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14 декабря, 2021
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The selected design and its safety review
The design selected must undergo a formal design safety review process by the regulator before a construction license can be issued. This review determines whether the design of the selected technology meets the required national safety regulations. Normally, these regulations will be consistent with the IAEA Safety Standards, which constitute the international consensus on nuclear safety in the form of Principles, Requirements, and Guides. A recent overview of the current status of the relevant IAEA documentation is available from the IAEA (IAEA, 2010a). Chapter 9 discusses current and near-future available technologies.
The IAEA has published a Safety Requirements document to establish the generally applicable requirements for a safety assessment of nuclear facilities and activities (IAEA, 2009a). The major licensing document the licensee must provide for a construction license is the PSAR for the selected NPP design. This is a comprehensive document running to thousands of pages of technical information, backed up by detailed analyses, R&D results, and other supporting documentation. Table 20.3 lists the content and some examples of the scope of material that needs to be covered (IAEA, 2004b). It is clear from Table 20.3 that the licensee must be familiar with all aspects of the NPP life cycle: design, construction, commissioning, operations, and decommissioning. The PSAR is the licensee’s evaluation of the safety basis for the plant covering its entire plant life cycle.
The production of the PSAR is a major task. Normally, the vendor/ designer provides much of the non-site specific technical information for this document. The licensee must provide the information that is specific to the country building the NPP, such as site conditions and operating
668 Infrastructure and methodologies for justification of NPPs
Table 20.3 Safety analysis report content
|
SAR chapter |
Chapter scope and examples |
|
Introduction |
This chapter deals with general issues that are country and project-specific. |
|
General plant description |
Topics include a description of the applicable codes and standards, the basic technical characteristics of the technology, the plant layout, plant operating modes, and the documents and analyses incorporated by reference. |
|
Management of safety |
Specific aspects of management processes are described along with the monitoring and review of safety performance. |
|
Site evaluation |
This includes site reference data such as hydrology, meteorology and seismology, as well as the evaluation of site-specific hazards and activities at the site that could influence the plant’s safety. The proximity of industrial, transport and military facilities is also described. Site-related issues for emergency planning and accident management are developed. Also, monitoring of site-related parameters and a description of radiological conditions are included. |
|
General design aspects |
The safety objectives and design principles, and conformance with the design principles are discussed. The classification of structures, systems, and components is also addressed. Specific topics include civil engineering works and structures, equipment qualification, environmental factors, human factors engineering, and protection against internal and external hazards. |
|
Description and conformance to the design of plant systems |
This is a comprehensive discussion of the reactor components. These include the reactor coolant and associated systems, the engineered safety features, instrumentation and control, electrical systems, plant auxiliary systems, power conversion systems, fire protection systems, fuel handling and storage systems, radioactive waste treatment systems, and other safety — related systems. |
|
Safety analysis |
Acceptance criteria for the safety objectives are stated. A summary of the results of the safety analyses to meet the acceptance criteria is presented. |
|
Commissioning |
This describes how the various SSCs will be tested and verified to meet the design requirements. |
|
Table 20.3 Continued
Source: IAEA (2004b). |
organization information. Notwithstanding the contributions from the vendor/designer, the licensee must have access to expertise for each of the PSAR areas. It is not possible to operate an NPP safely without this knowledge, whether available internally or obtained externally through technical support organizations. The latter would include access to R&D facilities capable of handling and characterizing radioactive components.
The regulator performs a detailed independent assessment of the PSAR and usually presents its results in a safety evaluation report (SER). The SER then becomes the technical basis for awarding or denying the construction license and for establishing the required limits and conditions to be complied by the licensee. Therefore, the licensee must be prepared to respond effectively during the evaluation process to any detailed technical questions from the regulator on the PSAR topics using internal or external expertise.