Paragraphs in "Joint Convention On The Safety Of Spent Fuel Management And On The Safety Of Radioactive Waste Management" coded as SCIR
Displaying 1 - 23 of 23
| Label | Provision |
|---|---|
| Pre.3 | (i) Recognizing that the operation of nuclear reactors generates spent fuel and radioactive waste and that other applications of nuclear technologies also generate radioactive waste; |
| Art.1.1x.i | (i) to achieve and maintain a high level of safety worldwide in spent fuel and radioactive waste management, through the enhancement of national measures and international co-operation, including where appropriate, safety-related technical co-operation; |
| Art.6.1.iv | (iv) to consult Contracting Parties in the vicinity of such a facility, insofar as they are likely to be affected by that facility, and provide them, upon their request, with general data relating to the facility to enable them to evaluate the likely safety impact of the facility upon their territory. |
| Art.7.1x.ii | (ii) at the design stage, conceptual plans and, as necessary, technical provisions for the decommissioning of a spent fuel management facility are taken into account; |
| Art.7.1x.iii | (iii) the technologies incorporated in the design and construction of a spent fuel management facility are supported by experience, testing or analysis. |
| Art.8.1x.i | (i) before construction of a spent fuel management facility, a systematic safety assessment and an environmental assessment appropriate to the hazard presented by the facility and covering its operating lifetime shall be carried out; |
| Art.8.1x.ii | (ii) before the operation of a spent fuel management facility, updated and detailed versions of the safety assessment and of the environmental assessment shall be prepared when deemed necessary to complement the assessments referred to in paragraph (i). |
| Art.9.1x.ii | (ii) operational limits and conditions derived from tests, operational experience and the assessments, as specified in Article 8, are defined and revised as necessary; |
| Art.9.1x.iii | (iii) operation, maintenance, monitoring, inspection and testing of a spent fuel management facility are conducted in accordance with established procedures; |
| Art.9.1x.iv | (iv) engineering and technical support in all safety-related fields are available throughout the operating lifetime of a spent fuel management facility; |
| Art.9.1x.vi | (vi) programmes to collect and analyse relevant operating experience are established and that the results are acted upon, where appropriate; |
| Art.14.1x.ii | (ii) at the design stage, conceptual plans and, as necessary, technical provisions for the decommissioning of a radioactive waste management facility other than a disposal facility are taken into account; |
| Art.14.1x.iii | (iii) at the design stage, technical provisions for the closure of a disposal facility are prepared; |
| Art.14.1x.iv | (iv) the technologies incorporated in the design and construction of a radioactive waste management facility are supported by experience, testing or analysis. |
| Art.15.1x.i | (i) before construction of a radioactive waste management facility, a systematic safety assessment and an environmental assessment appropriate to the hazard presented by the facility and covering its operating lifetime shall be carried out; |
| Art.15.1x.ii | (ii) in addition, before construction of a disposal facility, a systematic safety assessment and an environmental assessment for the period following closure shall be carried out and the results evaluated against the criteria established by the regulatory body; |
| Art.15.1x.iii | (iii) before the operation of a radioactive waste management facility, updated and detailed versions of the safety assessment and of the environmental assessment shall be prepared when deemed necessary to complement the assessments referred to in paragraph (i). |
| Art.16.1x.i | (i) the licence to operate a radioactive waste management facility is based upon appropriate assessments as specified in Article 15 and is conditional on the completion of a commissioning programme demonstrating that the facility, as constructed, is consistent with design and safety requirements; |
| Art.16.1x.ii | (ii) operational limits and conditions, derived from tests, operational experience and the assessments as specified in Article 15 are defined and revised as necessary; |
| Art.16.1x.iii | (iii) operation, maintenance, monitoring, inspection and testing of a radioactive waste management facility are conducted in accordance with established procedures. For a disposal facility the results thus obtained shall be used to verify and to review the validity of assumptions made and to update the assessments as specified in Article 15 for the period after closure; |
| Art.16.1x.iv | (iv) engineering and technical support in all safety-related fields are available throughout the operating lifetime of a radioactive waste management facility; |
| Art.16.1x.vii | (vii) programmes to collect and analyse relevant operating experience are established and that the results are acted upon, where appropriate; |
| Art.27.2x.iii | (iii) a Contracting Party which is a State of destination shall consent to a transboundary movement only if it has the administrative and technical capacity, as well as the regulatory structure, needed to manage the spent fuel or the radioactive waste in a manner consistent with this Convention; |