[en] The report presents the requirements on management of disused sealed sources in Lithuania; disused sealed source disposal facilities; performed safety analysis and planed repository safety improvements. The requirements on pre-disposal management of Disused Sealed Sources (DSS) are presented. The requirements on disposal of short lived VLLW and LILW (A, B and C classes) radioactive waste approved in 2002-2003. Generic Waste Acceptance Criteria for Near Surface Disposal, P-2003-01 approved in 2003. Requirements on disposal of Low and intermediate level long lived waste do not exist (D and E classes). Requirements for the disposal of disused sealed sources (F class) do not exist. Disposal method for the F class - Near Surface or Deep geological repository, depending on the waste acceptance criteria. Only one repository for institutional radioactive waste exist in Lithuania - Maisiagala repository. It is near surface RADON type disposal facility, built in 1963 and closed in 1988. It was constructed of the monolithic reinforced concrete with the dimensions 5 m x 15 m x 3 m, the thickness of the sidewalls is about 0.25 m and the thickness of the bottom is about 0.2 m. The overall volume is about 200 m³. At time of closure only three fifths of the volume had been filled. The empty two fifths of the vault were filled with concrete, then with sand, then with the concrete (0.01 m), hot bitumen and the 0.05 m asphalt layers. Monolithic concrete that was covered with bitumen and 0.05 m thick layer of asphalt closed the vault. Sand layer the thickness of which was not less than 1.2 m formed the cap. Disused radioactive sources embedded in a biological shielding were buried together with their shielding, the sources without the shielding were buried in two stainless steel containers. The total activity of buried radioactive nuclides is 3.42.10^-15 Bq (calculated according the documentation). There are some uncertainties about the inventory: from 1963 to 1973. After the closure of the Maisiagala repository all industrial radioactive waste are transported to the Ignalina NPP site. Disused sealed sources are stored in the separate section of the radioactive waste storage facility for the solid radioactive waste. Main disused sealed sources are: H-3 (5.3 1011 Bq), Co-60 (1.7 1014 Bq), Sr-90+Y-90 (1.7 109 Bq), Cs-137 (4.6 1012 Bq), Pu-239 (2.9 1012 Bq), Ni-63 (2.4 109 Bq), C-14 (2.0 108 Bq), Ir-192 (1.27 1013 Bq). (1998-2000). The Lithuanian Energy Institute started evaluation of nuclides migration from repository at Maisiagala. The results show that concentration of H-3 and Cl-36 in the groundwater near repository exceeds permissible limits. The evaluation made by the Institute of Physics shows that H-3 is the only radionuclide which could cause doses, exceeding the ICRP recommendations for individuals of the public, in the case of ingestion of water from the well situated near the repository. The dangerous concentration of H-3 could be reached in the ground water flow in 40 - 100 years after closing of the repository at the distances less than 1000 m from it. C-14, Cl-36, Sr-90 Ra-226 and Pu-239 concentrations could exceed permissible limits depending on the distance from repository. The long-term safety assessment show Pu-239 concentration in the waste exceeds recommended concentration for shallow burial disposal by one order of magnitude. In the beginning H-3 dominates the released activity. For some hundred years H-3 and Cs-137 are most important in terms of dose through drinking water (1 mSv/y dose exceeded). For times around some hundred years Cl-36 and Ra-226 are dominating nuclides