ANNEX I

(a)

the dismantling and decontamination of the reactors’ buildings and components in accordance with the decommissioning plans. Progress made in respect of this objective is to be measured by the quantity and type of materials removed as well as earned value;

(b)

the safe management of the decommissioning and radioactive waste in line with the needs identified in the respective decommissioning plan and of activated materials and dismantling materials, including their decontamination up to interim storage or to disposal (depending on the waste category), as well as the completion of the waste and material management infrastructure where necessary. This objective has to be accomplished in accordance with the decommissioning plan and subject to the necessary management of radioactive waste. Progress made in respect of this objective is to be measured by the quantity and type of material released from regulatory control and waste safely stored or disposed as well as earned value; and

(c)

to continue the downgrading of radiological hazards. Progress made in respect of this objective is to be measured through the safety assessments of the activities and the facility, identifying ways in which potential exposures could occur and estimating the probabilities and magnitude of potential exposures. In the Kozloduy programme, the release of the facilities from regulatory control up to corresponding regulatory free-release levels is due to take place by the end of 2030.

(a)

develop ties and exchanges among Union stakeholders (e.g. Member States, safety authorities, and utilities and decommissioning operators);

(b)

document explicit knowledge and make it available through multilateral knowledge transfers on decommissioning and waste management governance issues, managerial best practices, and technological challenges and decommissioning processes at both operational and organisational level, with a view to developing potential Union synergies.