软件安全生命周期和核电厂的可编程电子安全系统的方法.pdf
《软件安全生命周期和核电厂的可编程电子安全系统的方法.pdf》由会员分享,可在线阅读,更多相关《软件安全生命周期和核电厂的可编程电子安全系统的方法.pdf(14页珍藏版)》请在淘文阁 - 分享文档赚钱的网站上搜索。
1、J.Grski(Ed.):SAFECOMP 2006,LNCS 4166,pp.85 98,2006.Springer-Verlag Berlin Heidelberg 2006 Software Safety Lifecycles and the Methods of a Programmable Electronic Safety System for a Nuclear Power Plant Jang-Soo Lee1,Arndt Lindner2,Jong-Gyun Choi1,Horst Miedl2,and Kee-Choon Kwon1 1 KAERI:Korea Atomic
2、 Energy Research Institute,Daejeon,Korea jslee,choijg,kckwonkaeri.re.kr 2 Institut fuer Sicherheitstechnologie,Postfach 12 13,85740 Garching,Germany arndt.lindner,horst.miedlistec.grs.de Abstract.This paper describes the relationship between the overall safety life-cycle and the software safety life
3、cycle during the development of the software based safety systems of Nuclear Power Plants.This includes the design and evaluation activities of the components as well as the system.This paper also compares the safety lifecycle and planning activities defined in IEC 61508 with those in IEC 61513,IEC
4、60880,IEEE 7-4.3.2,and IEEE 1228.Using the Ko-rean KNICS(Korean Nuclear Instrumentation and Control System)project as an example,the software safety lifecycle is described by comparing it to the software development,testing,and safety analysis processes of international standards.The safety assessme
5、nt of the software for the KNICS Reactor Protec-tion System and Programmable Logic Controller is a joint Korean/German pro-ject.The assessment methods applied in the project and the experiences gained from this project are presented.1 Introduction This paper introduces the lifecycle based software s
6、afety analysis tasks for the KNICS(Korean Nuclear Instrumentation and Control System)project.The objectives of the safety analysis tasks are mainly to develop the programmable logic controller(PLC)for safety-critical instrumentation and control(I&C)systems,and then to apply the PLC to developing the
7、 prototype of the safety-critical software based digital protec-tion system in nuclear power plants.Safety-critical systems are those in which a failure can have serious and irreversi-ble consequences.For the past two decades,digital technology has been applied rapidly to I&C systems for nuclear pow
8、er plants,railways,airplanes,vehicles,com-munication networks,etc.In nuclear power plants more and more digital technology is being applied to I&C systems,too.Programmable logic controller based platforms(e.g.,TELEPERM XS,Common Q and Tricon)have been prototyped,evaluated for nuclear safety applicat
9、ions,and installed in several applications.The PLC is a special 86 J.-S.Lee et al.purpose digital controller,originally designed to replace the industrial hard-wired control systems.As PLCs are more widely used in digital I&C systems,the safety of the PLC software has become a primary consideration.
10、Fig.1 shows the developed PLC prototype of the KNICS project,which mainly consists of power modules,a processor module(embedded with the real-time operat-ing system pCOS),communication modules(HR-SDL,HR-SDN),and I/O modules.Power ModulesCPU ModuleComm.ModulesI/O ModulesPower ModulesCPU ModuleComm.Mo
11、dulesI/O Modules Fig.1.POSAFE-Q KNICS PLC pCOS is the software to control the hardware,such as the processors,storage,I/O device,and data communication.It is composed of five components:a scheduler,the inter-tasks communication part,a tick timer,an interrupt handler and application tasks.As shown in
12、 Fig.2,the plant protection system(PPS)consists of the reactor pro-tection system(RPS)and the engineered safety feature component control system(ESF-CCS).RPS generates the reactor trip signals and ESF actuation signals auto-matically whenever the monitored processing variables reach their predefined
13、 setpoints.PPS is designed as a PLC-based architecture with four redundant chan-nels/divisions(A,B,C,and D).The software of the prototype of the qualified PLCs(i.e.POSAFE-Q)is implemented by the proprietarily developed engineering tool pSET.The engineering tool pSET is used for developing the functi
14、onal block dia-grams,and for downloading the functional block diagram based programs into POSAFE-Q PLCs via RS-232C interface.The following chapters deal with the relationship of the overall safety lifecycle to the software safety lifecycle for the development of the components(e.g.,KNICS PLC)and th
15、e Reactor Protection System(RPS).The software safety lifecycles of the IEC 61508-3,IEC 60880,IEEE 1228-1994,and IEEE standards 7-4.3.2-2003 are com Software Safety Lifecycles 87 CPC/RCPSSSCPC/RCPSSSCPC/RCPSSSCPC/RCPSSSAuxiliary EquipmentControl Cabinet(Safety)S-FPDUController BS-FPDUMultiplexer Trai
16、n AReactorTripSwitchgearLocal BusTrain BSafety ConsoleS-FPDUController ASafetyLogicCabinet Train AS-FPDU Multiplexer Train BLocal BusTrain DLocal BusTrain AESF-CCSActuationCabinet(Train B)ReactorProtectionCabinet(B)ReactorProtectionCabinet(A)ESF-CCSActuationCabinet(Train A)VDUControllerS-FPDUControl
17、ler DS-FPDUMultiplexer Train CLocal BusTrain CS-FPDUController CSafetyLogicCabinet Train CS-FPDU Multiplexer Train DSafetyLogicCabinet Train DESF-CCSActuationCabinet(Train D)ReactorProtectionCabinet(D)ReactorProtectionCabinet(C)ESF-CCSActuationCabinet(Train C)SafetyLogicCabinet Train BQIAS-PEx-CoreI
18、n-CoreSOE(S)Auxiliary Equipment ConsoleCPC/RCPSSSCPC/RCPSSSCPC/RCPSSSCPC/RCPSSSCPC/RCPSSSCPC/RCPSSSCPC/RCPSSSAuxiliary EquipmentControl Cabinet(Safety)S-FPDUController BS-FPDUController BS-FPDUMultiplexer Train AReactorTripSwitchgearLocal BusTrain BSafety ConsoleS-FPDUController AS-FPDUController AS
19、afetyLogicCabinet Train AS-FPDU Multiplexer Train BLocal BusTrain DLocal BusTrain AESF-CCSActuationCabinet(Train B)ReactorProtectionCabinet(B)ReactorProtectionCabinet(A)ESF-CCSActuationCabinet(Train A)VDUControllerS-FPDUController DS-FPDUMultiplexer Train CLocal BusTrain CS-FPDUController CS-FPDUCon
20、troller CSafetyLogicCabinet Train CS-FPDU Multiplexer Train DSafetyLogicCabinet Train DESF-CCSActuationCabinet(Train D)ReactorProtectionCabinet(D)ReactorProtectionCabinet(C)ESF-CCSActuationCabinet(Train C)SafetyLogicCabinet Train BQIAS-PEx-CoreIn-CoreSOE(S)Auxiliary Equipment Console Fig.2.KNICS Pla
21、nt Protection System pared.The software safety lifecycle for the KNICS RPS and PLC systems is introduced and the relationship of the safety analysis and testing for a software safety lifecycle is identified.Finally,software safety assessment methods are described for the KNICS RPS and PLC systems.Ex
22、periences of the software safety analysis in the KNICS project are given.2 Safety Lifecycles in IEC and IEEE Standards The safety assessment of the software for the KNICS RPS and PLC is an ongoing joint Korean/German project.In the cases where the documents have been evaluated by KAERI,ISTec has che
23、cked the results of the evaluation by supplementing spot checks for the development documents according to the following IEC and IEEE standards.-IEC 61508-1,Functional safety of electrical/electronic/programmable elec-tronic safety-related systems Part 1:General requirements 6-IEC 61508-2,Functional
24、 safety of electrical/electronic/programmable elec-tronic safety-related systems Part 2:Requirements for electrical/electronic/programmable electronic safety-related systems 7-IEC 61508-3,Functional safety of electrical/electronic/programmable elec-tronic safety-related systems Part 3:Software requi
25、rements 8-IEC 60880,Nuclear Power Plants I&C systems important to safety Software aspects for computer-based systems performing category A functions 9-IEC 61513,Nuclear Power Plants Instrumentation and control for systems important to safety General requirements for systems 10-IEEE Std.7-4.3.2-2003,
- 配套讲稿:
如PPT文件的首页显示word图标,表示该PPT已包含配套word讲稿。双击word图标可打开word文档。
- 特殊限制:
部分文档作品中含有的国旗、国徽等图片,仅作为作品整体效果示例展示,禁止商用。设计者仅对作品中独创性部分享有著作权。
- 关 键 词:
- 软件 安全 生命周期 核电厂 可编程 电子 系统 方法
限制150内