 3 Passive Containment Cooling System. Severe accident prevention / mitigation measures 4 Passive Cavity Flooding System; 5 Passive Hydrogen Re-combiner System; 6 Automatic Depressurization System ; APC shell, protection from External Events ; Deep-buried NSSS.

20 Testing Six test research subjects Control rod drive line cold and hot test Control rod drive line anti-earthquake test Internals vibration test research Fuel assembly critical heat flux test research Passive emergency core cooling system integration test CMT and passive residual heat removal system test research

21 Demonstration Project New Site in Hainan Province; Safety Joint Research with NSC from the beginning of R&D in order to lower the risk; GRSR (IAEA); Issued the Review Principles China Fujian Milestone Hainan Design / Testing General Design Preliminary Design Detailed Design Construction / Commissioning Project Approval Construction / commissioning before loading FCD First Loading Operation Feasibility Report PSAR Site Change FSAR Completed GRSR Licensing Joint Research With NSC NNSA Review NNSA Review Submit Submit

22 Contents Ⅰ Ⅱ Status of nuclear power plants in China Introduction of I&C design and implementation in NPPs 3Ⅲ Domestic digital platforms Ⅳ Recommendations to IAEA

23 HPR1000 I&C Design As the nerve system of NPP, HPR1000 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. 23

24 Defense in Depth HPR1000 I&C design follows the defense in depth requirement in HAF which is technically equivalent with IAEA NS-R-1. In 2016, the latest IAEA SSR 2-1 Safety of Nuclear Power Plants: Design is published, there are some evolution, but no big influence for HPR1000 I&C design. 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

25 Overall architecture ECP BUP Operator Workstation PSMS Other NC and NC* Relay DAS Severe accident related I&C Special I&C Safety class NC* NC Priority module Isolation & Distribution level1 of DID Level2/3 of DID Level4 of DID Safety actuator/instrument Non-safety actuator/instrument 25

26 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

27 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

28 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

29 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

30 HTR-PM I&C Design 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; The protection system will be delivered to site in May this year. 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; All process control system cabinets had been delivered to site in November, HTR-PM Computer based MCR INET has finished the Multi-modules control room and HMI design; INET has finished engineering prototype manufacture and HSI validation; The MCR available in December of 2016.

31 Contents Ⅰ Ⅱ Status of nuclear power plants in China Introduction of I&C design and implementation in NPPs 3Ⅲ Domestic digital platforms Ⅳ Recommendations to IAEA

32 CNCS China Nuclear Control System Engineering Co., Ltd. Series of Products Series 1: Nuclear Digital Control System(DCS) NicSys 2000: Non-Safety platform of nuclear 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 of nuclear power plants digital control system platform NicSys 8000N has passed through the IAEA independent engineering review of I&C systems(ierics) in November,2016. Simulator 7 U 3 U RPS Prototype Simulator HMI 10 U 3 U 5 U 2 U 2 U 10 U 2 U 5 U 2 U S-VDU 10 U 2 U 5 U 2 U Engineer Station

33 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 Instruments Neutron Ionization Chamber Scintillator Detector Semiconductor Detector Sodium Iodide Detector Thermo luminescence Detector Photomultiplier Tube

34 Nuclear Power Institute of China (NPIC) As one of the 5 key Institutes, engaged in NPP and other types of reactor design, research, and technology services Sichuan Province Chengdu National Nuclear Power R&D Base Based on National Key Laboratory, many NPP engineering researches have been conducted. DRSI has completed 22 units of NPPs engineering design. the design range is extended from the reactor,reactor coolant system,correlative instrument and control system,correlative instrument and control system,to the nuclear steam supply system(nsss). At present,the design of Hualong No.1 engineering FuQing 5&6 units is in progress.

35 NPIC Advanced in-core instrumentation system 3 Service In Progress Core neutron flux measurement subsystem Main function 1 Real-time calculating core power 3D distribution. 2 Real-time monitoring LPD and DNBR. Composed by two subsystem In-core cool monitoring subsystem Main function 1Real-time monitoring core outlet temperature & key point vessel level 2post-accident parameters

36 NPIC Nuclear power plant safety DCS platform Guided by relevant standards of GB/IEEE/IEC, NASPIC adopts the digital technology which is featured with ARM series microprocessor and high-speed serial bus. During this time, NPIC has already developed high-reliability micro kernel boot software and safety communication protocol with completely independent intellectual property rights. In the field of I&C of nuclear power, NASPIC has reached advanced level. The safety DCS of the ETR and FR used NASPIC are currently at engineer design stage.

37 NPIC Nuclear power plant safety DCS platform Primary technical feature: (1)Comprehensive application area: Applicable of different reactors ( AP1000 Hualong No.1 M310 unit reactors) the nuclear power plants safety DCS platform of different architectures, applied to the different instrumentation and control systems (Power reactor research reactor test reactor and so on) (2)Deterministic task processing technology:adopt security processor which design for critical security domain, which is safe and reliable (3)Good maintainability:the system provide abundant and convenient maintenance means, which have good maintainability. (4)Good test and calibrate performance :The system can provide test and calibrate performance in many ways, which can fully validate function and performance of this system.

38 SNPTC-State Nuclear Power Automation System Engineering Company, Ltd. Company Background: 上海自仪 S A I C Responsible for one of China National S&T Major Project, to develop the digital I&C system and equipment in advanced PWR. CAP1400 Demonstration Project s I&C equipment supplier. 51% 49% A professional I&C solution supplier Engineering Equipment development Testing & Verification Installation & Commissioning Spare Parts Updating Life-cycle Service

39 SNPTC Nu Series NPP Digital I&C System Complete "Nu Series" NPP Digital I&C System Plant Control System and Its Platform Diverse Actuation System and Its Platform Full-Scope Simulator NPP Special Monitoring System and Seismic Monitoring System New Generation FPGA Technology based Reactor Protection System and Its Platform In-core and Ex-core Nuclear Instrumentation System Radiation Monitoring System Rod Control and Position Indication System

40 SNPTC Reactor Protection System-NuPAC 1. NuPAC Platform acquired license from NNSA In December 2016, License from NNSA. NuPAC Platform acquired HAF NuPAC Platform acquired certification from NRC In March 2017, NRC officially issued the Safety Evaluation Report (SER) of NuPAC Platform on its official website. NuPAC Card NuPAC Cabinet EQ Test

41 SNPTC Plant Control System-NuCON In April 2014, NuCON acquired CE Certification (EU Safety Standard Test) In August 2014, NuCON acquired FCC Certification (Equipment Communication Security Verification) In December 2015, NuCON acquired SIL3 Certification (ETS System) Platform Product Identification Type Tests CE 型式 SIL3 鉴定试验 3C FCC Pilot Project Application NuCON Cabinet

42 SNPTC digital systems Application All Nu-series products will be applied to CAP1400 Demonstration Project and the full-scale prototypes have already been manufactured. Nu-series products can be applied to the construction,upgrading and modernization of NPPs of various reactors,as well as heavy gas turbine and other energy projects.

43 Contents Ⅰ Ⅱ Status of nuclear power plants in China Introduction of I&C design and implementation in NPPs 3Ⅲ Domestic digital platforms Ⅳ Recommendations to IAEA

44 Recommendations Suggest IAEA could hold an seminar on SSG39 and on IAEA nuclear energy series No.NP-T-X.XX ARCHITECTURAL APPROACHES IN THE DESIGN OF NUCLEAR POWER PLANT INSTRUMENTATION AND CONTROL SYSTEMS in China. Suggest IAEA to establish guidance on application of CGD (commercial grade dedication) in NPP. Suggest IAEA to establish guidance on cyber security design of computer based I&C system in NPP. Suggest IAEA to establish guidance on new type of reactors I&C system design of NPP.

45 Special Thanks to the Experts & Contributors: Fujing Fuqing Nuclear Power Co., Ltd. Mr. Yang Ruzhen, Beijing Institute of Nuclear Engineering (BINE) Mr. Chen Rigang, Mr. Song Lei, Mr. Li Xiyun, Institute of Nuclear Energy Technology(INET), Tsinghua University Prof. Li Duo, Nuclear Power Institute of China(NPIC) Mr. Wang Yuanbing, I&C division, State Nuclear Power Automation System Engineering Company Mr. Liuzhen,

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