Patent Number: 051397340
Section: summary

BACKGROUND OF THE INVENTION 1. Field Of The Invention The present invention relates to the field of decontamination of nuclear reactor primary systems. More specifically, it relates to an improved method of processing resin used in chemical decontamination methods. 2. Description Of The Prior Art The problem of excessive personnel exposures caused by high background radiation levels in a nuclear reactor primary system, such as in pressurized water reactor (PWR) systems, and the resultant economic cost of requiring personnel rotation to minimize individual exposure is significant at many nuclear plants. These background levels are principally due to the buildup of corrosion products in certain areas of the plant. The buildup of corrosion products exposes workers to high radiation levels during routine maintenance and refueling outages. The long term prognosis is that personnel exposure levels will continue to increase. As a nuclear power plant operates, the surfaces in the core and primary system corrode. Corrosion products, referred to as crud, are activated by transport of the corroded material to the core region by the reactor coolant system (RCS). Subsequent release of the activated crud and redeposition elsewhere in the system produces radiation fields in piping and components throughout the primary system, thus increasing radiation levels throughout the plant. The activity of the corrosion product deposits is predominately due to Cobalt 58 and Cobalt 60. It is estimated that 80-90% of personnel radiation exposure can be attributed to these elements. One way of controlling worker exposure, and of dealing with this problematic situation, is to periodically decontaminate the nuclear reactor primary system using chemicals, thereby removing a significant fraction of the corrosion product oxide films. Prior techniques had done very little to decontaminate the primary system as a whole, typically focusing only on the heat exchanger (steam generator) channel heads. Two different chemical processes, referred to as LOMI (developed in England under a joint program by EPRI and the Central Electricity Generating Board) and CAN-DEREM (developed by Atomic Energy of Canada, Ltd.), have been used for small scale decontamination in the past. These processes are multi-step operations, in which various chemicals are injected, recirculated, and then removed by ion-exchange. Although the chemicals are designed to dissolve the corrosion products, some particulates are also generated. One method of chemical decontamination, focusing on the chemistry of decontamination, is disclosed in U.K. Patent Application No. GB 2 085 215 A (Bradbury et al.). There is little disclosure, however, of the methodology to be used in applying that chemistry to system decontamination. While these chemical processes had typically been used on only a localized basis, use of these chemical processes has now been considered by the inventors herein for possible application on a large scale, full system chemical decontamination. Such an application is disclosed generally in co-pending Application Ser. No. 07/621,120 Nov. 26, 1990, entitled "System For Chemical Decontamination Of Nuclear Reactor Primary Systems", and incorporated herein by reference. While some work has been done in the boiling water reactor (BWR) programs, the BWR scenarios examined by those in the field involved only decontaminating fuel assemblies in sipping cans employing commercial processes at off-normal decontamination process conditions with little regard for the effects of temperature, pressure, and flow that would be mandated by an actual application of the process to the full reactor system. The estimated collective radiation dose savings over a 10-year period following decontamination is on the order of 3500-4500 man rem, depending upon whether or not the fuel is removed during decontamination. At any reasonable assigning of cost per man-rem, the savings resulting from reduced dose levels will be in the tens of millions of dollars. As a result of the present examination of potential full system decontamination, and the resulting need for new sub-system methods, developments have been made by the assignor of this invention to use demineralizing resin beds in conjunction with the known chemical processes. These developments are set forth in co-pending application Ser. No. 07/621,129 filed Nov. 26, 1990, entitled "Clean-up Sub-system for Chemical Decontamination of Nuclear Reactor Primary Systems," and incorporated herein by reference. Due to the large water volume to be treated within such a full system decontamination process, an in-line clean-up sub-system using filters and demineralizers is used for efficient dissolved chemical and crud removal. However, the quantity of resin required for effective decontamination is so large that the number of demineralizer vessels that would be needed to hold the entire required amount of resin is cost-prohibitive. As a further result, a need now exists for a system to transfer fresh and spent resin from demineralizers to be used within the decontamination process. Heretofore, an in-line sub-system for removing activated crud had not been needed nor developed. The wholly new need for a system to transfer resin requires a wholly new development unanticipated by any existing art. Accordingly, there exists a need for a method and apparatus for optimizing the delivery and use of resin within the proposed full system chemical decontamination processes. SUMMARY OF THE INVENTION The present invention is directed to a resin processing system for use within a chemical decontamination system for full nuclear reactor primary system decontamination. To this end, a limited number of demineralizer vessels are utilized in conjunction with a fresh resin supply tank, large enough to supply all needed resin for a particular decontamination step, and a batching tank sized to deliver an appropriate amount of fresh resin to a particular demineralizer bed when so desired. A sluice water supply tank is utilized to supply water to each demineralizer for removal of spent resin from each such demineralizer. The spent resin is then delivered to a spent resin storage tank and the sluice water is withdrawn from the storage tank for recycling. After a particular decontamination process step is completed, the spent resin collected within the spent resin storage tank can be removed for ultimate disposal. Accordingly, it is an object of the present invention to provide a resin processing system to economically process resin within a chemical decontamination process to be used on nuclear reactor systems. These and further objects and advantages will be apparent to those skilled in the art in connection with the detailed description of the invention that follows.