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  1. Safety Regulation Implemented by Gosatomnadzor of Russia

    International Nuclear Information System (INIS)

    Gutsalov, A.T.; Bukrinsky, A.M.

    2001-01-01

    The principles and approaches used by Gosatomnadzor of Russia in establishing safety goals are described. The link between safety goals and safety culture is demonstrated. Information on nuclear regulatory activities in Russia is also presented

  2. THE NUCLEAR MATERIAL MEASUREMENT PROGRAM PLAN FOR GOSATOMNADZOR OF RUSSIA

    International Nuclear Information System (INIS)

    Bokov, Dmitry; Byers, Kenneth R.

    2003-01-01

    As the Russian State regulatory agency responsible for oversight of nuclear material control and accounting (MC and A), Gosatomnadzor of Russia determines the status of the MC and A programs at Russian facilites by testing the nuclear material inventory for accounting record accuracy. Currently, Gosatomnadzor is developing and implementing an approach to planning and conducting MC and A inspections using non-destructive assay (NDA) instruments that will provide for consistent application of MC and A measurement inspection objectives throughtout Russia. This Gosatomnadzor NDA Program Plan documents current NDA measurement capability in all regions of Gosatomnadzor; provides justification for upgrades to equipment, procedures and training; and defines the inspector-facility operator interface as it relates to NDA measurement equipment use. This plan covers a three-year measurement program cycle, but will be reviewed and updated annually to ensure that adequate inspection resources are available to meet the demands of the inspection schedule. This paper presents the elements of this plan and describes the process by which Gosatomnadzor ensures that its NDA instruments are effectively utilized, procedures are developed and certified, and inspection personnel are properly trained to provide assurance that Russian nuclear facilities are in compliance with Russian MC and A regulations.

  3. Safety goals and safety culture opening plenary. 2. Safety Regulation Implemented by Gosatomnadzor of Russia

    International Nuclear Information System (INIS)

    Gutsalov, A.T.; Bukrinsky, A.M.

    2001-01-01

    This paper describes principles and approaches used by Gosatomnadzor of Russia in establishing safety goals. The link between safety goals and safety culture is demonstrated. The paper also contains information on nuclear regulatory activities in Russia. Regulatory documents of Gosatomnadzor of Russia do not provide precise definitions of safety goals as IAEA documents INSAG-3 or INSAG-12 do. However, overall activities of Gosatomnadzor of Russia are directed to the achievement of these safety goals, as Gosatomnadzor of Russia is a federal executive authority responsible for the regulation of nuclear and radiation safety in accordance with the Russian Federal Law 'On the Use of Nuclear Energy'. Thus, in the Statement of the Policy of the Russian Regulatory Authority, enacted in 1992, it was established that the overall activities of Gosatomnadzor of Russia are directed to the achievement of the main goal. This goal is to establish conditions that ensure that personnel, the public, and the environment are protected from unacceptable radiation and nonproliferation of nuclear materials. The practical application of such a method as given by the publication of Statements of Policy of Gosatomnadzor of Russia may be considered as a safety culture element. 'General Provisions of NPP Safety Ensuring' (OPB-88/ 97) is a regulatory document of the highest level in the hierarchy of regulatory documents of Gosatomnadzor of Russia. It establishes quantitative values of safety goals as do the foregoing IAEA documents. Thus, this regulatory document sets up the following: 1. The estimated total probability of severe accidents should not exceed 10 5 /reactor.yr. 2. The estimated probability of the worst possible radioactive release to the environment specified in the standards should not exceed 10 -7 /reactor.yr in the case of severe beyond-design-basis accidents. 3. The probability of a reactor vessel failure should not exceed 10 -7 /reactor.yr. The foregoing values are somehow

  4. A Practical MC and A Inspection Training Approach for Gosatomnadzor of Russia

    International Nuclear Information System (INIS)

    Byers, Kenneth R.; Krupchatnikov, B.; Wright, T.; Key, C.; Coady, K.; Kilmartin, W.; Hawkins, R.; Kodman, G.

    2000-01-01

    The Russian nuclear materials control and accounting (MC and A) program has undergone many changes over the last five years. New technologies have been introduced; personnel have been trained; and new regulations are being developed. Gosatomnadzor of Russia (GAN), as the state oversight authority for the control and accounting of nuclear materials used for civil purposes, has the responsibility to assure that nuclear materials are controlled, accounted for, and used only for peaceful and defensive purposes. To ensure that GAN inspectors are fully capable and able to carry out this objective, an extensive training program has been developed. One activity under this program was a practical MC and A training exercise conducted in the U.S. at an Argonne National Laboratory-West (ANL-W) Category I nuclear material facility. This paper describes the development of the exercise in the U.S., the inspection activities conducted, an evaluation of the results, lessons learned, and recommendations for future inspector training programs

  5. US Department of Energy (DOE)/Gosatomnadzor (GAN) of Russia project at the Petersburg Nuclear Physics Institute (PNPI)

    International Nuclear Information System (INIS)

    Baranov, I.A.; Konoplev, K.A.; Hauser, G.C.

    1997-01-01

    This paper presents a summary of work accomplished within the scope of the DOE-Gosatomnadzor (GAN) Agreement to reduce vulnerability to theft of direct-use nuclear materials in Russia. The DOE-GAN agreement concerns the Russian Academy of Science B.P. Konstantinov Petersburg Nuclear Physics Institute (PNPI), located 45 kilometers from St. Petersburg. The PNPI operates facilities to research basic nuclear physics. Current world conditions require particular attention to the issue of Material Protection, Control, and Accounting (MPC ampersand A) of nuclear materials. The long-term plan to increase security at the facility is outlined, including training, physical protection upgrades, and material control and accountability. 4 figs

  6. The role of the Gosatomnadzor of Russia in national regulating of safety of radiation sources and security of radioactive materials

    International Nuclear Information System (INIS)

    Mikhailov, M.V.; Sitnikov, S.A.

    2001-01-01

    As at the end of 1999, the Gosatomnadzor of Russia supervised 6551 radiation sources, including 1285 unsealed sources with individual activity from a minimal level to 1x10 12 Bq and a total activity of 585x10 12 Bq, and also 5266 sealed sources with individual activity from 30 to 1x10 17 Bq and the total activity of more than 11x10 17 Bq. A national infrastructure has been created in the Russian Federation in order to regulate the safety of nuclear energy use. The infrastructure includes the legal system and the regulatory authorities based on and acting according to it. The regulation of radiation safety, including assurance of radiation source safety and radioactive material security (management of disused sources, planning, preparedness and response to abnormal events and emergencies, recovery of control over orphan sources, informing users and others who might be affected by lost source, and education and training in the safety of radiation sources and the security of radioactive materials), is realized within this infrastructure. The legal system includes federal laws ('On the Use of Nuclear Energy' and 'On Public Radiation Safety'), a number of decrees and resolutions of the President and the Government of the Russian Federation, federal standards and rules for nuclear energy use, and also departmental and industrial manuals and rules, State standards, construction standards and rules and other documents. The safety regulation tasks have been defined by these laws, according to which regulatory authorities are entrusted with the development, approval and putting into force of standards and rules in the nuclear energy use, with issuing licenses for carrying out nuclear activities, with safety supervision assurance, with review and inspection implementation, with control over development and realization of protective measures for workers, population and environment in emergencies at nuclear and radiation hazardous facilities. Russian national regulatory

  7. Governmental regulation of nuclear power in Russia: Status and development

    International Nuclear Information System (INIS)

    Gordon, B.; Vishnevskij, Yu.G.

    1995-01-01

    Gosatomnadzor is responsible for governmental supervision of nuclear and radiation safety. Its sphere of competence covers nuclear power, research reactors and the nuclear fuel cycle complex, among others. The paper discusses the situation regarding the adoption of the draft Law of the Russian Federation on the Use of Atomic Energy and its basic formulations. The draft Law is based on the principle that priority be given to safety and the protection of human health, the environment and property over any economic interests in the area of atomic energy utilization. The most important respect in which the activities of Gosatomnadzor differ from those of its predecessors is that it has been assigned the functions of the regulatory authority for safety in the utilization of atomic energy. The paper discusses the main functions of Gosatomnadzor. An important task is to set up operating organizations, preparing the requirements for these organizations and monitoring compliance with those requirements. Gosatomnadzor has adopted safety analysis reports as the basic form of documentation to demonstrate the safety of facilities involving nuclear and radiation hazards. Independent assessment of safety and preparation of reference documents for its regulatory activities are other tasks of Gosatomnadzor. (author)

  8. Regulatory aspects and experience with Russian research reactors

    International Nuclear Information System (INIS)

    Morozov, S.I.

    2003-01-01

    Regulatory activity of Gosatomnadzor of Russia in the field of research reactors (RR) safety implies implementing three major aspects: 1) establishing the nuclear and radiation safety standards; 2) licensing; and 3) inspection and enforcement. Relatively recently a full set of safety standards and regulations for RR has been established thus allowing Gosatomnadzor of Russia to effectively implement its designated functions in the field of RR safety. A minimum set of these documents is shown as follows: Level I: Fundamentals: Law 'On the use of nuclear energy'; Law 'On Public radiation protection' Level II: Safety Standard: 'General Provisions for Safety of Research Facilities' Level III: Safety Rules: Nuclear Safety; - Radiation Safety; Waste Management; Safe Decommissioning of RR; Safety Analysis Report; QAP Level IV: Safety Regulations: Licensing (incl. Peer Review and Safety Assessment) - Inspection Gosatomnadzor of Russia has created and regularly updates the database on nuclear research reactors based on the actual status of all facilities. According to the database many facilities have been shutdown during recent years whether temporary or permanently waiting for the final decision on their decommissioning. For example, in 2003 Gosatomnadzor of Russia has 85 nuclear research reactors under its supervision (compared to 113 in 1998). This fact can be explained by three main reasons: 1) experimental program finished and no other programmes in place; 2) lack of resources (financial and human); 3) safety problems (physical obsolescence and ageing of equipment). One of the main difficulties in regulating RR safety is a variety of operating organizations - 21, with different financial and human resource capabilities. Ministries responsible for supporting their operation are of a little help. It becomes obvious that a unified governmental program for RR utilization is urgently needed to decide what number of RR and for what needed purposes is required to support the

  9. Regulation of nuclear materials control and accountability and inspection practices in the Russian Federation

    International Nuclear Information System (INIS)

    Volodin, Y.G.; Dimitriev, A.M.; Krouptchatnikov, B.N.

    1999-01-01

    Review and assessment of the resent state orders and directives regulating nuclear materials control and accountability, defining responsibilities and incorporation of different agencies in nuclear materials control and accountability (MC and A) area in Russia, related actions to stipulate tasks in developing the State System of Accounting for and Control of Nuclear Materials (SSAC) and a role of the Federal Nuclear and Radiation Safety Authority of Russia (Gosatomnadzor) in this process is presented. Main principles, elements and practical results of Gosatomnadzor inspection activities are reported. Elements of the SSAC, status of works in establishment of the SSAC and in implementation of fragments of the SSAC, an international assistance in up-grading MC and A systems at some of the Russian facilities and in establishing the SSAC in Russia is outlined. (author)

  10. Licensing of spent nuclear fuel dry storage in Russia

    International Nuclear Information System (INIS)

    Kislov, A.I.; Kolesnikov, A.S.

    1999-01-01

    The Federal nuclear and radiation safety authority of Russia (Gosatomnadzor) being the state regulation body, organizes and carries out the state regulation and supervision for safety at handling, transport and storage of spent nuclear fuel. In Russia, the use of dry storage in casks will be the primary spent nuclear fuel storage option for the next twenty years. The cask for spent nuclear fuel must be applied for licensing by Gosatomnadzor for both storage and transportation. There are a number of regulations for transportation and storage of spent nuclear fuel in Russia. Up to now, there are no special regulations for dry storage of spent nuclear fuel. Such regulations will be prepared up to the end of 1998. Principally, it will be required that only type B(U)F, packages can be used for interim storage of spent nuclear fuel. Recently, there are two dual-purpose cask designs under consideration in Russia. One of them is the CONSTOR steel concrete cask, developed in Russia (NPO CKTI) under the leadership of GNB, Germany. The other cask design is the TUK-104 cask of KBSM, Russia. Both cask types were designed for spent nuclear RBMK fuel. The CONSTOR steel concrete cask was designed to be in full compliance with both Russian and IAEA regulations for transport of packages for radioactive material. The evaluation of the design criteria by Russian experts for the CONSTOR steel concrete cask project was performed at a first stage of licensing (1995 - 1997). The CONSTOR cask design has been assessed (strength analysis, thermal physics, nuclear physics and others) by different Russian experts. To show finally the compliance of the CONSTOR steel concrete cask with Russian and IAEA regulations, six drop tests have been performed with a 1:2 scale model manufactured in Russia. A test report was prepared. The test results have shown that the CONSTOR cask integrity is guaranteed under both transport and storage accident conditions. The final stage of the certification procedure

  11. NPP Decommissioning: the concept; state of activities

    International Nuclear Information System (INIS)

    Nemytov, S.; Zimin, V.

    2001-01-01

    The main principles of NPP decommissioning concept in Russia are given. The conditions with fulfillment of works on NPP unit pre-decommissioning and decommissioning including: development of the normative documentation, creation of special fund for financing NPP decommissioning activities, deriving the Gosatomnadzor license for decommissioning of shut down NPP units, development of the equipment and technologies for waste and spent fuel management are presented. The decommissioning cost and labour intensity of one WWER-440 unit are shown. The practical works, executed on shut down units at Beloyarsk NPP (Unit1 and 2) and Novo Voronezh NPP (Unit 1 and 2) are outlined

  12. Safety status of Russian research reactors

    International Nuclear Information System (INIS)

    Morozov, S.I.

    2001-01-01

    Gosatomnadzor of Russia is conducting the safety regulation and inspection activity related to nuclear and radiation safety at nuclear research facilities, including research reactors, critical assemblies and sub-critical assemblies. It implies implementing three major activities: 1) establishing the laws and safety standards in the field of research reactors nuclear and radiation safety; 2) research reactors licensing; and 3) inspections (or license conditions tracking and inspection). The database on nuclear research facilities has recently been updated based on the actual status of all facilities. It turned out that many facilities have been shutdown, whether temporary or permanently, waiting for the final decision on their decommissioning. Compared to previous years the situation has been inevitably changing. Now we have 99 nuclear research facilities in total under Gosatomnadzor of Russia supervision (compared to 113 in previous years). Their distribution by types and operating organizations is presented. The licensing and conduct of inspection processes are briefly outlined with emphasis being made on specific issues related to major incidents that happened in 2000, spent fuel management, occupational exposure, effluents and emissions, emergency preparedness and physical protection. Finally, a summary of problems at current Russian research facilities is outlined. (author)

  13. Support in the development of Regulatory Procedures for licensing Lepse Waste Management Operations

    International Nuclear Information System (INIS)

    2001-05-01

    This report describes a project intended to assist Gosatomnadzor of Russia develop a set of documents defining the regulatory requirements for information to be submitted to Gosatomnadzor in support of any application for a licence relating to the removal of spent nuclear fuel from the depot ship Lepse. The project resulted in the development of three regulatory documents covering the documentation required in support of a licence application, the requirements for quality assurance arrangements and the safety analysis report. The working method adopted involved staged development of draft material and review at workshops involving a wide variety of relevant Russian and western organizations. The input and output of the workshops was fully documented to provide an audit trail for the document development and the rationale for what has been included and what is excluded and why. The availability of the regulatory documents in English should significantly assist in the use of the documents by western partners in the actual industrial project. Important experience and information was exchanged among participants in the project. The developing understanding is an important element in providing confidence, from a western perspective, that appropriate regulatory supervision can be applied to industrial projects supported by organizations such as the European Commission and national agencies. The same working methods could be used in the next phase of Lepse regulatory support, i.e., support in development of the procedures for the regulatory review of licence applications, and, subsequently, support in the application of the regulatory inspection process to ensure licence conditions are being complied with. Similarly, these working methods could be used in providing regulatory support for nuclear and radiation safety related to other industrial projects involving radioactive waste management. The participants in this sub-project described in this report were Norwegian

  14. Development and Attestation of Gamma-Ray Measurement Methodologies for use by Rostekhnadzor Inspectors in the Russian Federation

    International Nuclear Information System (INIS)

    Jeff Sanders

    2006-01-01

    Development and attestation of gamma-ray non-destructive assay measurement methodologies for use by inspectors of the Russian Federal Service for Environmental, Technological, and Nuclear Oversight (Rostekhnadzor, formerly Gosatomnadzor or GAN), as well as for use by Russian nuclear facilities, has been completed. Specifically, a methodology utilizing the gamma-ray multi group analysis (MGA) method for determining plutonium isotopic composition has been developed, while existing methodologies to determining uranium enrichment and isotopic composition have been revised to make them more appropriate to the material types and conditions present in nuclear facilities in the Russian Federation. This paper will discuss the development and revision of these methodologies, the metrological characteristics of the final methodologies, as well as the limitations and concerns specific to the utilization of these analysis methods in the Russian Federation

  15. Comprehensive survey of the Russian nuclear industry; Le panorama nucleaire russe

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-01

    This document presents the organization of nuclear activities in the Russian federation: Minatom and its replacement by the federal agency of atomic energy, personnel, nuclear power plants (VVER, RBMK, fast neutron and mixed reactors), availability and power production, export of activities (construction of nuclear power plants in Slovakia, Iran, China, India, project in Viet Nam), expansion of the nuclear power plants park (improvement of plants safety, increase of service life), completion of uncompleted plants, the construction of which was stopped after the Chernobyl accident and the reorganization of the former-USSR, construction of new generation power plants (VVER-640, -1000 and -1500), fuel cycle facilities (geographical distribution, production of natural uranium, conversion and enrichment), fuel fabrication, reprocessing processes and spent fuel storage, management of radioactive wastes (leasing), R and D activities (organizations and institutes), research programs of the international scientific and technical center, nuclear safety authority (Gosatomnadzor - GAN). (J.S.)

  16. Comprehensive survey of the Russian nuclear industry

    International Nuclear Information System (INIS)

    2004-03-01

    This document presents the organization of nuclear activities in the Russian federation: Minatom and its replacement by the federal agency of atomic energy, personnel, nuclear power plants (VVER, RBMK, fast neutron and mixed reactors), availability and power production, export of activities (construction of nuclear power plants in Slovakia, Iran, China, India, project in Viet Nam), expansion of the nuclear power plants park (improvement of plants safety, increase of service life), completion of uncompleted plants, the construction of which was stopped after the Chernobyl accident and the reorganization of the former-USSR, construction of new generation power plants (VVER-640, -1000 and -1500), fuel cycle facilities (geographical distribution, production of natural uranium, conversion and enrichment), fuel fabrication, reprocessing processes and spent fuel storage, management of radioactive wastes (leasing), R and D activities (organizations and institutes), research programs of the international scientific and technical center, nuclear safety authority (Gosatomnadzor - GAN). (J.S.)

  17. Status of the U.S. Department of Energy (DOE) Government to Government Program in Russia

    International Nuclear Information System (INIS)

    Olascoaga, M.T.

    1996-01-01

    The US-Russian Government-to-Government Program of Cooperation on Nuclear Material Protection, Control, and Accounting (MPC ampersand A) evolved from the Nunn-Lugar Cooperative Threat Reduction Program. In 1995, the US Department of Energy (DOE) assumed responsibility as the executive agent for implementation of the Government-to-Government MPC ampersand A Program, followed by the programmatic responsibility for funding. The Russian Program initially emphasized limited exchanges, demonstrations, and upgrades at low-enriched uranium (LEU) fuel fabrication facility at Elektrostal in 1994. The program has expanded to include upgrades at nuclear facilities across Russia, development of the Russian Methodological Training Center (RMTC) in Obninsk; and cooperation with Gosatomnadzor, the Russian Federal Nuclear Radiation and Safety Authority. This paper describes the overall program including program objectives, approach, and US-Russian participation, with an emphasis on DOE-GAN cooperation

  18. Neutron fluence measurement in the cavity of Balakovo nuclear power plant, unit 3

    International Nuclear Information System (INIS)

    Voorbraak, W.P.; Baard, J.H.; Paardekooper, A.; Nolthenius, H.J.

    1996-12-01

    An international benchmark exercise has been organized by the Russian GOSATOMNADZOR. The aim was to reduce the uncertainty of fluence measurements in Nuclear Power Plants in particular VVER-1000 reactors. The benchmark was set up in the cavity of the Balakovo NPP 3. Eight institutes were involved. This report presents the results obtained by ECN. From this report, it can be concluded that the results of the relative large monitor set (13 different reaction rates with overlapping response regions) point to possible imperfections in the calculated neutron spectra. However the experimental information is not powerful enough to reduce the uncertainty of the neutron fluence rate especially in the energy region between 0.1 and 0.5 MeV below 50 percent. (orig.)

  19. The use of the codes from MCU family for calculations of WWER type reactors

    International Nuclear Information System (INIS)

    Abagijan, L.P.; Alexeyev, N.I.; Bryzgalov, V.I.; Gomin, E.A.; Glushkov, A.E.; Gorodkov, S.S.; Gurevich, M.I.; Kalugin, M.A.; Marin, S.V.; Shkarovsky, D.A.; Yudkevich, M.S.

    2000-01-01

    The MCU-RFFI/A and MCU-REA codes developed within the framework of the long term MCU project are widely used for calculations of neutron physic characteristics of WWER type reactors. Complete descriptions of the codes are available in both Russian and English. The codes are verified and validated by means of the comparison of calculated results with experimental data and mathematical benchmarks. The codes are licensed by Russian Nuclear and Criticality Safety Regulatory Body (Gosatomnadzor RF) (Code Passports: N 61 of 17.10.1966 and N 115 of 02.03.2000 accordingly)). The report gives examples of WWER reactor physic tasks important for practice solved using the codes from the MCU family. Some calculational results are given too. (Authors)

  20. Efforts in strengthening accounting for and control of nuclear materials in Russia

    International Nuclear Information System (INIS)

    Dmitriev, A.; Volodin, Y.; Krupchatnikov, B.; Sanin, A.

    2001-01-01

    Full text: Recent state orders, directives, regulations are reviewed as well as practical results of the state system for nuclear material accountancy and control (NMAC) development in the Russian Federation are addressed. Based on the Federal Laws and regulations responsibilities of different agencies related to the NMAC are discussed in view of transforming the existing nuclear material accountancy and control systems to a new system at the federal level. Governmental Orders of 10 July 1998 No.746 and of 15 December 2000 No. 962 assigned Minatom of Russia as the agency in charge of establishing and operating the NMAC at the federal level while Gosatomnadzor of Russia as the agency responsible for the enforcement of the MC and A regulation and for the NMAC oversight functions. Provisions of major regulatory documents that have been or are currently being developed defining requirements, procedures, conditions and agencies' responsibilities in the area of NM control and accounting are addressed. Trends in development of the domestic safeguards system are reported in light of strengthening regulation, inspection infrastructure and licensing of NM use. Incorporation of GAN and the agencies in charge of managing nuclear installations is discussed. Foreign support to the NMAC development in Russia is also reviewed. (author)

  1. Core Benchmarks Descriptions

    International Nuclear Information System (INIS)

    Pavlovichev, A.M.

    2001-01-01

    Actual regulations while designing of new fuel cycles for nuclear power installations comprise a calculational justification to be performed by certified computer codes. It guarantees that obtained calculational results will be within the limits of declared uncertainties that are indicated in a certificate issued by Gosatomnadzor of Russian Federation (GAN) and concerning a corresponding computer code. A formal justification of declared uncertainties is the comparison of calculational results obtained by a commercial code with the results of experiments or of calculational tests that are calculated with an uncertainty defined by certified precision codes of MCU type or of other one. The actual level of international cooperation provides an enlarging of the bank of experimental and calculational benchmarks acceptable for a certification of commercial codes that are being used for a design of fuel loadings with MOX fuel. In particular, the work is practically finished on the forming of calculational benchmarks list for a certification of code TVS-M as applied to MOX fuel assembly calculations. The results on these activities are presented

  2. Regulatory Perspectives on Risk Management for Lepse De-fuelling Operations

    International Nuclear Information System (INIS)

    Sneve, Malgorzata; Gordon, Boris

    2001-01-01

    The Lepse is a ship used for the storage of spent nuclear fuel from nuclear powered ice-breakers in the Murmansk region. Much of the stored spent fuel is damaged. While the status of the vessel may be considered reasonably secure for the present, it is well understood that, at some stage, it will be necessary to remove the spent fuel from the Lepse, so that the long term safe management of the spent fuel can be assured. Plans have been developed for unloading spent fuel from the Lepse. The operations to do this will be non-standard, because of the nature of the storage facilities within the vessel and the poor state of the majority of the spent fuel. For example, specialised equipment will be required for fuel handling, and special arrangements will have to be in place to avoid or mitigate the consequences of possible accidents. Regulatory supervision of these unique operations has also to be specifically provided. Concerning nuclear safety aspects, the Federal Nuclear and Radiation Safety Authority of Russia (Gosatomnadzor) has developed specific regulatory documents, with support from the Scientific and Engineering Centre of Gosatornnadzor and additional support from western agencies. Other regulatory bodies are also involved, concerned with the protection of the environment and other matters

  3. Safety assurance in radioactive waste management at nuclear power plants of the Northwest region of Russia

    Energy Technology Data Exchange (ETDEWEB)

    Safonov, Igor

    1999-07-01

    This presentation describes the two large operating nuclear power plants (NPP) in Northwest Russia, the Kola NPP and the Leningrad NPP. The four units at Kola are tank-type pressurised water reactors of 440 MW (electric) while the four Leningrad reactors are 1000 MW (electric) of RBMK type. Gosatomnadzor of Russia regularly conducts so-called target inspections on safety assurance for radioactive waste management at NNP. Among the many items checked during such inspections are the existence and realisation of an action plan for waste reduction, the technical state of equipment and the compliance with previous directions. The management of liquid, solid and gaseous radioactive wastes is described in some detail, and so are the violations revealed at both sites. There is also some discussion of modernisation plans for waste management. It is stated that the ecological impact of the plants is negligible and there is no hazard to people or environment. The presentation concludes with some suggestions for improving the licensing requirements for waste management.

  4. Safety assurance in radioactive waste management at nuclear power plants of the Northwest region of Russia

    International Nuclear Information System (INIS)

    Safonov, Igor

    1999-01-01

    This presentation describes the two large operating nuclear power plants (NPP) in Northwest Russia, the Kola NPP and the Leningrad NPP. The four units at Kola are tank-type pressurised water reactors of 440 MW (electric) while the four Leningrad reactors are 1000 MW (electric) of RBMK type. Gosatomnadzor of Russia regularly conducts so-called target inspections on safety assurance for radioactive waste management at NNP. Among the many items checked during such inspections are the existence and realisation of an action plan for waste reduction, the technical state of equipment and the compliance with previous directions. The management of liquid, solid and gaseous radioactive wastes is described in some detail, and so are the violations revealed at both sites. There is also some discussion of modernisation plans for waste management. It is stated that the ecological impact of the plants is negligible and there is no hazard to people or environment. The presentation concludes with some suggestions for improving the licensing requirements for waste management

  5. Improving MC and A Oversight in Russia by Implementing Measurement and Training Programs

    International Nuclear Information System (INIS)

    Bokov, Dmitry; Byers, Kenneth R.

    2004-01-01

    As the Russian State regulatory agency responsible for oversight of nuclear material control and accounting (MC and A), Gosatomnadzor of Russia (GAN) determines the status of the MC and A programs at Russian facilities. Last year, GAN developed and implemented their Nuclear Material Measurement Program Plan which documents current non-destructive assay (NDA) measurement capability in all regions of GAN; provides justification for upgrades to equipment, procedures and training; and defines the inspector-facility operator interface as it relates to NDA measurement equipment use. This Program Plan has helped to give the GAN inspection measurements more legal and official status as an oversight tool, and has also helped to improve other GAN MC and A oversight activities. These improvements include developing a tamper-indicating device program, conducting NDA workshops at specific Russian nuclear facilities to better train MC and A inspectors, and developing training evaluation programs. The Program is an important tool to address the GAN role in oversight of the Russian Federal Information System nuclear material database. This paper describes the feedback received from the GAN regional offices on the implementation of the Program Plan during its first year in operation and how the Program Plan has affected other GAN inspection activities to improve MC and A oversight.

  6. Consideration of severe accidents in design of advanced WWER reactors

    International Nuclear Information System (INIS)

    Fedorov, V.G.; Rogov, M.F.; Podshibyakin, A.K.; Fil, N.S.; Volkov, B.E.; Semishkin, V.P.

    1998-01-01

    Severe accident related requirements formulated in General Regulations for Nuclear Power Plant Safety (OPB-88), in Nuclear Safety Regulations for Nuclear Power Stations' Reactor Plants (PBYa RU AS-89) and in other NPP nuclear and radiation guides of the Russian Gosatomnadzor are analyzed. In accordance with these guides analyses of beyond design basis accidents should be performed in the reactor plant design. Categorization of beyond design basis accidents leading to severe accidents should be made on occurrence probability and severity of consequences. Engineered features and measures intended for severe accident management should be provided in reactor plant design. Requirements for severe accident analyses and for development of measures for severe accident management are determined. Design philosophy and proposed engineered measures for mitigation of severe accidents and decrease of radiation releases are demonstrated using examples of large, WWER-1000 (V-392), and medium size WWER-640 (V-407) reactor plant designs. Mitigation of severe accidents and decrease of radiation releases are supposed to be conducted on basis of consistent realization of the defense in depth concept relating to application of a system of barriers on the path of spreading of ionizing radiation and radioactive materials to the environment and a set of engineered measures protecting these barriers and retaining their effectiveness. Status of fulfilled by OKB Gidropress and other Russian organizations experimental and analytical investigations of severe accident phenomena supporting design decisions and severe accident management procedures is described. Status of the works on retention of core melt inside the WWER-640 reactor vessel is also characterized

  7. Russian normative approach to the question of management of NPP life time

    International Nuclear Information System (INIS)

    Karpunin, N.I.

    2002-01-01

    Full text: In Russia, the designated service life of a nuclear power plant (NPP) is 30 years. During the period 2001-2010, 15 Russian NPP units will reach the end of their service life. The 'Basic Provisions of NPP Safety Assurance', OPB-88/97, Item 5.1.14, provide for a possible extension of NPP operation beyond the designated service life. For such an extension, the NPP operating organization must apply for a license renewal to Gosatomnadzor, which needs to specify the relevant requirements. GAN is developing regulatory documents to provide a basis for NPP license renewal/extension of NPP operation, which would benefit from international experience. In accordance with 'The program of Atomic Energy Development in the Russian Federation for 1998-2005 and up to 2010' adopted by Decree No. 815 of the Government of the Russian Federation on 21 July 1998, priority is placed on the preparation of NPPs for extension of service life and on ensuring safety in the extended operating period. The length of the extension beyond the designated service life is to be determined on the basis of a range of technical and economic considerations, including: The ability to ensure and maintain operational safety; Sufficient residual service life of the unit's non-repairable components; The availability of temporary storage facilities for the additional spent nuclear fuel and radioactive waste, or the possibility of its transport off-site; The ability to ensure safe handling of the radioactive waste generated during the extension period; To extend the lifetime of an NPP unit, the plant Operator is required to perform the following tasks: Carry out a comprehensive survey of the NPP unit; Draw up a programme of preparation for lifetime extension; Prepare the NPP unit for operation in the extended period; Carry out the necessary tests. There are also some normative documents, which regulate management of NPP life time. (author)

  8. Development of System Regulating and Support for Nuclear Security in Belarus

    International Nuclear Information System (INIS)

    Lobach, D.; Astashka, R.; Lugovskaya, O.

    2015-01-01

    A safeguards strengthening in Belarus is realized as complex for measures of legal authorities building, advance staff education and international cooperation. The main scope of complex coordinated activities is to provide the sustainable development of national regulatory system and support for current and future challenges in a more globalized world to assure relevant safeguards measures and implements, to get the sustainable international and regional cooperation. Collected and implemented information and knowledge, analytical thinking of involved specialists will improve cooperation between IAEA and States to optimize technical support and experience exchange. Some authorities are responsible in regulating and oversighting for nuclear security in Belarus. The main challenge of national system development is realization the conception of effective coordination. The nuclear regulatory authority (the Ministry for Emergency Situations/ Gosatomnadzor) has the responsibility either to build up own technical capabilities for detailed review and assessment of processes and activities of the NPP operator or to make sure that a technical support organization equipped with sufficient knowledge and structural capabilities is involved in assessment and analysis of processes at all phases of the NPP use. There is developed the conception for creation of analytical and technical support laboratory including both stationary and mobile equipment and techniques for nuclear security prevention and control measures and arrangements. It is actually the realization of conception the Joint Center for Nuclear Security Competence in Belarus for national and cooperational purposes. The implementation of strengthening plans and put-up arrangements will lead to integrated regulatory activities in order to allow practical optimization of the resources to get benefits from exchange of experience and issues from safety analysis and oversighting as synergy effect. (author)

  9. Co-operation Between Different Authorities on Radiation and Health Protection Related to the Measures in Andreeva Bay

    International Nuclear Information System (INIS)

    Sneve, Malgorzata K.

    2003-01-01

    The Norwegian Radiation Protection Authority (NRPA) has been involved in the implementation of the Norwegian Plan of Action run by the Norwegian Government to ensure appropriate environmental protection and nuclear safety in the decommissioning of nuclear installations in the Northwest Russia. One objective is to ensure that the procedures used for the decommissioning of nuclear installations and radioactive waste management are appropriate and consistent with relevant policies and guidelines adopted by Russian regulatory bodies and international agencies. NRPA is an advisor for the Norwegian Ministry of Foreign Affairs on radiation protection and nuclear safety issues and ensures good co-operation with Russian authorities on the common goals. The Russian Federation state regulatory process imposes strict requirements on operators to demonstrate adequate safety, environmental and human health protection. Practically, however, there is little experience in Russia of how to assess coherently and combine all different issues within an overall process that leads to informed decision making. Regulatory requirements and related assessments tend to focus either on safety (prevention of accidents), protection of human health (in normal operations and in the event of accidents) or protection of the environment as distinct from human health, not on the whole problem. The Regulatory Support Project has been carried out by NRPA and different Russian regulatory bodies like Gosatomnadzor, Medbioextreme and others with support also from regulatory bodies in other countries. The major goal of the Regulatory Support Project is to support Russian regulatory bodies when developing guidelines and requirements for the planning, licensing and implementation of the industry projects. Another goal is that related industrial projects in Northwest Russia are managed in such a way as to efficiently secure an acceptable level of protection of human health and the environment, consistent with

  10. Some points in legal regulation of radioactive waste management

    International Nuclear Information System (INIS)

    Tikhankin, Anatoly; Levin, Alexander

    1999-01-01

    In Russia, the system of the legal acts regulating radioactive waste management is now in progress. Development of the federal norms and regulations on the use of atomic energy is a responsibility of Gosatomnazdor. This presentation describes in detail the work done by Gosatomnadzor in 1997/1998 on the development of the legal documents regulating the management of radioactive waste and spent nuclear material. A document of special importance is ''Burial of Radioactive Wastes. Principles, Criteria and Basic Safety Requirements''. This is discussed in some detail. For all stages of radioactive waste management, safety criteria for population and personnel are set up in strict analogy with current legislation for any other type of radiological hazard. A combined, or hybrid, safety criterion is suggested for estimation of long-term safety of radioactive waste repository systems, for the period upon termination of the established administrative monitoring after closing the repository. A dose criterion is accepted for normal radiation exposure and a risk criterion for potential radiation exposure. The safety of radioactive waste repository should be ensured by means of graded safeguard throughout the entire period of burial. Graded safeguard is based on independent barriers on the way of ionising radiation and emission of radioactive substances into the environment and protection and maintenance of these barriers. Examples show how the provisions of the document are applied in practice in the permafrost area of Russia. Permafrost soil has low water permeability, which is significant because underground water is the main transport medium in case of a leakage from a repository

  11. Radkowsky Thorium Fuel Project

    International Nuclear Information System (INIS)

    Todosow, Michael

    2006-01-01

    In the early/mid 1990's Prof. Alvin Radkowsky, former chief scientist of the U.S. Naval Reactors program, proposed an alternate fuel concept employing thorium-based fuel for use in existing/next generation pressurized water reactors (PWRs). The concept was based on the use of a 'seed-blanket-unit' (SBU) that was a one-for-one replacement for a standard PWR assembly with a uranium-based central 'driver' zone, surrounded by a 'blanket' zone containing uranium and thorium. Therefore, the SBU could be retrofit without significant modifications into existing/next generation PWRs. The objective was to improve the proliferation and waste characteristics of the current once-through fuel cycle. The objective of a series of projects funded by the Initiatives for Proliferation Prevention program of the U.S. Department of Energy (DOE-IPP) - BNL-T2-0074,a,b-RU 'Radkowsky Thorium Fuel (RTF) Concept' - was to explore the characteristics and potential of this concept. The work was performed under several BNL CRADAs (BNL-C-96-02 and BNL-C-98-15) with the Radkowsky Thorium Power Corp./Thorium Power Inc. and utilized the technical and experimental capabilities in the Former Soviet Union (FSU) to explore the potential of this concept for implementation in Russian pressurized water reactors (VVERs), and where possible, also generate data that could be used for design and licensing of the concept for Western PWRs. The Project in Russia was managed by the Russian Research Center-?'Kurchatov Institute' (RRC-KI), and included several institutes (e.g., PJSC 'Electrostal', NPO 'LUCH' (Podolsk), RIINM (Bochvar Institute), GAN RF (Gosatomnadzor), Kalininskaja NPP (VVER-1000)), and consisted of the following phases: Phase-1 ($550K/$275K to Russia): The objective was to perform an initial review of all aspects of the concept (design, performance, safety, implementation issues, cost, etc.) to confirm feasibility/viability and identify any 'show-stoppers'; Phase-2 ($600K/$300K to Russia

  12. Experience in arranging shipments of spent fuel assemblies of commercial and research reactors

    International Nuclear Information System (INIS)

    Komarov, S.; Barinkov, O.; Eshcherkin, A.; Lozhnikov, V.; Smirnov, A.

    2008-01-01

    At present the key activities of Sosny Company are to inspect physical conditions, handle and arrange shipment of SFA including failed SFA. In 2003 after obtaining the license of Gosatomnadzor (Rostechnadzor now) entitled to handle nuclear materials in the process of their shipment, Sosny Company started preparing certification and arranging SFA shipment on its own. About 40 shipments of SFA were performed with participation of Sosny Company. Experience in handling failed SFA - an example of development of a new technology could be the transport and technological scheme of RBMK-1000 SFA shipment from Leningradskaya NPP that was designed by Sosny Company. TUK-11 cask was selected for this shipment. The example of change of transport and technological scheme is modification of the technology for handling and shipment of WWER-440 SFA from Kola NPP. Experience in arranging transportation - based on the results of development of logistics schemes for shipping SFA of reactor facilities Sosny Company justified and implemented composition of mixed trains containing rail cars of many types that enabled to perform shipment more efficiently in time and cost. Experience in arranging handling and shipment of research reactor SFA - over the past years the activity of Sosny Company was aimed at implementing international Russian Research Reactor Fuel Return (RRRFR) program. Since equipment of the majority of research centers doesn't allow for the large casks to be accepted and loaded, special casks of less mass and dimensions are used to ship SFA from research reactors. In RRRFR program it is assumed to use different casks for RR SFA such as Russian TUK- 19, TUK-128 and foreign SKODA VPVR/M and NAC-LWT. At present Sosny Company is involved in coordination of the efforts of the affected organizations in creating the type 'C' package for RR SFA in the RF. Conclusion: Under conditions of constant increase of the requirements to shipment safety and complication of regulations of all

  13. Upgrading nuclear material protection, control and accounting in Russia

    International Nuclear Information System (INIS)

    Caravelli, Jack; Behan, Chris; Fishbone, Les

    2001-01-01

    Full text: I. Program goal and organization - In this paper we review the Cooperative US-Russia Program of Nuclear Material Protection, Control and Accounting (MPC and A), whose goal is to reduce the risk of nuclear weapons proliferation by strengthening systems of MPC and A; thereby the Program enhances US national security. Based on this goal, the technical objective is to enhance, through US technical cooperation, the effectiveness of MPC and A systems at Russian sites with weapons-usable nuclear material, i.e. plutonium and highly enriched uranium. The Program exists because the extensive social, political and economic changes in Russia arising from the dissolution of the Soviet Union have increased the risk that these materials would be subject to theft or other misuse, with potentially grave consequences. On the US side, the MPC and A Program is administered by the US Department of Energy (DOE) National Nuclear Security Administration through the DOE national laboratories and other contractors. On the Russian side, the Program is administered by the Russian Ministry of Atomic Energy (Minatom) through its nuclear sites, by the regulatory agency Gosatomnadzor, and by nuclear sites not under Minatom. To carry out the Program objective, the DOE national laboratories consummate contracts with the Russian sites to implement agreed MPC and A upgrades. Deciding on what upgrades to perform depends on a cooperative analysis of site characteristics, materials, and vulnerabilities by joint US and Russian teams. Once the upgrades are agreed, the DOE laboratories supply technical and financial support and equipment to the Russian sites. The staff of the Russian sites do the work, and the US team members monitor the work through some combination - according to contract - of direct observation and reports, photographs and videotape supplied by the staff of the Russian sites. II. MPC and A task areas - Information in this review covers a selection of topical areas, with a

  14. International cooperation in accident analysis of RBMK reactors

    International Nuclear Information System (INIS)

    Kaliatka, A.; Isag

    2005-01-01

    safety programme reflected International Atomic Energy Agency safety recommendations. The Specific Objective of this project is to provide the Russian Authorities with a detailed code system able to reliably evaluate the core behavior (and all the associated safety outcomes) during severe transients and accidents, including extensive fuel melting, individual fuel channel rupture and then multiple channel ruptures. This code system should enable experts to evaluate the safety of core designs, and to give advice how to lessen-and mitigate- the consequences of core severe transients and accidents. The use of this code system shall lead to a safety improvement, which should be reflected in Russian and international safety review reports. The beneficiary in this project is the Russian Authorities 'ROSENERGOATOM' and 'GOSATOMNADZOR', the contractor - University of Pisa. The sub-contractor - Russian research institute, designer of RBMK - MINATOM/NIKIET. The key experts for this project are involved from different countries and institutions: LEI and Ignalina NPP (Lithuania), IAEA, PSU (USA), FZK (Germany), ITER (Italy) and other. The scope of the second project (PHARE projects) is to enhance the experience and capabilities and to establish a powerful infrastructure to Lithuanian State Nuclear Power Safety Inspectorate (VATESI) for following purposes: 1) Development of requirements for the Equipment Qualification Programme at Ignalina NPP, 2) Development of a regulatory guide on implementation of requirement for Ignalina NPP accident analysis, 3) Development of governing procedures for the operation of VATESI Emergency Centre accident analysis group, 4) Development of requirements on beyond design basis accident assessment and management of RBMK-1500 reactors, The beneficiary in this project was the Lithuanian State Nuclear Power Safety Inspectorate (VATESI) and its technical support organizations. The contractor was RISKAUDIT; which formed an EU project team with GRS, IRSN, SIP