Nuclear Power Plant Life Management Processes Guidelines And Practices For Heavy Water Reactors

This publication provides an overview of the various plant life management (PLiM) methodologies, technologies and processes to ensure long term operation of heavy water reactors (HWRs). Implementation of a systematic and comprehensive PLiM programme, such as that outlined in the publication, goes a long way towards meeting the overall goal of HWR owners and operators to successfully achieve design life and continued operation. Included in this publication are technical aspects of HWR PLiM, component specific technology considerations for condition assessment, an example of a proactive ageing management programme, and Ontario power generation experiences. Country reports from Argentina, Canada, India, the Republic of Korea and Romania are attached in an annex in order to share practices and experiences of PLiM programmes.

This publication reports on the outcome of an IAEA workshop on heavy water reactor operation. It summarizes the material presented at the workshop and discusses a broad range of operational practices, including regulatory aspects, the reduction of occupational dose, performance improvements, and reduction of operating and maintenance costs.

Explains the general approach to plant life management (PLiM), details and defines the relationship between nuclear power plant maintenance and PLiM, assembles a list of good practices and formulates guidelines for ageing management of critical structures, systems and components.

The recommendations provided in this Safety Guide are aimed primarily at operating organizations of nuclear power plants and regulatory bodies. It covers the concept of operational limits and conditions (OLCs), their content as applicable to nuclear power plants, and the responsibilities of the operating organization for their establishment, modification, compliance and documentation. Operating procedures (including emergency operating procedures and severe accident management guidelines) to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide.

The reactor core is the central part of a nuclear reactor where nuclear fission occurs. It consists of four basic systems and components: the fuel (including fuel rods and the fuel assembly structure), the coolant, the moderator and the control rods, as well as additional structures such as reactor pressure vessel internals, core support plates, and the lower and upper internal structure in light water reactors. This Safety Guide provides recommendations on meeting the safety requirements established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, applied to the design of the reactor core for nuclear power plants. The publication addresses the safety aspects of the core design and includes neutronic, thermohydraulic, thermomechanical and structural mechanical aspects. Other aspects considered are those relating to reactor core control, shutdown and monitoring, and core management.

This report contains practical guidance for performing accident analysis for nuclear power plants with pressurised heavy water reactors, based on current international good practice. It covers key aspects required including selection of initiating events and acceptance criteria, computer codes and modelling assumptions, the preparation of input data, presentation of results and quality assurance.

Provides guidance and a wide range of practical examples that will be helpful for both nuclear power plant (NPP) operating organisations and regulatory bodies in developing and improving the processes of authorization of control room personnel.

When nuclear power plants reach the end of their nominal design life, they undergo a special safety review and an ageing assessment of their essential structures, systems and components for the purpose of validating or renewing their licence to operate for terms beyond the service period originally intended. Three different plant life management models have been used to qualify these nuclear power plants to operate beyond their original design life. This publication presents a collection of sample licensing practices for long term operation among IAEA Member States. The various plant life management models used to obtain long term operation authorizations are described and comparisons drawn against the standard periodic safety review model. Lessons learned and warnings about possible complications and pitfalls are also described to minimize the licensing risk during operation and future long term operation applications. The main intention of this publication is to support nuclear power plant owners and operators planning an extension of plant operation beyond its original design life, but it also serves as a useful guide for those interested in procuring, from the beginning, the necessary tools to implement ageing management in their future plant with long term operation in mind.