The SNESK program implements the approach described in [1][2][3] for calculating first-loop coolant leakage through the pipe board or collectors into the boiler water of a steam generator of a nuclear power plant with a VVI~R reactor.The algorithm is based on an analysis of a system of linear differential equations describing mass transfer of radionuclides through the second-loop systems of a nuclear power plant with VVI~R reactors. The case when all quantities appearing in the model are stationary random functions, which is important for practical applications, was studied. In the present version of the program it is assumed that the interaction between separate steam generators through the general systems is negligibly small, and the steam generator itself is a system with ideal mixing. The point and interval estimates of the leakage and flow rate of the blow-through water are calculated on the basis of a regression analysis of a model of the process being investigated, the input data, and the errors in these data. An important feature is the possibility of calculating leakage in the absence of reliable information about the flow rate of the blow-through water for cleaning.The leaks are calculated on the basis of a periodically measured specific activity of 131-135I, 24Na, and 42K in the first-loop coolant and in the boiler water of a steam generator, taking into account the reliability of these data (errors of measurement). For this list only data on radionuclides whose activity is measured with an error of not greater than 30% are used.When the flow rate of the blow-through water for cleaning is known, information about the activity of one radionuclide is sufficient to estimate the leakage. However, the error of the estimated leakage decreases as the number of radionuclides employed increases.In the absence of data on the flow rate of the blow-through water of the steam generator for cleaning, information about more than two radionuclides is used to calculate the leakage. The following technological parameters of the operation of a steam generator are used in the calculation: steam production, moisture content of the steam, the mass of the boiler water, and the flow rate of the blow-through water for cleaning (if it is measured). The data from the measurements, the name of steam generator, and required comments are also introduced into the program.The computational results are displayed on a monitor screen and are also printed out. The following information is displayed on the monitor screen: the name of the steam generator and the power-generating unit of the nuclear power plant, the date of the calculation, the average leakage, the confidence interval for the leakage, the flow rate of the boiler water for cleaning, the confidence interval for the flow rate of the boiler water for cleaning, and an estimate of the leakage for each of the reference radionuclides. In addition, visual and sound signals are given in the case when the leakage exceeds a limiting value or the quality of the input data is not satisfa...