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Computerized Reactor Protection and Safe^Ty Related Systems in Nuclear Power Plants XA9846490 IAEA-IWG-NPPCI-98/1 LIMITED DISTRIBUTION WORKING MATERIAL COMPUTERIZED REACTOR PROTECTION AND SAFE^TY RELATED SYSTEMS IN NUCLEAR POWER PLANTS Proceedings of a Specialists' Meeting Organized by the International Atomic Energy Agency in Co-operation with Paks Nuclear Power Plant 27-29 October 1997 Budapest, Hungary Reproduced by the IAEA Vienna, Austria, 1998 NOTE The material in this document has been supplied by the authors and has not need edited by the IAEA. The views expressed remain the responsibility of the named authors and do not necessarily reflect those of the government(s) or the designating Member State(s). In particular, neither the IAEA nor any other organization or body sponsoring this meeting can be held responsible for any material reproduced in this document. toft BLANK - 3 - FOREWORD Though the majority of existing control and protection systems in nuclear power plants use old analogue technology and design philosophy, the use of computers in safety and safety related systems is becoming a current practice. The Specialists Meeting on "Computerized Reactor Protection and Safety Related Systems in Nuclear Power Plants" was organized by IAEA (jointly by the Division of Nuclear Power and the Fuel Cycle and the Division of Nuclear Installation Safety), in co-operation with Paks Nuclear Power Plant in Hungary and was held from 27-29 October 1997 in Budapest, Hungary. The meeting focused on computerized safety systems under refurbishment, software reliability issues, licensing experiences and experiences in implemented computerized safety and safety related systems. Within a meeting programme a technical visit to Paks NPP was organized. The objective of the meeting was to provide an international form for the presentation and discussion on R&D, in-plant experiences in I&C important to safety, backfits and arguments for and reservations against the digital safety systems. The meeting was attended by 70 participants from 16 countries representing NPPs and utility organizations, design/engineering, research and development, and regulatory organizations. In the course of 4 sessions 25 technical presentations were made. The present volume contains the papers presented by national delegates and the conclusions drawn from the finial general discussion. NEXT PAGEfS) toft BLANK - 5 - IAEA Specialists' Meeting on Computerized Reactor Protection and Safety Related Systems in Nuclear Power Plants Budapest, Hungary 1997 October 27 - 29 PROGRAMME Monday, October 27 8:30 - 9:00 Registration, Ramada Grand Hotel 9:00 - 9:25 Opening Session Welcoming Remarks - G. Vamos, Safety Director of Paks NPP Welcoming Remarks - V. Neboyan, IAEA Overview of IAEA Specialists Meeting - A. Hetzmann, Paks NPP 9:25 - 10:25 Session 1: Computerized Safety Systems under Refurbishment Chairperson: Paul van Gemst, Sweden 1.1 The Modernization of the Safety I&C Systems at the Paks NPP. A. Hetzmann, Hungary 1.2 Experience and Perspective in Backfittings of Safety I&C Systems in Belgian Nuclear Power Plants. J.C. Naisse. Belgium. 10:25 - 10:50 Coffee Break and Registration 10:50 - 12:50 Session 1: (Continuation) 1.3 An Application study for the Class IE Digital Control and Monitoring System. H.Fukumitsu. Japan. 1.4 Computerized Reactor Surveillance and Control System: an FBR Example. J-P. Trapp, A. Lebrun. France. 1.5 GUARDS: an approach safety-related systems using COTS. Example of MMI and reactor automation in nuclear submarine application. M Brun, France. 1.6 Refurbishment of the Reactor Protection System at Paks NPP. The Refurbishment Process. T. Turi, B. Katies. Hungary. 12:50-13:50 Lunch Break - 6 - 13:50 - 15:20 Session 2: Software Reliability Issues Chairperson: Jeno Hetthessy,Hungary 2.1 Government of Common Cause Failures. H-W.Bock. Germany. 2.2 Reliability Analysis of Protection Systems in NPPs Using Fault-Tree Analysis Method. J.Bokor, G.Szabo, P.Gdspdr, J.Hetthessy. Hungary. 2.3 Adoption of digital safety protection system in Japan. Z. Ogiso. Japan. 15:20-15:50 Coffee Break 15:50 -17:10 Session 2: (Continuation) 2.4 Methodology of Formal Software Evaluation J. Tuszynski. Sweden 2.5 A Safety Related Control System for NPPs. G.H.Schildt. Austria. 2.6 Methodology and Tools for Independent Verification and Validation of computerized I&C Systems Important to Safety. A. Lindner, H. Miedl. Germany. 19:00 Dinner Tuesday, October 28 9:00 - 11:00 Session 3: Licensing Experiences Chairperson: Petr Krs, Czech Republic 3.1 A Regulatory Frame for Safety Digital Systems in Nuclear Power Plants. A. Mozas Garcia. Spain. 3.2 Regulatory Aspects of Digital Systems. Hungarian Approach to Licensing. A.H. Hamar. Hungary 3.3 Licensing Process of the Digital Application: Nuclear Measurement Analysis and Control-Power Range Neutron Monitor (NUMAC-PRNM) System for their Implementation in the Laguna Verde NPP Unit 2. R.Ledesma-Carrion. A. Hernandez-Cortes, Mexico. 3.4 NRC Perspectives on the Digital System Review Process. J.LMauck. USA 11:00-11:20 Coffee Break - 7 - 11:20 -12:50 Session 4: Experiences in Implemented Computerized Safety and Safety Related Systems. Chairperson: Jean-Claude Naisse, Belgium 4.1 Replacement of the Control & Instrumentation System with the Microprocessor Based System in Japanese PWR Plants. N. Hayashi. Japan. 4.2 Application of Computer-Based Safety Systems in Korea Nuclear Power Plants. Won-Young Yun. Republic of Korea. 4.3 Shutdown systems computer-monitoring for CernavodaNPP. M.C. Popescu, Romania. 12:50-13:50 Lunch break 13:50-15:15 Session 4: (Continuation) 4.4 The Use of PC Based Data Acquisition Systems, Connected to the Reactor Shutdown System #1 and #2. M.Stanciu, R.Dudu. Romania 4.5 Modernization of Safety Systems in Ringhals 1 NPP in Sweden. E. Strobeck, P. V. Gemst. Sweden. 4.6 Replacement of the Complete Control System of the NPP Oskarshamn 1 by Digital Distributed Control System. E. Berger. Germany. 15:15 - 15:35 Coffee Break 15:35 - 17:00 Session 4: (Continuation) 4.7 The Computer Aided Operation of the N4 Series. G.Guesnier, J.P.Bouard. France. 4.8 ABWR (K-6/7) Construction Experiences. Computer-Based Safety System. T. Yokomura. Japan. 4.9 NPP Control Command: Considerations for the Future. J-P. Trapp. France. 17:00 - 18:00 Session 5: General Discussion, conclusions and Recommendations Chairperson: James White, USA Wednesday, October 29 (Optional) Technical visit to Paks Nuclear Power Plant 8:30 - 10:30 Travel to Paks NPP 10:30 - 11:00 Visitor Centre Paks (coffee) 11:00-12:30 Visit to the Plant 12:30-13:30 Lunch 13:30-15:30 Travel to the hotel or to airport I NEXT PAQE(S) I left BLANK - 9 - TABLE OF CONTENTS Session 1: Page No. Computerized Safety Systems under Refurbishment 13 Chairperson: Paul van Gemst, Sweden The Modernization of the Safety I&C Systems at the Paks NPP 15 A.Hetzmann, Hungary Experience and Perspective in Backfittings of Safety I&C Systems 27 in Belgian Nuclear Power Plants. J.C. Naisse. Belgium. 1.3. An Application study for the Class IE Digital Control and Monitoring System 39 H.Fukumitsu. Japan. 1.4. Computerized Reactor Surveillance and Control System: an FBR Example 55 J-P. Trapp. A. Lebrun. France. GUARDS: an approach safety-related systems using COTS. Example of MMI and reactor automation in nuclear submarine application 65 M. Brun, France. 1.6. Refurbishment of the Reactor Protection System at Paks NPP 71 The Refurbishment Process. T. Turi. B. Katies. Hungary. Session 2: 81 Software Reliability Issues Chairperson: Jeno Hetthessy,Hungary Government of Common Cause Failures 83 H-W.Bock. Germany. Reliability Analysis of Protection Systems in NPPs 91 Using Fault-Tree Analysis Method. J.Bokor, G.Szabo, P. Gdspdr. J.Hetthessy. Hungary. Adoption of digital safety protection system in Japan 105 Z. Ogiso. Japan. Methodology of Formal Software Evaluation Ill J.Tuszynski. Sweden A Safety Related Control System for NPPs 119 G.H.Schildt. Austria. Methodology and Tools for Independent Verification and 127 Validation of computerized I&C Systems Important to Safety. A. Lindner. H. Miedl. Germany. - 10 - Session 3: 139 Licensing Experiences Chairperson: Petr Krs, Czech Republic A Regulatory Frame for Safety Digital Systems in Nuclear Power Plants 141 A. Mozas Garcia. Spain. Regulatory Aspects of Digital Systems. Hungarian Approach to Licensing 153 A.H. Hamar. Hungary Licensing Process of the Digital Application: Nuclear Measurement 163 Analysis and Control-Power Range Neutron Monitor (NUMAC-PRNM) System for their Implementation in the Laguna Verde NPP Unit 2. R.Ledesma-Carrion. A. Hernandez-Cortes, Mexico. NRC Perspectives on the Digital System Review Process 173 J.LMauck. USA Session 4: 183 Experiences in Implemented Computerized Safety and Safety Related Systems. Chairperson: Jean-Claude Naisse, Belgium Replacement of the Control & Instrumentation System with the 185 Microprocessor Based System in Japanese PWR Plants. N. Hayashi. Japan. Application of Computer-Based Safety Systems in Korea 199 Nuclear Power Plants. Won-Young Yun. Republic of Korea. Shutdown systems computer-monitoring for Cernavoda NPP 207 M.C. Popescu, Romania. The Use of PC Based Data Acquisition Systems, Connected to 211 the Reactor Shutdown System #1 and #2. M.Stanciu, R.Dudu. Romania Modernization of Safety Systems in Ringhals 1 NPP in Sweden 225 E. Strobeck, P. V. Gemst. Sweden. Replacement of the Complete Control System of the NPP 237 Oskarshamn 1 by Digital Distributed Control System. E. Berger. Germany. The Computer Aided Operation of the N4 Series 245 G. Guesnier. J. P. Bouard. France. ABWR (K-6/7) Construction Experiences. Computer-Based Safety System 253 T. Yokomura. Japan. - 11 - NPP Control Command: Considerations for the Future 267 J-P. Trapp. France. Session 5: 275 General Discussion, conclusions and Recommendations Chairperson: James White, USA Summary of the discussion. 277 J. White. USA List of participants 281 NEXT PAOEIS) Uf tBLANK - 13 - Session 1: Computerized Safety Systems under Refurbishment NEXT PAQE(S) left BLANK - 15 - XA9846491 THE MODERNISATION OF THE SAFETY l&C SYSTEMS AT THE PAKS NPP A.
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