PD IEC/TR 63084:2017
Current
The latest, up-to-date edition.
Nuclear power plants. Instrumentation and control important to safety. Platform qualification for systems important to safety
Hardcopy , PDF
English
09-18-2017
Important note : All end users must be registered with an Account prior to user licenses being assigned.| Committee |
NCE/8
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| DocumentType |
Standard
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| Pages |
60
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| PublisherName |
British Standards Institution
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| Status |
Current
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1.1 General This Technical report provides an assessment framework and activities for efficient and transparent qualification of I&C platforms for use in nuclear applications important to safety, according to nuclear standards and state of the art. The assessment aims at a prequalification of I&C platforms outside the framework of a specific plant design. Qualification is assumed to be pre-requisite for allowing the particular I&C platform to be used for implementation of the safety classified I&C system. It is to enable parties implementing particular plant specific I&C systems to concentrate on application functions, while for basic system functions to rely on platform qualification. The I&C platform qualification is based on evaluation of the hardware and software functions provided by the platform ensuring safe and cost-effective life-cycle support of I&C systems. That would include tools for software engineering and software development (software module libraries), code generation, validation, maintenance, etc. Basic means of equipment qualification, as prescribed by the IEC/IEEE 60780-323, are through analysis, type testing and documented operational experience. Other documents applicable for qualification for nuclear use include IEC 61513, IEC 60880, IEC 62138, IEC 62566, IEC 62671 and IEC 61226. The features of the I&C platform to be qualified will be identified in requirements on the I&C platform. The requirements can vary, but in essence are based on suppliers\' claims on the product scope and functionality. Those claims are normally given in platform documentation such as system descriptions and supplier\'s requirements for design, implementation, verification & validation. They are all based on the appropriate IEC SC 45A standards and national regulations.
| Standards | Relationship |
| IEC TR 63084:2017 | Identical |
| IEEE 1074-2006 | IEEE Standard for Developing a Software Project Life Cycle Process |
| CFR 10(PTS0-199) : JAN 87 | ENERGY - NUCLEAR REGULATORY COMMISSION |
| ISO/IEC 27001:2013 | Information technology — Security techniques — Information security management systems — Requirements |
| IEC 62342:2007 | Nuclear power plants - Instrumentation and control systems important to safety - Management of ageing |
| IEEE 1008-1987 | IEEE Standard for Software Unit Testing |
| IEC 61226:2009 | Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions |
| IEC 62138:2004 | Nuclear power plants - Instrumentation and control important for safety - Software aspects for computer-based systems performing category B or C functions |
| IEEE 1364-2005 | IEEE Standard for Verilog Hardware Description Language |
| IEC 61508-4:2010 | Functional safety of electrical/electronic/programmable electronic safety-related systems - Part 4: Definitions and abbreviations (see Functional Safety and IEC 61508) |
| IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
| IEC 61508-3:2010 | Functional safety of electrical/electronic/programmable electronic safety-related systems - Part 3: Software requirements (see Functional Safety and IEC 61508) |
| ISO/IEC 27002:2013 | Information technology Security techniques Code of practice for information security controls |
| IEC 60987:2007+AMD1:2013 CSV | Nuclear power plants - Instrumentation and control important to safety - Hardware design requirements for computer-based systems |
| IEEE 1076-2008 REDLINE | IEEE Standard VHDL Language Reference Manual |
| MIL-STD-461 Revision G:2015 | REQUIREMENTS FOR THE CONTROL OF ELECTROMAGNETIC INTERFERENCE CHARACTERISTICS OF SUBSYSTEMS AND EQUIPMENT |
| IEEE 384-2008 REDLINE | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
| IEC 60880:2006 | Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| ISO 9001:2015 | Quality management systems — Requirements |
| IEEE 1012-2012 | IEEE Standard for System and Software Verification and Validation |
| IEC 61513:2011 | Nuclear power plants - Instrumentation and control important to safety - General requirements for systems |
| IEC 60964:2009 | Nuclear power plants - Control rooms - Design |
| IEC 61508-1:2010 | Functional safety of electrical/electronic/programmable electronic safety-related systems - Part 1: General requirements (see Functional Safety and IEC 61508) |
| IEC/IEEE 60780-323:2016 | Nuclear facilities - Electrical equipment important to safety - Qualification |
| ISO/IEC 15504-1:2004 | Information technology Process assessment Part 1: Concepts and vocabulary |
| IEC 62566:2012 | Nuclear power plants - Instrumentation and control important to safety - Development of HDL-programmed integrated circuits for systems performing category A functions |
| IEC 61508-2:2010 | Functional safety of electrical/electronic/programmable electronic safety-related systems - Part 2: Requirements for electrical/electronic/programmable electronic safety-related systems (see Functional Safety and IEC 61508) |
| 768/2008/EC : 2008 COR 2 2015 | DECISION NO 768/2008/EC OF THE EUROPEAN PARLIAMENT AND OF THE COUNCIL OF 9 JULY 2008 ON A COMMON FRAMEWORK FOR THE MARKETING OF PRODUCTS, AND REPEALING COUNCIL DECISION 1993/465/EEC (TEXT WITH EEA RELEVANCE) |
| IEEE 7-4.3.2-2016 | IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
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