Abstract
The Soviet-Designed Reactor Safety Program of the U.S. Department of Energy is a cooperative effort with nine countries to reduce risks at Soviet-designed nuclear power plants. Projects are organized into the areas of management and operational safety, engineering and technology, plant safety assessment, fuel-cycle safety, nuclear safety regulatory and institutional framework, and Chonobyl initiatives. Those projects being carried out in Russia are reviewed.
Operated for the U.S. Department of Energy by Battle Memorial Institute under Contract No. DE-AC06-76RLO-1830
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a) Hall, S.F., and Gabaraev, B.A. (1994) RBMK Safety Review, Final Report, RBMK/CMC/FR, Vol. 1, Issue 1, March; b) Zlatnansky, J. (1991) IAEI older-reactors group looks at the V-230, Nuclear Engineering International,March, 17–19; c) Georgiev, B., Todorov, G., and Ganchev, T. (1991) Improving safety at Bulgaria’s V-230s, Nuclear Engineering International, March, 29–30; d) (1986) RBMK Nuclear Power Plants: Generic Safety Issues, IAEA-EBP-RBMK-04, International Atomic Energy Agency; e) Reister, R., and Goldsmith, S. (1998) The U.S. Department of Energy’s Efforts to Improve Safety at Soviet Designed Nuclear Power Plants, Presented at the American Nuclear Society International Topical Meeting on Safety of Operating Reactors, October 11–14, San Francisco.
A description of the EBRD program can be found at: http://www.ebrd.com/english/opera/nucsafe/english/opera/nucsafe.
A description of the TACIS program can be found at: http://europa.eu.indcomm/dgl/tacis/action_prog/actprog_nuclear.htm.
a) (1993) Russian RBMK Reactor Design Information, Pacific Northwest Laboratory Report PNL-8937; b) Almenas, K., Kaliatka, A., and Uspuras, E. (1998) Ignalina RBMK-1500, A Source Book, Ignalina Safety Analysis Group, Lithuanian Energy Institute; c) Dollezhal’, N.A., and Yemel’yanov, I.Ya. (1981) Channel Nuclear Energy Reactor [translated from Russian], FBIS Report No. JPRS L/10150.
Overall Plant Design Descriptions, VVER, Water-Cooled, Water-Moderated Energy Reactor, U.S. Department of Energy Report NE-0084.
Improving the Safety of Soviet-Designed Nuclear Power Plants, U.S. Department of Energy, Office of Nuclear Energy, Science and Technology.
Code on the Safety of Nuclear Power Plants: Operation, Safety Series No. 50-C-O (Rev. 1), IAEA, Vienna.
a) Klein, S.M. (1988) Fundamental attributes of a practical configuration management program for nuclear plant design control, Nuclear Regulatory Commission, Washington DC; b) (1966) Configuration change process description, INPO AP-905, Institute of Nuclear Power Operations; c) (1994) Position paper on configuration management, PP02–1994, Nuclear Information and Records Management Association Inc.; d) (1992) Position paper for implementing a configuration management enhancement program for a nuclear facility, PP03–1992, Nuclear Information and Records Management Association Inc.; e) (1981) Quality assurance in the design of nuclear power plants, A safety guide, IAEA Safety Guides No. 50-SG-QA6 International Atomic Energy Agency, Vienna.
Meeting protocol: Novovoronezh Nuclear Power Plant Configuration Management Project, October 6–9, INSP Resource Center, Document No. Russia 10/97.
a) (1997) Nuclear Power Plant Personnel Training and Its Evaluation, A Guidebook, IAEA Report No. 380, Vienna, Austria; b) Blank, W.E. (1982) Guidebook to Competency Based Training, Prentice Hall, Upper Saddle River, New Jersey; c) (1994) Training Program Handbook: A Systematic Approach to Training, DOE-HDBK-1078–94, U.S. Department of Energy, Washington, D.C. (1994); d) (1995) Alternative Systematic Approaches to Training, DOE-HDBK-1074–95, U.S. Department of Energy, Washington, D.C.
Haber, S.B., Shurberg, D.A., and Yoder, J. A. (1998) Enhancement of Operational Safety Through Training at Soviet-Designed Nuclear Power Plants, ati Fr
Kohut, P., Epel, L. G., Tutu, N.K., Ginsberg, T., Shier, W.G. Jr., Davis, R.E., Cleary, E.J., Erickson, K.G., Moffitt, R.L., and Yoder, J. (1998) Operational Safety Enhancement of Soviet-Designed Nuclear Reactors via Development of Nuclear Power Plant Simulators and Transfer of Related Technology, Presented at the American Nuclear Society International Topical Meeting on Safety of Operating Reactors, October 11–14, San Francisco.
Nuclear Power Plant Simulators for Use in Operator Training, American Nuclear Society, La Grange Park, IL.
a) (1982), Emergency Operating Procedures Implementation Guideline, Rev. 1, INPO 82–016, Institute of Nuclear Power Operations; b) (1982), Emergency Operating Procedures Writing Guideline, INPO 82–017, Institute of Nuclear Power Operations; c) (1983), Emergency Operating Procedures Verification Guideline, INPO 82–004, Institute of Nuclear Power Operations; d) (1983), Emergency Operating Procedures Validation Guidelines, INPO 83–006, Institute of Nuclear Power Operations; e) (1983), Emergency Operating Procedures Package Guideline, INPO 83–007, Institute of Nuclear Power Operations.
a) McMaster, R.C. (ed.) (1963) The Non-Destructive Testing Handbook, Ronald Press Co., New York; b) Krautkramer, J., and Krautkramer, H. (eds.) (1983) Ultrasonic Testing of Materials, 3`d Ed., Springer Verlag, Berlin-Heidelberg, New York; c) Prepechal, J., and Skala, Z. (1991) Ultrasonic testing of VVER440 vessels using Reactortest, Nuclear Engineering International, March 33–34; d) Getman, A.F., and Kozin, Yu.N. (1977) Nerazrushayushchii Kontrol’ I Bezopasnost’ Ekspluatatsii Sosudov I Truboprovodov Davleniya (Nondestructive Examination and Operational Safety of Pressure Vessels and Pipes) [in Russian], Energoatomizdat, Moscow.
) Reactor Core Protection Evaluation Methodology for Fires at RBMK and VVER Nuclear Power Plants, Report DOE/NE-0113, Revision 1, U.S. Department of Energy.
Denning, R.S., Durst, B.M., and Fletcher, N. (1998) Safety Parameter Display Systems for Soviet-Designed Nuclear Power Plants, Presented at the
a) (1992) Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 1), IAEA Safety Series No. 50-P-4, International Atomic Energy Agency, Vienna; b) Basic Safety Principles for Nuclear Power Plants, IAEA Report No. 75 INSAG-3, International Atomic Energy Agency, Vienna.
Guidelines for the In-Depth Safety Assessment of Operational NPP Units with VVER and RBMK Type Reactors, Russian Federal Nuclear and Radiation Safety Inspectorate (Gosatomnadzor), Moscow.
Ivanov, V.A. (1994) Ekspluatatsiya AES (NPP Operation) [in Russian], Energoatomizdat, St. Petersburg, pp. 92–97.
Nuclear Safety: International Assistance Efforts to Make Soviet-Designed Reactors Safer, GAO/RECD-94–234, Letter Report, 29 Sept.
Decommissioning Handbook, DOE/EM-0142P, U.S. Department of Energy, Office of Environmental Restoration.
) Facilitation of Decommissioning of Light Water Reactors, NUREG/CR-0569, U.S. Nuclear Regulatory Commission, Washington DC.
Joint U.S./Russian Study on the Development of a Decommissioning Strategy Plan for RBMK-1000 Unit #1 at the Leningrad Nuclear Power Plant, Prepared for U.S. DOE, Office of Nuclear Energy, Science and Technology, PNNL, International Nuclear Safety Program, Richland, Washington.
Joint U.S./Russian Study on the Preliminary Cost Estimate of the SAFSTOR Decommissioning Alternative for the Leningrad Nuclear Power Plant Unit #1, Prepared for U.S. DOE, Office of Nuclear Energy, Science and Technology, PNNL, International Nuclear Safety Program, Richland, Washington.
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Wester, D.W. (1999). The View from Russia of the Soviet-Designed Reactor Safety Program of the U.S. Department of Energy. In: Choppin, G.R., Khankhasayev, M.K. (eds) Chemical Separation Technologies and Related Methods of Nuclear Waste Management. NATO Science Series, vol 53. Springer, Dordrecht. https://doi.org/10.1007/978-94-011-4546-6_16
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