Radiation protection at the RA Reactor in 1999, 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. 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. Previously initiated actions concerning future decision on the status of the RA reactor were continued during 1999. The main objective of this activity was to complete the first phase of cleaning the spent fuel storage pool, removal of the slug from the bottom of the pool and transportation channels, as well as preparing the documentation for decision about the methods for improvement of storage pool conditions in future phases. Detailed analysis of procedures and planning of radiation safety and radiation protection methods was started. State of 30 aluminium barrels containing 4929 spent fuel elements stored in the storage pool was examined and demanded special radiation protection measures