[en] High temperature steam system if not operation the processing liquid radioactive waste can not be implemented. In 2018 were deemed urgent to revitalize one of which is the Steam system, due to the aging process condition of the fire tube in boiling water has corrosion that causes leaks and fragility that it can not be operated on the grounds of safety, considering the operating pressure of 8 bar and temperature 170 °C, so it needs a new revitalization of boiling water system so that the efficiency of steam production is achieved. Steam distribution pipes are also experiencing aging and corrosion, resulting in some point of steam leaks when streamed. This condition is very threaten the safety of workers and the environment. This problem solution is to revitalize the high temperature steam generating system so that liquid radioactive waste treatment can be carried out. (author)

[en] In 2018, was done manufactured of special tool for container Disused Seal Radioactive Source (DSRS) to minimize of potential of radiation expose on dismantling activities. The purpose of this activity is to simplify and speed up the release of radioactive sources from the package or container so as to minimize the risk of the excess radiation exposed for workers. The method is identification of key models required, design, material selection, execution of workmanship and function tests. The results obtained in the form of tool for 4 different DSRS container models are key model ^T, square or square model, medium and large minus model and double dot model. This tool made from carbon steel material that comes from a used electric motor shaft that has a resistance in receiving torque. From the test results obtained that the release time of the container cover using this special tool is faster than opening with a conventional tool, so it can be assumed that the amount of radiation exposure received by radiation workers is smaller. (author)

[en] Repair chiller pump for indications of cooling water droplets on the seal pump is air-wasters. In the visual observation of the seal cooling water droplets above the range of 15 drops per minute, for normal conditions is permitted droplets: 10 sid 15 drop per minute. Because beyond normal limits then need immediate replacement, among others: gland packing, gland follower as it broke, shaft sleeve for wear, and rubber clutch. After the replacement chiller pump P 62303 test functions and adjustment. The result obtained by the cooling water droplets are 11 drops per minute, so that the pump can operate properly. (author)

[en] Observation of an Air Handling Unit (AHU) performance after repair was carried out to ensure the suitability of operating standards. From the observation after AHU repair it was obtained that the average temperature of type A room is 22,75 °C, type B is 23,06 °C and type C is 23,42 °C. The temperature differences before and after repair were 0.65 °C for type A room, 1.08 °C for type B room and 1.28 °C for type C room. It indicates an improvement of performance. The improvement of performance will be continued by cleaning the cooling coil surface and prefilter, so that the heat transfer of air blowed into the cooling coil will be better. Due to aging of the AHU and other media provider and energy system, monitoring, maintenance and measurement of operating parameters must be conducted regularly. (author)

[en] Chiller Systems of Radioactive Waste Technology Center has been operated nearly 30 years, so it has suffered a lot of damage can not be repaired. It must perform the replacement of key components by the method of revitalization. Revitalization must be done because spare parts were no longer exist in the market according to type and models and also for cost efficiency. The main objective of revitalization to be fulfilled cold and fresh air in the rooms Installation of Radioactive Waste-Installations and administrative space. Before conducting activity, has been conducted an analysis of the cost-efficiency, repair methods, equipment performance and analysis of the various obstacles that will be experienced in the field so revitalization of the Chiller E 62302 can be conducted. (author)

[en] The cooling process is very important in the processing of radioactive waste, the radioactive waste management installations (IPLR) is used for cooling installations, offices and processing needs required. The objective of data is to monitoring performance AHU system. The monitoring was conducted during 2017 and the results of service meet the quality requirement IPLR, average in one year type region A 23.15 °C, type B 23,46 °C, type C 24.08 °C. Corrosion causes leakage of cooling water in the cooling coil headers, with the result that the performance of the Air Handling Unit declined from August, losses arising from AHU leaks have five aspects of loss are energy, media, life time instrument, safety and service, time in the filings improvement. (author)

[en] Boiler E6251 A (Boiling water system) serves to supply steam to the evaporation plant for liquid waste treatment in radioactive waste installation. Improvements include dry chemical fire pipe, fire resistant stone on the back hood, setting operation and replacement of other instruments. Revitalization of the activities that function test results obtained in accordance with the value of required operating standards. Function test results are obtained with the normal functioning of automation, security systems functioning normally, an operating pressure of 8.3 bar, 17.5 bar oil driver, relive low fire 600 kPa (RLF), relive high fire of 1100 kPa (RHF), no leakage of combustion. (author)

[en] The operation of the VAC system in the Radioactive Waste Treatment (IPLR) aims to keep the room and the instrument is in a state of vacuum partially to the outside air pressure (negative pressure) and obtaining the renewal of the room air through the blowing and withdrawal of air from the room. This partial vacuum prevents contamination sewage treatment out of the room. The air system is monitored by measuring the parameters operation. The results of activity in 2015 obtained a type area average of 23.13 °C, area type B under 23.75 C and C type area below 24.21 °C. Relative humidity value meets standard type A is the area average of 42.57 %, an average type B and type C 49.76 % Average 53.05 %. Negative pressure according to the standard required in each zone. Pressure drop of the HEPA filters are used for one year the average below 105 onshore at zona 2 and 3, below 90 dapa on zona 4. (author)

[en] Ventilation and Air Conditioning Systems in the Radioactive Waste Installation (RWI) serves to keep the room at a state of partial vacuum to the outside air pressure, limit the possibility of contamination, and air treatment before existing through the chimney. When operating, VAC Off-Gas system using the controls on-off relay. Measurement of operating parameters is done periodically using portable measuring instrument. Control and monitoring is less effective that need to be changed to a newer technology. Change control system of on-off control to the control-based Programmable Logic Control (PLC) becomes an attractive solution. To begin with, it should be made the design of VAC control system based PLC. Method done by identifying and inventory needs and make the system work diagram will be applied. Control system design of VAC Off-Gas IPLR need 1515-2 PN CPU components number as 1 piece. Interface Modules IM 155-5PN ET 200MP number as 1 piece. PM 1507 Power supply 24 V/8 A number as 2 pieces. Digital Input Module DI 32 x DC 24 V, 32 Channels in Groups of 16 number as 2 pieces. Digital Output Module DO 32 x 24 VDC/0.5 A; 32 Channels in Groups of 8 number as 2 pieces. Analog Input Module AI 8 X 4 units. Software components are S 7300 and Win CC Flexible 2008 Runtime. On-off control operation connected to the CPU through the input/output devices in the control room while monitoring performance information and measurement instrument operating parameters to the interface module connected via input/output devices. (author)

[en] The manufacturing and testing of the burner furnace of lead melting has been carried out with the resulted results burner that suitable to be used for use in melting furnaces and has been known the optimal work characteristics of the burner on the air pressure is 0.75 bar with a fuel consumption of waste oil in 1248 ml/hour, the temperature of flue 1041 °C, population flames 52 cm and atomizing performance is stable. Population smoke can not be measured because limitations of instrument. (author)