In-Service Inspection of Nuclear Power Plants - gnssn - International ...

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1. INTRODUCTION
1.1. BACKGROUND
The IAEA 'Code on the Safety of Nuclear Power Plants: Operation' (IAEA
Safety Series No. 50-C-O (Rev. 1)), hereafter referred to as the Code, was developed
as part of the IAEA NUSS programme. The Code established the general safety
aspects of management, commissioning and operation of a nuclear power plant. The
first level of detailed guidance on the implementation of the Code was provided by
the associated Safety Guides.
The Safety Guide 50-SG-O2 'In-Service Inspection for Nuclear Power Plants'
provides this first level of guidance on the in-service inspection of structures, systems
and components of a nuclear power plant. However, more detailed guidance
on in-service inspection activities is needed for implementation of the recommendations
in the Guide.
1.2. OBJECTIVE
This 'Manual on In-Service Inspection of Nuclear Power Plants', hereafter
referred to as the Manual, is intended to provide more comprehensive considerations
on the management, organization, preparation, improvement and implementation of
in-service inspection activities and the related surveillance. It also gives illustrative
examples of good practices and recommendations from operating and other organizations
that are consistent with the requirements and recommendations of the Code and
Safety Guides. The Manual is directed primarily towards plant management.
This Manual should be used in conjunction with the Code and the Safety
Guides, in particular with IAEA Safety Series Nos. 50-C-O, 50-SG-O2, 50-SG-O5,
50-SG-O7, 50-SG-O8 and 50-SG-D1, which contain recommendations of a general
character about maintenance activities and radiation protection in an operating power
plant, and with the 'Manual on the Maintenance of Systems and Components Important
to Safety'.
1.3. SCOPE
This Manual serves as a guideline at the plant management level for in-service
inspection (ISI) of structures, systems and components important to safety for light
water reactor (LWR), pressure tube reactor (PTR), and gas cooled reactor (GCR)
nuclear power plant. It is not the intention of this Manual to address the technical
problem of how to perform in-service inspection for a particular component but
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