Seismic Instrumentation Requirements for CANDU Nuclear Power Plants
View Access for this document is only available for viewers in Canada
This is the first edition of CSA Standard CAN/CSA-N289.5, Seismic Instrumentation Requirements for CANDU Nuclear Power Plants. Development of this Standard began in 1976 under the sponsorship of the Canadian Nuclear Association's Codes, Standards, and Practice Committee. In 1977 the decision was made to promulgate this document as a CSA Standard.
Standards in the N289 Series were initiated in response to a recognition by the utilities and industries concerned with nuclear structures in Canada of a need for the documentation of standards applicable to the seismic qualification of nuclear structures and components of a CANDU nuclear power plant.
The purpose of this Standard is to provide a basis for specifying requirements for seismic instrumentation for CANDU nuclear power plants where a need for such instrumentation has been established. It is intended as an aid to owners of nuclear power plants to specify the extent and nature of instrumentation to be installed (if required). It also is intended as an aid to owners and equipment suppliers in specifying instrumentation, where such instrumentation is required, which meets a quality and standard commensurate with the safety principles necessary to comply with the Canadian nuclear safety philosophy.
This Standard covers seismic instrumentation for nuclear power plants for the measurement of seismic responses that may be used for the following reasons:
(a) To indicate the severity of the seismic response of the plant and to assist in deciding the acceptability of continued plant operation.
(b) To compare the recorded data against the Design Basis Seismic Ground Motion (DBSGM) and the Site Design Seismic Ground Motion (SDSGM) as specified in CSA Standard CANS-N289.2 and thus evaluate whether or not the design basis for safety structures and systems as defined in CSA Standard CAN3-N289.1 has been exceeded.
(c) To provide guidance for the need and extent of post earthquake inspection.
(d) To assess the seismic design assumptions made for structures, support systems, and components.
Data obtained using seismic instrumentation cannot be used alone to decide whether or not the plant should be shut down. However, the data used in conjunction with plant parameters and damage inspection reports should set the basis for the decision to continue to operate.
Additionally, the recorded data of seismic activity will be useful to compare actual versus predicted response and to assess the need for further detailed inspections.
This Standard is one of the N289 Series of Standards, which comprises the following:
CAN3-N289.1 - General Requirements for Seismic Qualification of CANDU Nuclear Power Plants;
CAN34289.2 - Ground Motion Determination for Seismic Qualification of CANDU Nuclear Power Plants;
CAN3-N289.3 - Design Procedures for Seismic Qualification of CANDU Nuclear Power Plants;
CAN3-N289.4 - Testing Procedures for Seismic Qualificotion of CANDU Nuclear Power Plants; and
CAN3-N289.5 - Seismic Instrumentation Requirements for CANDU Nuclear Power Plants.
Users of this Standard are reminded that the design, manufacture, construction, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the provisions of the Atomic Energy Control Act and Regulations. Thus, requirements additional to those specified in this Standard may be imposed by the Atomic Energy Control Board.
This Standard outlines the requirements for seismic instrumentation systems for nuclear power plants where site-specific seismic responses are required to be determined and recorded.