Radioactive waste treatment system

This section should provide relevant information on the radioactive waste treatment systems as described in paras 3.65-3.70. It should include the design features of the plant that safely control, collect, handle, process, store and dispose of solid, liquid and gaseous forms of radioactive waste arising from all activities on the site throughout the lifetime of the plant. This should include the structures, systems and components provided for these purposes and also the instrumentation incorporated to monitor for possible leaks or escapes of radioactive waste. The potential for radioactive waste to be adsorbed and/or absorbed should be considered in deciding on the measures necessary to deal with this hazard. Further discussion on matters to be covered in this section of the SAR is provided in Ref. [32]. 

This section may need to cross-reference the section of the SAR in which radiation protection issues for the plant are considered. This section may also refer to other sections of the SAR in which the operational aspects of radioactive waste management are considered in detail. 

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Section II of Appendix I also includes a numerical cost-benefit guideline to judge the necessity for additional improvements in radioactive waste treatment systems. This guideline has not been included as a top-level regulatory criterion as it is not a direct statement of acceptable health or safety consequence or risk to the public. Similarly, the other operative... 

Down sizing of radioactive waste treatment system... 

From a construction point of view the radioactive waste treatment system has been removed from seismic I category building and its components have been simplified and optimized as much as possible for modularization. 

The radioactive waste treatment systems provides all equipment necessary to coUect, process, monitor, and dispose of radioactive gaseous, liquid, and solid wastes that are produced during reactor operation. 

The design and the operation (see para. 7.104) of the research reactor shall be such as to minimize the generation of radioactive waste. Treatment systems for radioactive waste shall include adequate provisions for control and monitoring to keep releases as low as reasonably achievable and below authorized limits. 

Other reactor systems 60% by reducing the radioactive waste treatment systems, etc. 

Radioactive waste treatment system Available, similar to that of a BWR... 

It has been demonstrated that membrane separation processes can be successfully used in the removal of radioactive substances, with some distinct advantages over conventional processes. Following the development of suitable membrane materials and their long-term verification in conventional water purification, membrane processes have been adopted by the nuclear industry as a viable alternative for the treatment of radioactive liquid wastes [1]. In most applications, membrane processes are used as one or more of the treatment steps in complex waste treatment systems, which combine both conventional and membrane treatment technologies. These combined systems have proved more efficient and effective for similar tasks than conventional methods alone. 

The RO process was implemented at the Institute of Atomic Energy, Swierk. The wastes collected there, from all users of nuclear materials in Poland, have to be processed before safe disposal. Until 1990 the wastes were treated by chemical methods that sometimes did not ensure sufficient decontamination. To reach the discharge standards the system of radioactive waste treatment was modernized. A new evaporator integrated with membrane installation replaced old technology based on chemical precipitation with sorption on inorganic sorbents. Two installations, EV and 3RO, can operate simultaneously or separately. The membrane plant is applied for initial concentration of the waste before the evaporator. It may be also used for final cleaning of the distillate, depending on actual needs. The need for additional distillate purification is necessitated due to entrainment of radionuclides with droplets or with the volatile radioactive compounds, which are carried over. 

There are many examples of the studies on SLM for nuclear applications in the literature. SLMs were tested for high-level radioactive waste treatment combined with removal of actinides and other fission products from the effluents from nuclear fuel reprocessing plants. The recovery of the species, such as uranium, plutonium, thorium, americium, cerium, europium, strontium, and cesium, was investigated in vari-ons extracting-stripping systems. Selective permeation... 

Release of radioactive material from a subsystan or component overheating of or damage to used fuel in transit or storage break in a gaseous or liquid waste treatment system. 

The radioactive waste management system of the QP300 consists of gaseous waste treatment system, liquid waste treatment system, solid waste treatment and storage system and radioactive waste solidification system. 

The gaseous waste treatment system prowdes storage of radioactive effluent until it decays down to a value allowable for discharge to the environment through the HEPA filter and iodine filter into the plant stack. 

The liquid waste treatment system collects, processes and monitors all potentially radioactive liquid waste produced during normal plant operation and maintenance. The liquid effluent is discharged, reused or finally disposed in the plant according to its radioactive level. 

The structural complex at the center of the plant comprises the reactor building and the turbine building. The second complex contains the switchgear equipment, the systems for radioactive waste treatment and storage, the hot workshop, staff amenities, the main control room and the entrance to the controlled access area. The third structural complex consists of the plant service systems the circulating water supply systems, the emergency diesel generators, the cold workshops and the demineralized water system. 

The ATS-150 is equipped with a system for radioactive waste treatment, an auxiliary feed water system, and other supporting systems of standard design ensuring appropriate operation of a nuclear power plant. 

Following an accident, auxiliary systems may have to deal with high radioactive water and the potential exists for an unexpected release to the environment. In addition, waste treatment systems may have to process beyond design radioactive releases. 

Scrub solutions used for off-gas cooling or cleanup, together with all condensates and purge streams, should be collected, treated and returned to the scrubbing process. There shall be no direct pathway for active liquids to the environment. The scrub solution system blowdown should be treated by a radioactive liquid waste treatment system. In some instances the blowdown may be processed (e.g. dried) in the incineration system. 

In practice, these design targets can be addressed independently, although in principle any enhancement of waste treatment systems to reduce the releases of radioactive substances to the environment may result in additional work being carried out by site personnel with a consequent increase in their exposures. In providing the best practicable means for reducing releases, the imphcations for the exposures of site personnel should be monitored to ensure that there is no undue increase. 

The equipment in treatment systems for solid, liquid and gaseous radioactive waste may contain radioactive material in high concentrations, and radiation protection from this material should be provided for site personnel. An estimate should be made of the expected radionuclide content in treated waste, and of the consequent maximum radiation level that can arise in each area of the waste treatment system. Consideration should be given to the sources that give rise to the highest radiation levels (such as ion exchange... 

For water that cannot be recycled into the plant, provision should be made to reduce its radioactive contamination to such levels that the design target doses and discharge limits discussed in Section 2 are met. If necessary, reduction of the radionuclide content of the water can be achieved by means of several passages of the water through the liquid waste treatment system. 

In LWRs, before treatment some of the hquid wastes may have a radionuclide content as high as that of the reactor coolant, with the exception of short lived nuclides, which will have decayed, and gases, which will have been evolved as a result of depressurization. Concentrations of up to a few 10 Bq/ m may be found in such untreated liquids. Thus, since the liquid waste treatment system processes active liquids, radioactive substances will... 

III-2. Account needs to be taken of the possibility of radioactive material accumulating on and being released from air filters or components of the liquid waste treatment system after accidents. In comparison with the radiation emanating from fission products and actinides, activation products are usually of minor importance. 

According to the vendor, the FE ACTIVE system is not applicable to nonvolatiles, inorganic or radioactive wastes in groundwater or soil. Contaminants recovered by the FE ACTIVE system will require additional treatment or disposal. 

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