Paragraphs in "Convention On Nuclear Safety" coded as SCIR
Displaying 1 - 14 of 14
| Label | Provision |
|---|---|
| Pre.12 | ix. Recognizing the usefulness of further technical work in connection with the safety of other parts of the nuclear fuel cycle, and that this work may, in time, facilitate the development of current or future international instruments; |
| Art.1.1x.i | i. to achieve and maintain a high level of nuclear safety worldwide through the enhancement of national measures and international co-operation including, where appropriate, safety-related technical co-operation; |
| Art.14.1x.ii | ii. verification by analysis, surveillance, testing and inspection is carried out to ensure that the physical state and the operation of a nuclear installation continue to be in accordance with its design, applicable national safety requirements, and operational limits and conditions. |
| Art.17.1x.i | i. for evaluating all relevant site-related factors likely to affect the safety of a nuclear installation for its projected lifetime; |
| Art.17.1x.ii | ii. for evaluating the likely safety impact of a proposed nuclear installation on individuals, society and the environment; |
| Art.17.1x.iii | iii. for re-evaluating as necessary all relevant factors referred to in sub-paragraphs (i) and (ii) so as to ensure the continued safety acceptability of the nuclear installation; |
| Art.17.1x.iv | iv. for consulting Contracting Parties in the vicinity of a proposed nuclear installation, insofar as they are likely to be affected by that installation and, upon request providing the necessary information to such Contracting Parties, in order to enable them to evaluate and make their own assessment of the likely safety impact on their own territory of the nuclear installation. |
| Art.18.1x.i | i. the design and construction of a nuclear installation provides for several reliable levels and methods of protection (defense in depth) against the release of radioactive materials, with a view to preventing the occurrence of accidents and to mitigating their radiological consequences should they occur; |
| Art.18.1x.ii | ii. the technologies incorporated in the design and construction of a nuclear installation are proven by experience or qualified by testing or analysis; |
| Art.19.1x.i | i. the initial authorization to operate a nuclear installation is based upon an appropriate safety analysis and a commissioning programme demonstrating that the installation, as constructed, is consistent with design and safety requirements; |
| Art.19.1x.ii | ii. operational limits and conditions derived from the safety analysis, tests and operational experience are defined and revised as necessary for identifying safe boundaries for operation; |
| Art.19.1x.iii | iii. operation, maintenance, inspection and testing of a nuclear installation are conducted in accordance with approved procedures; |
| Art.19.1x.v | v. necessary engineering and technical support in all safety-related fields is available throughout the lifetime of a nuclear installation; |
| Art.19.1x.vii | vii. programmes to collect and analyse operating experience are established, the results obtained and the conclusions drawn are acted upon and that existing mechanisms are used to share important experience with international bodies and with other operating organizations and regulatory bodies; |