CSA N287.1-93 pdf download – General Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants.
lD Scope
1.1
This Standard provides the general requirements used in the design, construction, testing,
and commissioning of concrete containment structures for CANDU nuclear power plants
designated as class containment and is directed to the owners, designers, manufacturers,
fabricators, and constructors of the concrete components and parts.
Note: The requirements of the N287 Series of CSA Standards generally exceed the requirements of the
National Building Code of Canada.
1*2
This Standard includes definitions that are applicable in this Standard and in the other
Standards forming the N287 Series.
1.3
This Standard includes the responsibilities of the incumbent organizations and individuals
with respect to the functions mentioned in Clause 1.4, together with the pertinent
documentation required as a statement of quality assurance.
1.4
This Standard contains the general requirements for the design, fabrication, construction,
installation, examination, testing, and commissioning of containment structures of
reinforced (prestressed and non-prestressed) concrete that are installed as components of a
CANDU nuclear power plant.
1,5
This Standard includes the general requirements for certain metallic and nonmetallic parts
that form part of the containment boundary and that are placed in their final position
within the concrete or are attached to the concrete, as in the case of containment liners,
anchorage systems, and appurtenances.
2.2 Definitions The following definitions apply in this Standard: Note: A glossary of definitions that may be found in the N287 Series of CSA Stundards is given in Appendix D. Accessible area-an area of a nuclear power plant, the normal environment of which is such as to allow safe access by authorized personnel during power production. Act-the Act, Regulation, or Ordinance governing boilers and pressure vessels of the respective province. Note: When reference is made to the federal Atomic Energy Control Act, the full title will be used. Audit-those activities which are carried out to confirm that applicable elements of the quality assurance program have been established in accordance with the requirements of the quality assurance program and are being effectively implemented in accordance with specified re q u ire men ts . Class containment-a classification for the structures and parts designed, fabricated, constructed, installed, inspected, examined, and tested in accordance with the requirements of the CAN/CSA-N287 Series of Standards. Commissfoning-those activities performed following installation and prior to plant operation to demonstrate that equipment and systems meet their design requirements. Commissioning leakage rate target-the leakage rate for a new structure that commissioning tests attempts to confirm. Components-concrete structures and appurtenances that form part of the containment system, including those elements necessary to support or sustain containment.
Constructor-the organization that, by this Standard, is responsible for the construction of the components and the installation of the parts and materials. Containment appurtenance-the metallic and nonmetallic portions of the containment boundary which are not part of the containment structure. Containment boundary-the pressure-retaining portion of the containment system. Containment structure-the structural portion of the containment boundary. Containment system-the arrangement of components which limits the release of radioactive substances to the environment when such substances are released from the reactor process systems located within containment. Design basis earthquake (DBE)–an engineering representation of potentially severe effects at the site of earthquakes that have sufficiently low probability of being exceeded during the lifetime of the plant. The DBE may also be defined as the engineering representation of the design basis seismic ground motion (refer to CSA Standard Note: The DBE is expressed in the form of response spectra or time histories and employed for the seismic qualification of certain structures and equipment. Designer-the organization that, by this Standard, is responsible for the design of the components and their parts. Embedded parts-those parts which are in their final location at the time of concrete placing and are permanently anchored in the concrete structures. These are generally of two categories: (a) penetrations that provide openings through the concrete structure for the passage of personnel, material, process piping, ducts, and cables; and (b) nonpenetrations that are used primarily as a means of supporting items such as platforms, equipment, and piping in the concrete structure or for the protection of the con Crete.CSA N287.1-93 pdf download.
