T/AST/046 - Issue 2
1.1 This Technical Assessment Guide (TAG) addresses Safety Assessment Principle 1 (SAP) ESS.27 which deals with the software of computer based safety systems (SSs). Technical Assessment Guide T/AST/003 addresses SSs in general. This SAP is supported by other general and plant specific SAPs. Where a computerised SS is used, because the technology is inherently complex and not amenable to traditional methods of reliability assessment, SAP ERL.1 and SAP paragraph 177 should be applied1. ESS.27 presents the elements of a multi-legged procedure that should be used to demonstrate the adequacy of a SS using software based technology which is based on SAP ERL.1 and SAP paragraph 177.
1.2 The TAG contains guidance to advise and inform ONR inspectors in the exercise of their professional regulatory judgement. Comments on this guide, and suggestions for future revisions, should be recorded on the appropriate registry file.
There is only one key principle that deals specifically with this topic, ESS.27. It is, however, underpinned by two more general principles, ERL.1 and ERL.2. The content of ESS.27 is reproduced below for ease of reference.
| Engineering principles: safety systems | Computer-based safety systems | ESS.27 |
|---|---|---|
Where the system reliability is significantly dependent upon the performance of computer software, the establishment of and compliance with appropriate standards and practices throughout the software development life-cycle should be made, commensurate with the level of reliability required, by a demonstration of ‘production excellence’ and ‘confidence-building’ measures. |
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The key principle is supported by a number of other principles of relevance to computer based SSs. The SAPs identified below are explicitly referenced in the main body of this TAG. Other SAPs are implicitly referenced in Appendix 1 (e.g. A1.1 to ESS.18 and A1.2 to EDR.4). Note that T/AST/003 ‘Safety Systems’ addresses the generality of SS SAPS (e.g. ESS.1 to ESS.27).
3.1 Licence conditions 14 and 15 (preparation and review of safety cases) apply particularly, and Lcs 17 (Quality Assurance), 20 and 22 (modification), 27 (safety mechanisms, devices and circuits), 28 (examination, inspection maintenance and testing) are also relevant.
2 - IAEA Safety Standards Series, Safety Guide No.NS-G-1.1 - Software for Computer Based Systems Important to Safety in Nuclear Power Plants. (2000)
4 - The Tolerability of Risk From Nuclear Power Stations (HSE 1992) ISBN 0-11-886368-1.
9 - BS IEC 61226:2005. Nuclear power plants - Instrumentation and control systems important to safety – Classification of instrumentation and control functions.
10 – The use of computers in safety-critical applications – Final report of the study group on the safety of operational computer systems, (HSE 1998) ISBN 0-7176-1620-7 [729KB]
5 - Software-based protection for Sizewell B: the regulator’s perspective. Nuclear Engineering International, September 1991
6 - Software-based protection for Sizewell B: the regulator’s perspective. Proceedings of the International Conference on Electrical and Control Aspects of the Sizewell B PWR, September 1992.
8 - IEC 61508:2002. Functional safety of electrical/electronic/programmable electronic safety-related systems.
1 The multi-legged procedure requires a demonstration of production excellence, covering initial specification through to the finally commissioned system, comprising the following elements:
7 - IEC 60880:2006. Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions.
NB. Text in clauses a), b) and c) above that is identical to that contained in SAP paragraph 360 is identified by bold.
2 Excellence of production requires that the best practices current at the time be used to avoid errors, detect and remove those not avoided and provide in-built system tolerance to those not detected (ECS.3 and EDR.1). It is important that an unambiguous, comprehensive and verified specification of the system requirements, covering the full system life-cycle is available from the earliest stages of the production process.
3 Should the production excellence assessment identify weaknesses in the production process, compensating measures should be applied to address these. The type of compensating measures will depend on, and should be targeted at, the specific weaknesses found (ESS.27 paragraph 362). Compensating measures should not be confused with the confidence building activities discussed below. The confidence building activities should be determined at the outset of the project and applied as far as possible to the final production software (i.e. after the completion of any compensating measures).
4 Although not mandatory, the case for production excellence is greatly assisted by evidence of the systematic application of national and international e.g. 7 standards, coupled with a case by case justification of non-compliances.
5 It must be demonstrated that the integrated equipment is capable of satisfactory operation in situ through an extensive pre-operational test (A1.87). During this stage the equipment will be operational (with frequent testing) while being progressively integrated with other plant as part of commissioning (ECM.1).
6 It is recognised that the dynamic testing could be part of the confidence building measures if not undertaken by the manufacturer. The number of dynamic tests should be informed by statistical testing considerations. This might mean that tens of thousands of tests are required for confidence in the dependability of the system to be built up (e.g. of the order of 50,000 tests with no failures for a 1E-4 probability of failure on demand demonstration to 99% confidence). Consideration should be given to the feasibility of generating a statistical estimation of system reliability (as informed by research).
1 The confidence building leg provides an independent and thorough ‘reasonably practicable’ assessment of the SSs’ ‘fitness for purpose’ (ERL1), comprising the following elements:
NB. Text in clauses a) and b) above that is identical to that contained in SAP paragraph 361 is identified by bold.
2 The independents should determine and justify their approach, the rigour of which should be proportional to the needs of the task. Wherever practicable the independent assessors should employ checking methods dissimilar to those used by the systems producer(s) (e.g. Dynamic Testing, MALPAS etc. as applied to the Sizewell B PPS).
3 The chosen confidence building techniques should be demonstrated to be adequate prior to application. New and unproven techniques will need especially comprehensive demonstration in order to provide confidence that the route chosen will be successful.
4 It is important to stress that the product checking should be applied only to the finally delivered product - that is after completion of the manufacturers verification and validation. The licensee may, however, be able to make a case for applying techniques to code that has completed the manufacturer’s independent verification.
5 The timing of the confidence building activities should ensure that their application and correction of findings does not become entwined with the production process. The conduct of the initial proving of confidence building techniques should not compromise the assessment of the delivered product.
6 The confidence building measures should be conducted by suitably qualified and experienced persons who are independent, established in a working regime compatible with the objectives of the task and free from conflicts of interest.
7 The use of “independent” should be interpreted as meaning not connected with the systems’ suppliers, either designer or manufacturer. The organisational arrangements including allocation of responsibility for confidence building tasks to the licensee’s procurement group (i.e. the intelligent customer group for the system) and to independent assessors in a different line management chain should be justified.
8 The independents who are separate to the licensee’s procurement group should have financial autonomy and managerial independence to reach their own conclusions on the adequacy of the system and its safety case. They should not be restricted in technical scope and have a frank reporting regime with a route to the licensee’s main Board.
9 The independents should report findings and their reconciliation within the safety case. All reporting of confidence building measures including findings and their reconciliation within the safety case should be auditable.
1 Technical guidance can be found in Appendix 1 which is a record of an earlier detailed technical assessment guide. The guidance provided in Appendix 1 should be used in conjunction with the later IAEA Safety Series 2 guidance, European Commission guidance document 3, the report “Licensing of safety critical software for nuclear reactors. Common position of seven European nuclear regulators and authorised technical support organisations – Revision 2007 [736KB]” and IEC standards as appropriate (see below). The term “protection systems” is used in Appendix 1, however, the guidance is also applicable to other SSs and SRI containing software falling within the scope of ESS.27.
3 - European Commission – Nuclears safety and the environment – Common position of European nuclear regulators for the licensing of safety critical software for nuclear reactors, European Commission’s Advisory Experts Group, The Nuclear Regulators Working Group, Task Force on Safety Critical Software - Version 11. (May 2000)
2 Technical guidance and regulatory advice is available in the IAEA Safety Series 2, a European Commission guidance document 3 and the report “Licensing of safety critical software for nuclear reactors. Common position of seven European nuclear regulators and authorised technical support organisations – Revision 2007 [736KB]”. In particular, they contain guidance on a number of topics not fully addressed or considered in the earlier assessment guide (Appendix 1), such as; use and validation of pre-existing software, computer security, use of tools, software diversity, safety demonstration and formal methods. Assessors should ensure that the recommendations and guidance of these documents 2, 3 and 13 have been considered. While they are directed at Nuclear Power Plants much of their content is applicable to other nuclear facilities.
3 Further technical guidance can be found in IEC standards such as IEC 60880 7 (for software of SSs), IEC 61508 8 (grading of techniques and measures for software development - see Appendix 3) and IEC 6151311 (general requirements for systems). The IEC standards should be consulted for topics not addressed by the guidance provided by Appendix 1, the IAEA Safety Series[2], the European Commission guidance document 3, or the report “Licensing of safety critical software for nuclear reactors. Common position of seven European nuclear regulators and authorised technical support organisations – Revision 2007 [736KB]”.