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Topical Issues in Nuclear Safety XA0102762 ~O?J| INTERNATIONAL ATOMIC ENERGY AGENCY Topical Issues in Nuclear Safety Vienna, Austria 3-6 September 2001 IAEA-CN-82 PLEASE BE AWARE THAT ALL OF THE MISSING PAGES IN THIS DOCUMENT WERE ORIGINALLY BLANK NOTE The International Atomic Energy Agency is organizing an International Conference on Topical Issues in Nuclear Safety, to be held in Vienna, Austria, from 3 to 6 September 2001. This book contains concise contributed papers submitted on issues falling within the thematic scope of the Conference which were accepted by the Conference Programme Committee for consideration at the Conference. The material compiled in this book has not been edited by the editorial staff of the IAEA. However, certain modifications were made: a unified format was adopted for all papers and corrections were made in the text where required. It is intended that, after the Conference, the contents of this book will be published in the form of a CD ROM as part of the proceedings of the Conference. Authors wishing to make slight modifications or corrections to their paper are encouraged to contact the Conference Secretariat. The views expressed in the papers are the responsibility of the named authors. These views are not necessarily those of the Governments of Member States. Neither the IAEA nor Member States assume any responsibility for consequences which may arise from the use of information contained in this book. CONTENTS Topical Issue 1: Risk-informed decision making Regulatory approach to risk informed decision making in India (IAEA-CN-82/17) S.K. Chande, J. Koley 3 Risk concepts in UK nuclear safety decision-making (IAEA-CN-82/18) P.W.M. Brighton 8 Risk informed decision making for the allowed outage times changes (IAEA-CN-82/25) Z. Kovdcs, P. Cigdnik, P. Hlavdc. 15 The use of the decision theory and probabilistic analysis in the NPP licensing decision process (IAEA-CN-82/28) D. Serbanescu 19 Experiences and future plan for risk-informed decision making in Korea (IAEA-CN-82/29) D.W. Chung, Y.H.Ryu 26 Risk informed decisions and regulations — STUK's policy and current practice (IAEA-CN-82/33) A. Julin, I. Niemeld, R. Virolainen 32 Using probabilistic safety assessment for making decisions on improving the safety of in-service and newly developed nuclear power stations with WWER reactors (IAEA-CN-82/46) Y.V. Shvyryaev 39 Impediments for the application of risk-informed decision making in nuclear safety (IAEA-CN-82/49) L. Hahn 44 A framework of risk-informed seismic safety evaluation of nuclear power plants in Japan (IAEA-CN-82/58) S. Kondo, M. Sakagami, M. Hirano, M. Shiba 48 The use of PSA in the Dukovany NPP as a support tool for risk-informed decision making (IAEA-CN-82/60) A. Veleba 52 Risk-informed decision making during Bohunice NPP safety upgrading (IAEA-CN-82/63) M. Lipdr, E. Muzikovd, J. Kubdnyi 58 Structuring a risk-informed and performance-based process for optimization of regulation for Laguna Verde NPP (IAEA-CN-82/65) A. Rodriguez-Hernandez 65 Topical Issues 2: Influence of external factors on safety The Brazilian experience in licensing Angra 2, a 'delayed' nuclear power plant (IAEA-CN-82/03) C. Almeida 75 Nuclear and radiation safety in Kazakhstan (IAEA-CN-82/08) A.A. Kim 80 Nuclear installations in Belarus: Implications of political and technical issues (IAEA-CN-82/10) S.I.Zaitsev 86 Deliberations on nuclear safety regulatory system in a changing industrial environment (IAEA-CN-82/32) H.J.Kim 89 Regulatory concern about economic deregulation in Finland (IAEA-CN-82/34) R. Virolainen, P. Koutaniemi 95 A way of Dukovany NPP to privatization and liberalized market (IAEA-CN-82/36) I.Kouklik 98 The nuclear safety regulation in Japan and the response to changes of circumstances surrounding the nuclear electricity generation (IAEA-CN-82/37) K. Hombu, M. Hirota, T. Taniguchi, N. Tanaka, S. Akimoto 103 Assessment of the effectiveness of the Hungarian nuclear safety regulatory authority by international expert teams (IAEA-CN-82/41) L. Voross, F. Lordnd 107 The UK nuclear regulator's view of external influences on safety (IAEA-CN-82/55) J.L. Summers 113 Requalification of the steam supply systems of Units 3 and 4 of the Kozloduy NPP to a new model WWER-440/B-209M (IAEA-CN-82/57) /. Iordanov, S. Sabinov, V. Ourutchev, M. Stoev 119 Topical Issue 3: Safety of fuel cycle facilities Success in behaviour-based safety at Los Alamos National Laboratory's plutonium facility (IAEA-CN-82/12) R.E. Wieneke, J.J. Balkey, J.F. Kleinsteuber 125 Criticality accident studies and research performed in the Valduc criticality laboratory, France (IAEA-CN-82/26) F. Barbry, P. Fouillaud 134 Recent development in safety regulation of nuclear fuel cycle activities (IAEA-CN-82/38) S.Kato 141 Prospects for safe management of spent nuclear fuel of research reactors (IAEA-CN-82/42) N.S. Yanovskaya, T.F. Makarchuk, V.N. Ershov, N.B. Zaitsev 147 Criticality Studies: One of the two pillars of criticality safety at the Belgonucleaire MOX plant (IAEA-CN-82/44) B. Lance, T. Maldague, G. Renard, P. Kockerols 153 Regulation of fuel cycle facilities in the UK (IAEA-CN-82/54) W.W. Ascroft-Hutton 159 Topical Issue 4: Safety of research reactors Safety of Ghana research reactor (GHARR-1) (IAEA-CN-82/05) J.H. Amuasi, C. Schandorf, J. Yeboah 167 Safety of assessment of various operation modes (IAEA-CN-82/06) M. Pesic, I. Plecas, R. Pavlovic 171 Experience in the implementation of quality assurance programme and safety culture assessment of research reactor operation & maintenance (IAEA-CN-82/14) Syarip, K. Suryopratomo 177 Safety enhancement in CIRUS through ageing management and refurbishing (IAEA-CN-82/16) S.K.Sharma 184 Safety status of Russian research reactors (IAEA-CN-82/19) S.I.Morozov 190 Safety challenges encountered during the operating life of the almost 40 year old research reactor BR2 (IAEA-CN-82/27) E. Koonen, F. Joppen, P. Gubel 196 Strengthening operational safety of the 3MW TRIGA MK-II research reactor of Bangladesh Atomic Energy Commission through modification and upgrade of its water system (IAEA-CN-82/35) MM. Haque, M.A. Zulquarnain, MA. Salam 200 French safety authority projects in the field of research and test reactors (IAEA-CN-82/43) P. Saint Raymond, M. Duthe, H. Abou Yehia 207 Safety operation of training reactor VR-1 (IAEA-CN-82/45) K.Matejka 212 Experiences in controlling the upgrading of TRIGA 200 Bandung reactor (IAEA-CN-82/56) K. Huda, Y.W. Wibowo, M.S. Suprawhardana 219 Ageing of research reactors (IAEA-CN-82/61) M. Ciocanescu 225 Emergency planning and preparedness of the Dalat Nuclear Research Institute (IAEA-CN-82/66) B.V.Luong 230 Safety of research reactors - A regulator's perspective (IAEA-CN-82/67) M.S.Rahman 237 Topical Issue 5: Safety of performance indicators Performance indicators at Embalse NPP: PSA & safety system indicators based on PSA models (IAEA-CN-82/09) D.A. Fornero 245 Development and use of safety indicators at STUK (IAEA-CN-82/20) P. Tiippana 253 Improvement programme of safety performance indicators (SPIs) in Korea S.Y.Lee. 260 Estimations of actual availability (IAEA-CN-82/23) M.Molan, G.Molan 266 Development of safety performance indicators in Japan (IAEA-CN-82/39) H. Ohashi, S. Tamao, J. Tanaka, T. Sawayama 272 Operational safety performance indicator system at the Dukovany Nuclear Power Plant - Experience with indicator aggregation (IAEA-CN-82/59) J.Mandula 279 Safety assessment, safety performance indicators at the PAKS Nuclear Power Plant (IAEA-CN-82/62) C. Baji, G. Vdmos, J. Toth 284 The establishment and implementation of safety culture policy in Indonesia (IAEA-CN-82/64) A.R. Antariksawan, Suharano, B. Arbie 291 TOPICAL ISSUE 1: RISK-INFORMED DECISION MAKING XA0102763 IAEA-CN-82/17 REGULATORY APPROACH TO RISK INFORMED DECISION MAKING IN INDIA CHANDE, S. K., KOLEY, J. Atomic Energy Regulatory Board Niyamak Bhavan Anushakti Nagar Mumbai 400 094, India Fax: 0091-22-5552879 Email: [email protected] Abstract Atomic Energy Regulatory Board (AERB), the authority for licensing and monitoring safety in Indian Nuclear Power Plants (NPPs), makes use of insights gained from PSA together with the results of the other deterministic analyses in taking decisions regarding the acceptability of the safety of the NPPs. PSA provides an estimation of risks; it also gives information on a balanced design by revealing interaction between engineered features and weak areas in a design. For regulatory use, PSA needs to be carried out using standardized methodology and state of the art technology. PSA helps regulators in taking faster and consistent decisions. Keeping in mind the limitations associated with PSA study, AERB has decided to adopt risk-informed decision making in regulatory licensing process. This paper describes the AERB policy regarding PSA and gives overview of the experience in this area. 1. INTRODUCTION 1.1. Licensing process The licensing process of Indian Nuclear Power Plants is based on deterministic regulatory requirements where the intent is to ensure safety with multiple layers of defense in-depth. Design basis accidents are defined and engineered safety features are incorporated into the design to respond to these accidents;. The safety analysis must then prove the adequacy of safety systems to meet their objective and ensure safety of plant, personnel and environment. 1.2. Deterministic analysis The classical and deterministic safety analysis submitted by the utilities to support license applications cover various areas like reactor physics, fuel design and thermal hydraulics to assess the adequacy of engineered safety systems including reactor shutdown system, containment systems, etc.
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