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Additional resources for Safety Analysis Report Format for Nuclear Powerplants (IAEA GS-G-4.1)
117. This section should refer to the principles and objectives of nuclear safety, radiation protection and technical safety applicable to the particular plant design, as previously identified in the chapter on general design aspects [20, 21]. 118. In addition, detailed acceptance criteria specific to structures, systems and components for different classes of events and types of analyses should be specified. These acceptance criteria should be such that frequent events should have minor consequences and events that may result in severe consequences should be of a very low probability.
Where the actuation logic for engineered safety features is implemented by means of digital computers, a discussion of the software design and QA programmes, and the software verification and validation programme. Further discussion on matters to be covered in this part of the SAR is provided in Ref. . The specification of actuation system set points for engineered safety features, time delays in system operation and measurement uncertainties and how these relate to the assumptions made in the safety analyses chapter of the report.
Important simplifications made should be justified. The set of limiting assumptions for safety analysis used in the deterministic safety analyses performed for the different types of PIEs should be described in this section. The methods used to ensure that these assumptions demonstrate that sufficient safety margins are achieved for PIEs of each type should also be described. 130. A general summary of the verification and validation processes used for the computer codes should be presented, with reference to more detailed topical reports.
Safety Analysis Report Format for Nuclear Powerplants (IAEA GS-G-4.1)