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Introduction and general considerations (3.1.1–3.1.14)

3.1.1. The safety analysis report should start with an introduction that includes the following:

(a) Identification of the purpose of the nuclear power plant, making reference to the case for justification (e.g. in terms of meeting the demand for energy and the choice of the nuclear option);

(b) A statement of the main purpose of the safety analysis report;

(c) Information about the preparation process for the safety analysis report, the major contributors to the preparation (e.g. vendors), and the use of information that has been previously reviewed by the regulatory body, if applicable;

(d) A description of the structure of the safety analysis report, the objectives and scope of each of its chapters, and the connections between them;

(e) A description of the national and international guidance applied in the preparation of the safety analysis report, with justification of any deviations from this guidance.

Project implementation

3.1.2. The information provided in the project implementation section should include a description of the existing authorization status of the plant, with an indication of future project milestones, as appropriate.

Identification of interested parties regarding design, construction and operation

3.1.3. The primary contractors for the design, construction and operation of the nuclear power plant should be specified in this section. The principal consultants and external service organizations (e.g. those providing audits of the management system) should also be identified. The division of responsibilities between the designers, the owner, the constructors and the operating organization should also be described.

Information on the plant layout and other aspects

3.1.4. Drawings of the general layout of the entire plant (including multiple unit plants) should be included in the plant layout section, together with a presentation of the physical and geographical location; connections with the electricity grid; and means of access to the site by rail, road and water.

3.1.5. The main interfaces and boundaries between on‑site equipment and equipment and systems external to the plant should be described. In addition, it should be clearly specified which external equipment is under the responsibility of the operating organization and which is under the responsibility of other organizations.

3.1.6. This section might also refer to sensitive information (i.e. in a separate document; see para. 2.29) on the provisions made for the nuclear security of the plant. Such information might also include a description of the steps that would be taken to provide protection in the event of a malicious act on the site or off the site.

General plant description

3.1.7. This section should provide a general description of the plant, including the overall safety philosophy, the safety concepts to be applied and a general comparison with appropriate international practices. It should enable the reader to gain an adequate general understanding of the plant without having to refer to subsequent chapters of the safety analysis report.

3.1.8. This section should briefly present (e.g. in a table) the principal elements of the plant, including the number of units, the type of reactor, the principal characteristics of the plant, the type of nuclear steam supply system, the type of nuclear fuel, the type of containment structure and associated systems, the

thermal power levels in the core, the corresponding net electrical power output for each thermal power level, the type of ultimate heat sink, and any other characteristics necessary for understanding the main technological processes included in the design.

Comparison with other plant designs

3.1.9. If applicable, this section should include information about the reference plant (e.g. location and brief summary of relevant data). If the plant design is new, unique or special (‘first of a kind’), the plant design should be compared with designs that have previously been authorized, so as to identify the main differences and assist in the justification of any modifications and improvements that have been made. This comparison should focus on new safety features that differ from previous designs, such as the use of redundant, diverse, simplified, inherent, passive or other innovative means of fulfilling safety functions.

Drawings and other more detailed information

3.1.10. Basic technical and schematic drawings of the main plant systems and equipment should be included in this section. The drawings should be accompanied by a brief description of the main plant systems and equipment, together with their purposes and interactions. References should be made, where necessary, to other chapters of the safety analysis report that present detailed descriptions of specific SSCs.

Modes of normal operation of the plant

3.1.11. All operating modes of the nuclear power plant should be described:

startup, power operation, shutting down, shutdown (including long term shutdown), maintenance, testing, refuelling, and any other allowable modes of normal operation, including load following operation. The permissible periods of operation at different power levels in the event of a deviation from normal operating conditions should be specified.

Principles of safety management

3.1.12. This section should briefly introduce the management of safety as an integral component of the management of the operating organization. It should be confirmed that the operating organization will be able to fulfil its responsibility to operate the plant safely throughout its operating lifetime. The principles of safety management should be described.

Additional supporting or complementary documents to the safety analysis report

3.1.13. This section should provide a list and summary of the topical reports that are incorporated, by reference, as part of the safety analysis report. Typically, the results of tests and analyses (e.g. results of manufacturers’ material tests and qualification data) may be submitted as separate reports.

Conformance with applicable regulations, codes and standards

3.1.14. This section should provide an overview of the relevant regulations, codes and standards that collectively represent the safety rules used in the design, including information on the use of relevant IAEA safety standards. If these regulations, codes and standards have not been prescribed by the regulatory body, a justification of their appropriateness should be provided. Any deviations from existing regulations, codes and standards should be described in this section, together with a demonstration that the deviations will not be detrimental to safety.