Nuclear Supervision Research Articles

Производственный травматизм: анализ основных причин и перспектив снижения

Instability of the occupational injuries dynamics in recent years determined the need to improve the system of its prevention and a corresponding reduction in the injuries number. The study is devoted to the analysis of statistical data on fatal injuries at the facilities supervised by the Federal Environmental, Industrial and Nuclear Supervision Service of Russia. The analysis showed that the largest number of fatal injuries occurred at the electrical installations corresponding to the 6–35 kV voltage class, and the most traumatic professions in the power industry include: electrician — 66 % of all fatal injuries, electrical fitter and foreman — per 8 % for each profession. The analysis of the period duration that passed from the moment of checking knowledge on occupational safety to the moment of the injury allowed to conclude that it is required to improve approaches to training employees on occupational safety, due to the fact that the maximum level of fatal injuries is fixed after 1–3 months that passed since the moment of checking knowledge on occupational safety. The analysis of factors significant from the point of view of the risk of injury was carried out, and the most common technical and organizational reasons were identified based on the results of the investigation of injuries. The study substantiates the most promising areas of measures to reduce occupational injuries, and proposes the recommendations for improving such basic procedures of the occupational safety management system at enterprises as training employees in occupational safety, and assessing occupational risks. At the same time, it is required to consider that many procedures of the occupational safety management system, including training of employees in occupational safety, conducting a special assessment of working conditions and assessing occupational risks, are carried out by the enterprises with the involvement of the third-party organizations providing services in the field of occupational safety. Therefore, the main areas of measures to reduce the level of occupational injuries include not only the development of recommendations for the prevention of injuries and the reduction of occupational risks for employers, but also measures to stimulate the motivation of employees for safe work, as well as improving the quality of services of the third-party organizations in the field of occupational safety.

Обоснование безопасности ядерной энергетической установки модернизированного плавучего энергоблока при внешних воздействиях

Object and purpose of research. This paper discusses an upgraded floating nuclear power plant (NPP) to justify its nuclear and radiation safety under external effects. Materials and methods. The authors follow the methods of system analysis. Main results. Following the requirements of Russian Maritime Register of Shipping (RS) and Federal Service for Ecological, Technological and Nuclear Supervision (Rostekhnadzor) to the safety of upgraded floating NPP reactors, this study explored the incidents related to external loads on floating NPPs, drawing up the list of initiating events and their respective probabilities of occurrence, as well as predicting final states of floating NPPs and their reactors as per the data on hull and equipment damage, with the assessment of corresponding radiation hazards. Conclusion. Nuclear and radiation safety justification of upgraded floating NPP was justified as per the regulations in force and Krylov State Research Centre procedures. If an icebreaker rams the reactor compartment of upgraded floating NPPs at the speed exceeding 6.5 knots, primary coolant circuit might leak, thus triggering a radioactive discharge into sea water that might create a contaminated spot up to 325 m in size. The worst-case scenario in terms of radiation hazard is a hypothetical (unlikely) off-design case of a medium-range airliner crash onto the upgraded floating NPP destroying all reactor protection barriers, so all humans within the range of 3.8 km might receive dangerous radiation doses and all population within the range of up to 20 km will have to be evacuated.

Анализ часто встречающихся нарушений обязательных требований в сфере деятельности Ростехнадзора за период 2016–2022 гг.

The results of studies of frequent violations of mandatory requirements in the field of activity of the Federal Environmental, Industrial and Nuclear Supervision Service for the period 2016–2022 are presented. The main approaches used to analyze data in this area, which are found in the domestic and international practice, are described. Using the methods of structuring the collected materials considering the division into groups and subgroups in accordance with a certain criterion presented in the source data, and arranging the data in the required order, the causes and types of identified violations are investigated. The enlarged groups of violations detected by different types of state supervision (in the field of nuclear energy use, energy supervision, construction supervision, industrial safety supervision) are identified. The purpose of the study is to systematize open data for the period of 2016–2022 for the subsequent identification of the distribution of the number of recorded cases of violations in various sections — according to the severity of the consequences, as a percentage of detected violations by enlarged groups of violations. When checking the data for compliance with the Pareto rule, it is shown that, on the one hand, 13 % of the detected types of violations of mandatory requirements lead to 80 % of the total number of violations detected, on the other hand, 13.3 % of the main causes of violations also lead to 80 % of the total number of violations detected. The parameters of the presented open data are identified, the completion of which can lead to a refinement of the obtained values in the analysis of the identified violations, as well as the key types of violations, for which there are no well-developed methods for assessing the risk of consequences and the severity of negative consequences.

О научно-производственном семинаре взрывников Урала

The article presents information on the outcomes of the scientific and practical workshop on drilling and blasting operations in surface and underground mines and special blasting operations, which was organized by the Blasting Specialists of the Urals Association and held on May 26, 2022, at the Museum Complex of the Urals Mining and Metallurgical Company in the City of Verkhnyaya Pyshma with participation of the Institute of Mining of the Urals Branch of the Russian Academy of Sciences and the Urals Department of the Federal Service for Environmental, Technological and Nuclear Supervision (Rostekhnadzor). The workshop included presentations on the following topics: dedicated blasting operations in explosion bonding of metals and demolition of buildings; experience in working with non-explosive mixtures and devices, including ‒ pulse gas generators in restrained urban conditions; results of development and testing of a method to study the rock mass strength properties during roller-bit drilling of blast holes in open-pits; forthcoming innovations in Federal Law No.116 "On industrial safety of hazardous facilities"; relevance, specific features and conditions of blasting operations below the safety covers; mining and technical conditions of underground operations in the Donskoy GOK mine in Kazakhstan. A tour of the four exhibition centres of the Museum Complex, i.e. those of the military and automobile equipment, the "Wings of Victory" aviation exhibition, the "Ceremonial Regiment" exhibition centre, and the open exhibition site with railway and artillery equipment, was held upon completion of the theoretical part of the event.

The bow tie method in assessing occupational risks

The Ministry of Labor recommendations for assessing occupational risks suggest 13 methods, among which is the bow tie technique. The employer chooses a method for assessing occupational risks, taking into account a large number of parameters, including the degree of danger of works performed and possible consequences of risks. The bow tie method specifies the risks of high-risk production operations and analyzes the effectiveness of safety barriers. The purpose of the study is to apply the "bow tie" method in assessing the occupational risks and to develop ways to minimize them. The method is analyzed on the example of works performed during oil production. We used the statistical data of the Federal Service for Ecological, Technological and Nuclear Supervision to identify the most common causes of accidental hydrocarbon leaks. We modelled incident trees and event trees to assemble bow tie models and analyze security barriers. This method was used to assess the risk of accidental releases of hydrocarbons. The incident tree was developed for the emergency release of hydrocarbons caused by the leakage of hydrocarbons from apparatuses, violations of the integrity of pipelines and tanks, depressurization of flanged and welded joints. Trees of events take into account equipment characteristics, possibilities of the method for assessing probabilities of both hazards and consequences. Security barriers were developed. They can be used in developing ways to minimize and assess risks. For the emergency release of hydrocarbons, the bow tie models show that a whole set of modern safety systems is required to ensure safety during oil and gas treatment operations.

O potrzebie przywrócenia właściwego statusu Radzie do spraw Bezpieczeństwa Jądrowego i Ochrony Radiologicznej

The article covers the issue of the functioning of one of the advisory bodies of central governmental administration, i.e. the Council for Nuclear Safety and Radiation Protection Affairs, which is associated with the President of the National Atomism Agency (PAA), the chief nuclear supervision body in Poland, which is the competent authority in nuclear safety and radiation protection affairs, as defined in the Atomic Law (Prawo atomowe). The article presents the objectives of the functioning of the Council as an advisory body to the nuclear supervision authority on the basis of international and European law and the views of the nuclear energy law doctrine. In relation to the Council, an important role is played by soft law acts, especially the so-called IAEA safety standards. Despite the fact that they are not legally binding, they constitute a valuable and extensive collection of recommendations supporting regional and national legislative activity. The purpose of this study is also a critical analysis of the amendment to the Atomic Law from 2016 in the section relating to changes made to the way of shaping the Council’s make-up. They caused the loss of one of the Council’s most important attributes, i.e. independence in the decision-making process and they deprived the President of the PAA (decision-making body) of influence on shaping its make-up. The changes introduced should be interpreted as an unequivocal negation of the ratio legis of appointing the Council and a significant step backwards in relation to the existing practice and legislative trends in recent years. The author postulates restoring the previous legal solutions as the ones that will allow the Council, the advisory body, to fulfil its function in the right way, really supporting the decision-making authority for which it works.

Statistical risk management analysis for hazardous oil and gas production facilities

Modern production conditions show that labor protection and industrial safety are one of the most important tasks of the government and oil and gas companies. The article aims to analyze the dynamics of accidents and industrial injuries with fatal outcomes that occurred at oil and gas production facilities in 2008-2018. The methods of statistical research were used. These are retro-perspective analysis and Shewhart control charts. The data on fatal industrial injuries in the Russian oil and gas production industry provided by the Federal Service for Environmental, Technological and Nuclear Supervision were used. Having analyzed the maps and identified the points beyond the upper and lower boundaries of average values, the conclusions about the random / systemic nature of damage to the health of workers were drawn. The results allowed us to analyze the risk of fatal injuries, their causes and find ways to reduce them. The effective operation and modernization of the industrial safety management system, constant development and an annual increase in the level of safety at hazardous production facilities is one of the main tasks of managers.

CHANGES JUSTIFICATION IN A CALCULATING METHOD OF LOAD STABILITY OF AUTOMOTIVE HOISTING CRANES AND AUTOMOTIVE MANIPULATOR CRANES BASED ON THE NORMATIVE DOCUMENTS ANALYSIS

Introduction. The main requirement for lifting equipment is a strict compliance with safe operation measures. Therefore, special attention is focused on this issue when designing each unit of the equipment. However, despite the extensive list of the current normative documents and systematic monitoring, according to the annual official reports of the Federal service for environmental, technological and nuclear supervision over recent years the facilities that use lifting structures have high indicators for the number of accidents. In addition, the study of a load stability ratio determining in the design of automotive hoisting cranes and automotive manipulator cranes is particularly relevant at the present time due to a wide development of new lifting equipment as the development of the market for cranes has resulted in the occurrence of new technical issues in design and manufacture this type of lifting equipment. As part of the research work to improve the accuracy of calculating the load stability of automotive hoisting cranes and automotive manipulator cranes based on the analysis of existing normative and technical documents the possible occurrence of the accidents causes due to imperfection of regulatory instructions or non-compliance with regulatory instructions during design manufacturer work was considered.Materials and methods. This article is devoted to the study the fundamental principles of the nominative documents regulating the design and operation of the automotive hoisting cranes and automotive manipulator cranes. Both of the current and archived nominative documents in the field of lifting equipment are considered. Special attention is paid to the issues of determining the load stability of the automotive hoisting cranes and automotive manipulator cranes.Discussion and conclusion. The key differences in the calculating method of the load stability of the automotive hoisting cranes and automotive manipulator cranes are highlighted. The accidents statistics of load-lifting mechanisms and lifting structures of the Federal service for environmental, technological and nuclear supervision are given. The main causes of lifting equipment accidents are highlighted. The ways of solving the modernization of the existing methodology for determining the load stability of automotive hoisting cranes are proposed by including previously unrecorded factors related to the technical features of the chassis which contributes to improving the accuracy of the obtained values of the load stability ratio.

The Use of Geodetic Methods in the Technical Examination of Hydraulic Structures from Soil Materials

In our country, particular attention is paid to the safety of operating hydraulic structures, operational reliability of which is an integral part of the overall security of the Russian Federation. The security and energetic efficiency of hydraulic structures is regulated by the Town Planning Code of the Russian Federation, federal laws, and the code of rules “Hydrotechnical Structures. Key Points” [1-4]. Recommendation on the implementation of federal state construction supervision by officials of Rostekhnadzor (Federal Environmental, Industrial and Nuclear Supervision Service of Russia) during the construction and reconstruction of hydraulic structures are contained in methodological recommendations [5, 6]. Investigation of the operational reliability of soil hydraulic structures issue and the development of measures to extend the established term of their operation is a pressing challenge. To solve this challenge, the technical examination of hydraulic structures from soil materials, which allows us to assess the state of strength properties and the stress-strain state of dams, dikes, etc. is of great importance.The vast majority of soil dams are checked only visually, which does not allow to reliably assess their strength properties. To determine the development of infractions in the body of the dam, to determine the amount of washed soil at hydraulic structures, etc. geodetic methods of research can be used, which, compared to the visual methods, are more accurate.In order to determine the capabilities of geodetic methods for determining the volume of washed soils at hydraulic structures, the authors carried out experimental work to determine the volume of washed soils of the coast protection structure “Gluhaya Damba” (“Deaf Dam”) in the ash-disposal area near Zaimskiy island in the Omsk region.

Regulatory framework of the new NPI technological platform

In the nuclear industry, the practical implementation of innovative projects of reactor facilities, such as NPP projects with the BN-1200 and BREST-300 reactors being developed within the new nuclear energy technological platform (NTP), is impossible without the adaptation of the existing or the creation of a corresponding new regulatory and legal framework. After the project development and licensing, the manufacture of separate elements, the NPP construction, commissioning and operation at all stages should be based on federal norms and rules (FNR) in the field of the atomic energy use. Another essential part of the work in the creation of innovative reactor facilities is scientifically based computer simulation to confirm the safety of the decisions made. The requirement to implement safety justifications with the use of software that has passed the relevant expertise is fixed at the legislative level. Thus, the processes of developing innovative NPP projects, new FNRs and advanced software (next-generation codes) should go almost simultaneously. Within the NTP framework IBRAE RAN, in collaboration with the scientific and design and engineering organizations of the industry, are developing new precision generation calculation complexes, describing in a related setting a wide range of physical processes and phenomena. The main features of the new generation software systems are multi-physical and multi-scale modeling. The FNR improvement in favor of the NTP is carried out under close cooperation between professionals and experts of Rostekhnadzor, “Rosatom” State Corporation, scientific organizations of the industry and the Russian Academy of Sciences, as well as innovative projects developers. An example of such effective cooperation is the activity of the working group created by the decisions of the heads of the Federal Service for Environmental, Technological and Nuclear Supervision and the Innovation Management Unit of “Rosatom” State Corporation in September 2015 to coordinate the work on the FNR improvement for the “Proryv” project. The WG members carried out a detailed analysis of the current FNRs and the needs of the “Proryv” Project, which allowed assessing and agreeing on the amount of necessary development of new or updating existing FNRs, as well as the priority of their development. As a result, “The List of Normative Documents regulating safety issues in implementing by organizations of “Rosatom” State Corporation the task of creating fast neutron reactors with a closed nuclear fuel cycle, to be developed or updated with prioritization and timing of their introduction into act” was agreed and accepted for further organization of work. To date, the editions of the priority FNRs have been developed and are being implemented. To detail the FNR requirements, a set of standards of “Rosatom” State Corporation has been developed and is being now approved. Thus, a reasonable approach is realized in the creation of innovative facilities, the technical solutions in which are adopted in accordance with the achieved level of science and technology and at the development stage naturally outrun existing norms and rules.

АНАЛИЗ МЕТОДОВ И СРЕДСТВ КОНТРОЛЯ ЗАЩИТНЫХ СООРУЖЕНИЙ МАГИСТРАЛЬНЫХ ТРУБОПРОВОДОВ

The purpose of research is to justify methods and means of remote sensing for monitoring of technical state of various types of main pipelines’ protective structures. An analysis of accidents at main pipelines based on the data of the Federal Service for Ecological, Technological and Nuclear Supervision, as well as the Ministry of Energy of the Russian Federation is given. The analysis revealed that all protective structures are divided into 2 types - engineering and earth structures. The essence of main methods of active remote sensing is described: radar imaging, radar interferometry, aerial, mobile and ground laser scanning. Accuracy characteristics are given. Justification of monitoring methods application for various types of engineering structures is performed.

Cross-Verification of 1D and 3D Models for a VVER-1000 Reactor’s Pressure Chamber Simulated by the KORSAR/CFD Computation Code in the Modes with Asymmetric Loop Operation

The KORSAR/CFD code results from the development of the KORSAR/GP system code certified in 2009 by the Rostekhnadzor (Federal Service for Ecological, Technological, and Nuclear Supervision) as applied to the calculated justification of the safety for VVER reactors. One of the important aspects of the development consists in the introduction of the CFD-module code into functional content for the simulation of spatial turbulent flows in the mixing chambers of reactors using a nested boundary method in the RANS-approximation. The CFD module is combined with a 1D model according to a semi-implicit scheme as a standard code element. Based on the calculations performed for three modes with an asymmetrical equipment operation in the heat-transfer loops of the VVER-1000 reactor, cross-verification has been performed for a 3D model in the CFD approximation, and a quasi-3D-multichannel model of the KORSAR/CFD computation code for the reactor pressure chamber. For cross-verification, the following modes have been chosen: breaking steam pipeline in a steam generator, connecting the main circulation pump while initially operating three pumps at the reactor power of 71% with respect to the nominal value, connecting a pump while initially operating two opposite pumps at the reactor power of 52% with respect to the nominal value. The scenario of the chosen modes is characterized by a decrease in the heat-carrier temperature at the entry into the pressure chamber from a single loop, which leads to an asymmetric increase in the reactor power with respect to the fuel assemblies owing to a negative reactivity effect. It is shown that, because of the artificial increase in the resistance to the downward heat-carrier flow along the channels that represent a pressure chamber in the multichannel calculation scheme, the reproduction of a spatial in-chamber flow pattern obtained using the 3D model of the chamber and its effect exerted on temperature change in the course of the heat-carrier stirring have been gained. The results of calculation using this scheme are in good agreement with data obtained by means of the 3D simulation of the pressure chamber in the CFD approximation in all the considered modes. A sensitivity of the calculation results with respect to changes in the calculation scheme under using the quasi-3D multichannel model of the reactor chamber is demonstrated.

Three-Dimensional Simulation of a VVER-1000 Reactor’s Pressure Chamber in the Modes with Asymmetrical Loop Operation Using a KORSAR/CFD Computation Code

The KORSAR/CFD code results from the development of the KORSAR/GP system code certified in 2009 by the Rostekhnadzor (Federal Service for Ecological, Technological, and Nuclear Supervision) as applied to the calculated justification of the safety for VVER reactors. One of the important aspects of development consists in the introduction of the CFD-module code into functional content for the simulation of spatial turbulent flows in the mixing chambers of reactors using a nested boundary method in the RANS-approximation. The CFD module is combined with a one-dimensional model according to a semi-implicit scheme as a standard code element. Calculation results using the KORSAR/CFD code are presented for the following three modes with the asymmetrical operation of a VVER-1000 reactor’s flow-circuit loops. They consist in breaking the steam pipeline in the steam generator, in connecting the main circulation pump while initially operating three pumps at the reactor power of 71% with respect to the nominal one, and in connecting a pump while initially operating two opposite pumps at the reactor power of 52% with respect to the nominal one. The calculations have been carried out based on the input data file for the NPP power unit with a VVER-1000 developed by the specialists in VVER design at OKB Gidropress, the Chief Designer in the field of VVER reactor units. A three-dimensional simulation of coupled neutron-physical and thermohydraulic processes in the reactor core has been performed. A thermohydraulic model of the reactor core has been used in a channel-by-channel approximation and a program block for the calculation of three-dimensional neutron kinetics. In the problems under consideration, the three-dimensional simulation domain for the CFD module includes four inlet manifolds and a part of the reactor pressure chamber before entering the holes in the elliptical bottom of the shaft. The holes in the elliptical bottom and the area beyond the shaft up to the outlet manifolds have been represented by the elements of a one-dimensional model. Based on the results of the calculations, the heat-carrier flow pattern in the reactor pressure chamber has been analyzed. A flow pattern effect exerted on the dynamics of the liquid temperature distribution at the entry into the fuel assemblies of the core and on the energy release power of the fuel assemblies in the simulated modes has been demonstrated.

Correcting the Semi-Implicit Numerical Scheme Incorporated in the KORSAR Code Two-Liquid Model

Two algorithms used to correct the semi-implicit numerical scheme for time integration of the conservation equations incorporated into the KORSAR/GP computer code two-liquid model are presented. The KORSAR/GP code has been developed jointly by specialists of the Federal State Unitary Enterprise Aleksandrov Research Institute of Technology and Gidropress Experimental Design Office; in 2009, the code was certified at the Federal Service for Environmental, Technological, and Nuclear Supervision (Rostekhnadzor) as applied to numerical safety assessment of VVER-based reactor plants. In the semi-implicit scheme, the convective terms appearing in the phase momentum conservation equations are written in an explicit form. The mass and energy flows of the phases are represented implicitly with respect to phase velocities, and the transferred donor quantities are calculated based on the parameters taken from the previous time layer. Owing to linearization of unsteady and source terms, the linear system of finite difference equations is solved in a noniteration manner. The first of the presented algorithms compensates for numerical imbalances of phase masses and energies resulting from linearization of unsteady terms appearing in the discrete equations and ensures conservativeness of the scheme. The second algorithm introduces correction for the nonphysical redistribution of coolant mass and energy over the computational cells if a change occurs in the phase motion direction within a time step when the scheme of approximating the convective terms becomes “antidonor” with respect to flow. The numerical imbalances and refinements taking into account the correction of donor quantities are computed at each time step according to the proposed correlations and are used for making compensation at the next time step as supplementary sources in the conservation equations. Results from testing the correction algorithms in the KORSAR/GP code are presented. The effectiveness of the imbalance compensation algorithm is confirmed by solving a problem involving the natural circulation loop heating process. The adequacy of the “antidonor” scheme correction algorithm is demonstrated on problems involving steplike initial distribution of the scalar parameters of a stagnant single-phase gaseous or water coolant in a horizontal tube when the flowrate at the tube inlet has different signs at different time steps.

Ecological and Economical Violations as a Threat for Sustainable Development and National Environmental Safety (on Example of Kemerovo Region)

The article considers the analytical and statistical materials unfolding parameters of economic and ecological crime in Kemerovo Oblast. The close interrelation of quality indicators of the presented groups of crime is caused by the specifics of the coal-mining region. The illegal coal-mining developing in the territory of Kemerovo Oblast within the decades led to the irreversible ecological effects: pollution of rivers, air, soil, deforestation, etc. The administration of Kemerovo Oblast and the enterprises of the coal-mining industry paid attention to the problem not bringing desirable results. Formed in 2011 upon the request of the governor of Kemerovo Oblast the Prosecutor’s Office on the supervision of respecting the rule of law in the coal-mining industry combines the efforts of Rostekhnadzor (the Federal Service for Ecological, Technological and Nuclear Supervision) and Rosprirodnadzor (the Federal Service for Nature Management Supervision) for the prevention of proliferation of crimes in this sphere. Kemerovo State University combines the efforts of scientific community, executive authorities, public organizations and not indifferent residents of Kemerovo Oblast to recognize and prevent economic and ecological offenses. Kemerovo State University has been regularly holding the ecological and tax forums on its basis in recent years. They let bring the factors causing threat of the national security of the region and country in general to the authorities and the public.

Итоги реализации Водной стратегии Российской Федерации применительно к обеспечению безопасности гидротехнических сооружений

On the basis of the performed analysis of the annual State reports “On the status and use of water resources of the Russian Federation, annual reports of the Federal Service for Ecological, Technological and Nuclear Supervision, and the data of the Russian Register of Hydraulic Facilities the outcomes of the Water Strategy of the Russian Federation implementation with reference to securing of hydraulic facilities safety are presented as current by the end of 2017. Analysis of the data on conditions of hydraulic facilities by the regions and Federal districts of the Russian Federation has been carried out. The results of quantitative assessment of the implementation of measures aimed to attaining of the hydraulic facilities adequate level of safety have been considered. Comparative analysis of the hydraulic facilities safe state establishing by years has been done.

Development of approaches to estimation of risk parameters

To a great extent, safety is ensured in the design and operation of hazardous production facilities (HPF) through identifying, analyzing and predicting the risk of accidents (failures), involving, where possible, a more complete quantitative risk estimation in determination of the HPF condition [1], which is the responsibility of the Federal Service for Environmental, Technological and Nuclear Supervision (Rostechnadzor). Among the HPFs, where multifactor risks exist at the stage of design, a special place is occupied by nuclear power installations, shelf development facilities, oil and gas platforms, as well as critical infrastructure facilities as the assets essential for the healthy state of society and the national economy in conditions of impacts from the catastrophic risk factors [2–4].The issues involved in the estimation and prediction of hazards from unfavorable situations, emergencies, accidents and failures are considered in [2,3,5–7] where the safety of HPFs is defined by two major factors: probability of an unfavorable event (situation) and the damage from such event, using different risk identification methods, including recent advances in the asymptotic theory of the probability of extreme values.To solve the risk estimation problems, issues involved in the estimation of risk parameters have been considered with different options of the HPF state graphical space interpretation. Peculiarities of estimating the risk sensitivity and the risk degree have been described and the evolution of approaches to the estimation of risk in the HPF design and operation has been shown. Big data analysis methods for risk management have been proposed.

Методы анализа и способы минимизации технологических и технических рисков энергопредприятия

Objective: Identifying an accurate quantitative risk assessment. FEC (Fuel and Energy Complex) plants are a high-risk area as they may cause manmade disasters, various accidents, pose a threat to human life and environment. In addition, the Russian energy industry is noted for its high complexity and social responsibility. Its specific feature is that it is not always possible to make an accurate quantitative risk assessment reasonably in advance and its degree determination methods are not well enough developed. In view of the above, there are some difficulties in minimizing the risks and estimating risk management costs. There has been a recent trend in improved current legislation on industrial safety and Rostechnadzor (Federal Environmental, Industrial and Nuclear Supervision Service of Russia) oversight and supervision activity practice toward implementing a risk-based approach using the risk analysis methods. It allows optimizing the methods and frequency of inspections made by regulatory bodies depending on the risk level of facilities supervised. Methods: The (accident) risk analysis is performed as a certain scientific justification set forth using qualitative and quantitative analysis of a potential accident likelihood, consequences of its occurrence, and identification of the weakest points in the engineering system or complex. Using fault tree analysis, this article identifies hazards and assesses the high-pressure gas pipeline loss of containment risk, one of the events possible for an energy provider in operation. Results: Based on the risk analysis, there has been a proposal to replace gland seal valves with bellows seal valves noted for their optimum relationship between the unit reliability, cost and sophistication level. In case the facilities with gland seal valves remain in operation, improved production process monitoring is recommended using gas leak detectors and automatic interlocking devices. Practical importance: The measures proposed will allow minimizing the gas pipeline loss of containment risk.

Constitutionality of Nuclear Power Supervision Act

Constitutionality of Nuclear Power Supervision Act

Сетевой университет в сфере промышленной, ядерной и энергетической безопасности

The article gives information on the establishment of a network university in the field of industrial, nuclear and energy security by the Federal Service for Environmental, Technological and Nuclear Supervision and six Russian universities. The goals and objectives of the network university, the organization of its work and educational and methodological support are considered. The proposals of the federal educational and methodological association «Technospheric Security and Environmental Management» for the creation of master’s educational programs on industrial safety within the framework of the direction 20.04.01 “Technosphere security” are given.