Radiation protection at the RA Reactor in 1997, Part -2, Annex 1, Control of the working environment, dosimetry and radiation protection

This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. Previously initiated actions concerning future decision on the status of the RA reactor were continued during 1997. Actions in 1997 were focused to detailed analysis of the conditions of storing the spent fuel in the storage pools and preparing the documentation for decision making about the methods for the improvement of the mentioned conditions. After adopting the procedures, detailed preparations, and purchasing the needed equipment, the first phase of remedial action, the removal of the sludge from the bottom of the spent fuel storage pool was started in September 1997. It is stated that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel