Dr.-Ing. Rainer Kaulbarsch, Gösgen Power Plant (CH) August, 26th, 2013, Vienna
|
|
- Bethanie Nelson
- 6 years ago
- Views:
Transcription
1 Safety Examinations and Improvements after Fukushima, Status Dr.-Ing. Rainer Kaulbarsch, Gösgen Power Plant (CH) August, 26th, 2013, Vienna Folie 1
2 Overview Introduction Examinations easures Outlook and Conclusions Folie 2
3 Introduction - Side and Type Side: North Switzerland, Däniken, Kanton Aargau, Beside river Aare Water intake «0» Water intake «5» Earth Quake Areas Basel Zürich Bern Reference: nuklearforum River Aare KKG Type: SIEENS PWR 3-Loop primary circuit 3002 W th,1035 W el, Heat extraction for industrial use Folie 3
4 Introduction Defence in Depth Operating Systems Limiting Systems Safety Systems *) (Special) Bunkered Emergency Systems Internal Emergency easures External Emergency easures *) In most foreign power plants the «Safety Systems» are called «Emergency Systems». At KKG the «Emergency Systems» are an additional defence line beyond the safety systems. Folie 4
5 Introduction ain Safety Data 3 +1 safety train system (separated) Additional 2 trains of special emergency system (bunkered system) - 10 h autarky operation Designed according to the 30 minutes rule for operator interference Designed against airplane crash, external explosions Elevated location (design against external floods) Accident management manual since 1994, Filtered containment venting since end of 1993
6 Safety Concept Available Equipment (Generators, Water source) Safety Systems Diesel EY1-4 Aare, 0 Aare, 5 Internal Emergency Equipment Dieselgenerators (Security Systems) Well No. 1 Well No. 2 Redundant River Water Intake Aare, 5 Bunkered Emergency Systems Diesel FY5-7 After Fukushima Well No. 1 Well No. 2 Not available due to earthquake loads Firefighting Car (SG Water Injection) i.e. Aare, Cooling Tower obile Dieselgenerators (planned) i.e. Aare, Cooling Tower External Emergency Equipment obile Dieselgenerators i.e. Aare, Cooling Tower Folie 6
7 Safety Examinations (ENSI and EU-Stresstest) 1v2 Examination Result Earthquake (deterministic approach) Earthquake, Fragilities Flood (Deterministic Approach) Earthquake with Dam Rupture (Deterministic Approach) Control by (special) bunkered emergency systems (with & without single failure). Verification for loads < 0.46 g (based on preliminary PEGASOS SSHAG Level 4 project) Controled by (special) bunkered emergency systems (with & without single failure), No water on the plant area. Controled by (special) bunkered emergency systems (with & without single failure). Cascade rupture of all dams upward the river. => 0.2 m water level for approx. 40 min. (> 2.0 m tolerable) Station Blackout Batteries of emergency eystems > 3.5 h. Emergency diesel generators fuel > 72 h. With all fuel reserves on side > h. H 2 Hazard Deflagration with pressure peaks < 3 bar. Containment stays closed. No release over the gas scrubbing unit. Folie 7
8 Safety Examinations (ENSI and EU-Stresstest) 2v2 Examination Primary Circuit Isolation Containment Isolation Extreme weather Result Integritiy is ensured. Internal release into coolant storage unit. Automatic primary circuit isolation. Isolation not necessary due to primary circuit integrity. ain ducts are isolated due to loss of power. Remaining (smaller) ducts can be closed by hand. Swiss nuclear project for re-evaluation ongoing. (Air temperatur, river temperature, rain fall, snow, tornados, ) Ongoing project. Results 1. Dose < 1 msv (100 msv required by Authority). 2. Weak points of the safety systems identified. 3. Event control with (special) bunkered emergency systems. 4. easures to enhance margins of the bunkered emergeny systems done. 5. Further enhancement of safety & bunkered emergency systems. Objective: Reach State of odernization Technology. Folie 8
9 easures External Equipment Storage in «Reitnau» External Storage «Reitnau» obile Pump - obile emergency equipment is stored in a central storage in Switzerland. - Equipment for emergency power generation, power supply cables, pumps for feed water injection into i.e. steam generators available. - Transport to the KKG will be done by the swiss military. obile Diesel Generator => Safety margin increased. Folie 9
10 easures Flood wall - Emergency systems are flood protected up to levels > 2 m. - New wall limits water levels on the plant area to several centimeters and enhances feasibility of emergency measures. => Safety margin increased. New flood protection wall Folie 10
11 easures 2 nd Isolation Valve of ain Coolant Pump Drainage System - 1st isolation of drainage line are the main coolant pump sealings. - 2nd isolation is done by an isolation valve of the volume regulation system. - New isolation valve between pump and (old) second isolation valve ensures primary circuit isolation. => Safety margin increased. 2. Isolation valve TA50S003 Folie 11
12 easures Enhanced Anchorages of the RPS Secured RPS at ZX building Unsecured RPS at ZE building RPS at bunkered emergency systems (ZX) was necessary for event control. RPS inside the electrical building beneficial for event control. => Done to control the event earth quake. Folie 12
13 easures Dampers of the bunkered Emergency Diesels Old dampers replaced. Safety margin increased. Enhanced earthquake robustness > 0.92 g. (0.46 g required) Emergency diesel FY New emergency diesel dampers Folie 13
14 easures Enhancement of the Fire Fighting Building New light construction gate Buildung will withstand earthquaks, gate can easily be destroyed and opend by the firefighting car. The car is not needed wihtin 3 day s. => Safety margin increased. Wall enhancement inside Folie 14
15 easures 2 nd Feed Line for Wet Spent Fuel Storage The wet storage pool is passive cooled by natural convection. No active cooling is needed. Without cooling, T > 80 C will be reached after appr. 4 d. (high grace times). Pipes for external cooling Feed water connector No. 1 Feed water connector No. 2 Emergency pipes for cooling with the heat exchanger were already installed. One emergency pipe to fill in water were already installed before Fukushima. Second feed line installed after Fukushima. => Safety margin increased. Folie 15
16 easures Feed Line for «Loading» Pool The loading pool contains 3 fuel elements and a decay heat of 120 kw in maximum. 60 C will be reached after 2.6 d without cooling. Boiling with loss of coolant will occur more than 3 days after an event. Piping with a connector for exernal water feed-in is installed inside the annulus buildung. => Safety margin increased. Feed water connector Folie 16
17 easures Spent Fuel Pool 2 nd Feed Line The spent fuel pool will heat up to 100 C during several hours (approx. 6 h in minimum). After several hours of boiling, water can be fed into the pool by the existing connector TH74S005 in the annulus building. Entrance to the connector An additional connector for external water feed-in (TH74S007) was installed after the Fukushima event at a different place in the annulus building. => Safety margin increased. Feed water connector Folie 17
18 easures Emergency Control Room Instrumentation (Display Spent Fuel Pool Temperatur & Level) Before the Fukushima event, the spent fuel pool level and temperature was already displayed at the control room. At the emergency control room, level and temperature was controlled by calculations and prepared tables depending on the number of fuel elements. Now an additional pen recorder was installed to provide the current and also previous information of the spent fuel temperature and water level. => Safety margin increased. Pen recorders Folie 18
19 No measure necessary: Spent Fuel Pool Robustness For the Spent Fuel Pool finite-element Calculations show: Pool Integrity is ensured up to Temperatures of approx. 160 C. (160 C corresponds nearly to the Design Pressure of the Containment.) ain Advantage: In Case of Pool boiling with Containment Isolation the Pool Integrity is ensured. Source: AREVA => Low Dose Values. => No Enhancement is necessary. Cross Section of a Welding Folie 19
20 Placement into current Safety Concept Earthquakes with low loads are still controlled by the safety systems. Earthquakes with higher loads (like Fukushima or PEGASOS results) are controlled by the (special) bunkered emergency systems. Bunkeres Emergency Systems are in the Focus of Retrofit easures. Folie 20
21 Conclusion Fukushima like events are controlled by the special bunkered emergency systems. Several measures were necessary to increase earthquake robustness of the special bunkered emergency systems. A lot of measures were done to increase safety margins. Due to the action list of the authority, several measures may have to be done to increase margins. Investigation of KKG for significant safety increase - A-seismic bedding of the hole power plant (positive investigations ongoing). - Significant enhancement of the bunkered emergency systems (positive investigations ongoing). Coherent large Retrofit is appreciated because of higher Benefit compared to punctual Safety Increase. Folie 21
Preliminary Lessons Learned from the Fukushima Daiichi Accident for Advanced Nuclear Power Plant Technology Development
Preliminary Lessons Learned from the Fukushima Daiichi Accident for Advanced Nuclear Power Plant Technology Development A. Introduction The IAEA Report on Reactor and Spent Fuel Safety in the Light of
More informationImplementation of Lessons Learned from Fukushima Accident in CANDU Technology
e-doc 4395709 Implementation of Lessons Learned from Fukushima Accident in CANDU Technology Greg Rzentkowski Director General, Power Reactor Regulation Canadian Nuclear Safety Commission on behalf of CANDU
More informationStress tests specifications Proposal by the WENRA Task Force 21 April 2011
Stress tests specifications Proposal by the WENRA Task Force 21 April 2011 Introduction Considering the accident at the Fukushima nuclear power plant in Japan, the Council of the European Union declared
More informationSafety enhancement of NPPs in China after Fukushima Accident
Safety enhancement of NPPs in China after Fukushima Accident CHAI Guohan 29 June 2015, Brussels National Nuclear Safety Administration, P. R. China Current Development of Nuclear Power Mid of year 2015
More informationBrazilian Operator s Response to Fukushima Daiichi Accident Luiz Soares Technical Director
Simposyum Siting of New Nuclear Power Plants and Irradiated Fuel Facilities Buenos Aires Argentina 24-28 June 2013 Panel Fukushima Daiichi s Impact in Nuclear Power Programs Worldwide Brazilian Operator
More informationNuclear Power Plant Safety Basics. Construction Principles and Safety Features on the Nuclear Power Plant Level
Nuclear Power Plant Safety Basics Construction Principles and Safety Features on the Nuclear Power Plant Level Safety of Nuclear Power Plants Overview of the Nuclear Safety Features on the Power Plant
More informationConvention on Nuclear Safety
Implementation of the obligations of the Convention on Nuclear Safety CNS National Report of Switzerland for the Second Extraordinary Meeting in Accordance with Article 5 of the Convention May 2012 Implementation
More informationSafety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident. Ryodai NAKAI Japan Atomic Energy Agency
Safety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident Ryodai NAKAI Japan Atomic Energy Agency Contents Introduction Japanese Government Report to the IAEA
More informationCNE Cernavoda Response to Fukushima Event/EU Stress Test Requirements
CNE Cernavoda Response to Fukushima Event/EU Stress Test Requirements Sorin Holostencu IAEA Technical Meeting on Operational Experience with Implementation of Post-Fukushima Actions in Nuclear Power Plants,
More informationEuropean level recommendations Sect. in NAcP 2 Generic recommendation for WENRA, Finland participates and follows the work.
Cross reference table of ENSREG and Extraordinary CNS recommendations and national actions 1(16) 2.1 European guidance on assessment of natural hazards and margins The peer review Board recommends that
More informationMonitoring of the EU Stress test improvement actions in neighbouring countries
Monitoring of the EU Stress test improvement actions in neighbouring countries Public Workshop: Five Years Fukushima, Thirty Years Chernobyl 26 th February 2016 Approach Review & monitoring of post Fukushima
More informationRegulatory Actions and Follow up Measures against Fukushima Accident in Korea
Int Conference on Effective Nuclear Regulatory Systems, April 9, 2013, Canada Regulatory Actions and Follow up Measures against Fukushima Accident in Korea Seon Ho SONG* Korea Institute of Nuclear Safety
More informationFOSH Forsmark Safety Enhancement Project Post-Fukushima actions at Forsmark NPP
FOSH Forsmark Safety Enhancement Project Post-Fukushima actions at Forsmark NPP NKS January 12-13, 2016 Ove Nilsson Sekretessklass: Open (S1) 1 2015-12-23 FOSH Forsmark Safety Enhancement Project F-0003165
More informationCLASSIFICATION OF SYSTEMS, STRUCTURES AND COMPONENTS OF A NUCLEAR FACILITY
CLASSIFICATION OF SYSTEMS, STRUCTURES AND COMPONENTS OF A NUCLEAR FACILITY 1 Introduction 3 2 Scope of application 3 3 Classification requirements 3 3.1 Principles of safety classification 3 3.2 Classification
More informationWhy I love working in the energy sector. Joanna Weng (BKW) Probabilistic safety Nuclear Power Plant
Why I love working in the energy sector Joanna Weng (BKW) Probabilistic safety analyst @ Nuclear Power Plant My HEP career at CMS 2002: Diploma thesis @ : simulation study Higgs to 4 muons 2003-2006: PhD
More informationImprovements Needed in Nuclear Power Plant Probabilistic Risk Assessments: Lessons Learned from Fukushima
Improvements Needed in Nuclear Power Plant Probabilistic Risk Assessments: Lessons Learned from Fukushima Mohammad Modarres Professor of Nuclear Engineering Department of Mechanical Engineering University
More informationANTICIPATED ANALYSIS OF FLAMANVILLE 3 EPR OPERATING LICENSE - STATUS AND INSIGHTS FROM LEVEL 1 PSA REVIEW
ANTICIPATED ANALYSIS OF FLAMANVILLE 3 EPR OPERATING LICENSE - STATUS AND INSIGHTS FROM LEVEL 1 PSA REVIEW Gabriel Georgescu, Patricia Dupuy and Francois Corenwinder Institute for Radiological Protection
More informationInstitute of Nuclear Technology and Energy Systems
Institute of Nuclear Technology and Energy Systems Experimental and Analytical Investigation of the Performance of Heat Pipes for Residual Heat Removal from Spent Fuel Pools J. Starflinger, C. Graß, R.
More informationPresent Status of Kyoto University Research Reactor, KUR
18th IGORR conference/iaea Technical Meeting 3-7 Dec. 2017, Sydney, Australia Present Status of Kyoto University Research Reactor, KUR Ken NAKAJIMA Research Reactor Institute, Kyoto University 1 Accident
More informationHPR1000: ADVANCED PWR WITH ACTIVE AND PASSIVE SAFETY FEATURES
HPR1000: ADVANCED PWR WITH ACTIVE AND PASSIVE SAFETY FEATURES D. SONG China Nuclear Power Engineering Co., Ltd. Beijing, China Email: songdy@cnpe.cc J. XING China Nuclear Power Engineering Co., Ltd. Beijing,
More informationPlant-specific safety review (RSK-SÜ) of German nuclear power plants in the light of the events in Fukushima-1 (Japan)
Note: This is a translation of Chapter 1 of the document entitled STATEMENT - Anlagenspezifische Sicherheitsüberprüfung (RSK-SÜ) deutscher Kernkraftwerke unter Berücksichtigung der Ereignisse in Fukushima-I
More informationThe EU-Stresstest Dr. Christoph Pistner
The EU-Stresstest Dr. Christoph Pistner 23.10.2015 Nuclear power plants in Europe as of 25.05.2014 Reactors in operation: Europe (West): 117 KKW 113,5 GW el. Europe (Middle and east): 68 KKW 48,6 GW el.
More informationWestinghouse Small Modular Reactor. Passive Safety System Response to Postulated Events
Westinghouse Small Modular Reactor Passive Safety System Response to Postulated Events Matthew C. Smith Dr. Richard F. Wright Westinghouse Electric Company Westinghouse Electric Company 600 Cranberry Woods
More informationRESULTS OF THE GRADUAL UPGRADING AT BOHUNICE WWER - 440/230 NPP
RESULTS OF THE GRADUAL UPGRADING AT BOHUNICE WWER - 440/230 NPP P. Krupa Ingeneer, e-mail: Krupa_Peter@ebo.seas.sk Bohunice NPPs Introduction The centre of upgrading activities in VVER NPP is clearly in
More informationLessons Learned from Fukushima Daiichi Nuclear Power Station Accident and Consequent Safety Improvements
Hitachi Review Vol. 62 (2013), No. 1 75 Lessons Learned from Fukushima Daiichi Nuclear Power Station Accident and Consequent Safety Improvements Masayoshi Matsuura Kohei Hisamochi Shinichiro Sato Kumiaki
More informationPost-Fukushima Assessment of the AP1000 Plant
ABSTRACT Post-Fukushima Assessment of the AP1000 Plant Ernesto Boronat de Ferrater Westinghouse Electric Company, LLC Padilla 17-3 Planta 28006, Madrid, Spain boronae@westinghouse.com Bryan N. Friedman,
More informationReactor Technology: Materials, Fuel and Safety. Dr. Tony Williams
Reactor Technology: Materials, Fuel and Safety Dr. Tony Williams Course Structure Unit 1: Reactor materials Unit 2. Reactor types Unit 3: Health physics, Dosimetry Unit 4: Reactor safety Unit 5: Nuclear
More informationDESIGN AND SAFETY PRINCIPLES LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION
DESIGN AND SAFETY PRINCIPLES LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION VIENNA OKTOBER 3-6, 2016 1 ANPP * ANPP is located in the western part of Ararat valley 30 km west of Yerevan close to
More informationSTATUS, ACHIEVEMENTS & FUTURE CHALLENGES
STATUS, ACHIEVEMENTS & FUTURE CHALLENGES FOR KANUPP By Muhammad Rashidullah, Senior Manager Technical Division, KANUPP, Pakistan 13 th Meeting of TWG-HWR on Advance Technologies, June 18-20, 2012, Vienna,
More informationBelgian Stress Test Nuclear Power Plants (BEST)
Belgian Stress Test Nuclear Power Plants (BEST) 2013-08-26 TM IAEA: Belgian Stress Tests Stress Test Specifications Technical scope Initiating events Earthquake Flooding Other extreme natural events (extreme
More informationSwedish action plan. for nuclear power plants
Swedish action plan for nuclear power plants Response to ENSREG s request December 2012 Page 2 (48) Abstract Following the severe accidents which started in the Fukushima Dai-ichi nuclear power plant,
More informationProvision of containment integrity at Russian VVER NPPs under BDBA conditions
Provision of containment integrity at Russian VVER NPPs under BDBA conditions IAEA Technical Meeting Severe Accident Mitigation through Improvements in Filtered Containment Venting for Water Cooled Reactors
More informationProbabilistic Safety Assessment (PSA): Case Study Leibstadt NPP. Dr. Olivier Nusbaumer Probabilistic Safety Analysis Kernkraftwerk Leibstadt AG
Probabilistic Safety Assessment (PSA): Case Study Leibstadt NPP Dr. Olivier Nusbaumer Probabilistic Safety Analysis Kernkraftwerk Leibstadt AG Background Methodological Aspects Swiss Atomic Law Scope of
More informationThe Westinghouse Advanced Passive Pressurized Water Reactor, AP1000 TM. Roger Schène Director,Engineering Services
The Westinghouse Advanced Passive Pressurized Water Reactor, AP1000 TM Roger Schène Director,Engineering Services 1 Background Late 80: USA Utilities under direction of EPRI and endorsed by NRC : Advanced
More informationJoint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety. Trieste,12-23 October 2015
Joint ICTP- Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety Trieste,12-23 October 2015 Safety classification of structures, systems and components
More informationThe 2011 Tohoku Pacific Earthquake and Current Status of Nuclear Power Stations
The 2011 Tohoku Pacific Earthquake and Current Status of Nuclear Power Stations March 31, 2011 Tokyo Electric Power Company Tohoku Pacific Ocean Earthquake Time: 2:46 pm on Fri, March 11, 2011. Place:
More informationSEVERE ACCIDENT FEATURES OF THE ALTERNATIVE PLANT DESIGNS FOR NEW NUCLEAR POWER PLANTS IN FINLAND
SEVERE ACCIDENT FEATURES OF THE ALTERNATIVE PLANT DESIGNS FOR NEW NUCLEAR POWER PLANTS IN FINLAND Risto Sairanen Radiation and Nuclear Safety Authority (STUK) Nuclear Reactor Regulation P.O.Box 14, FI-00881
More informationAssessing and Managing Severe Accidents in Nuclear Power Plant
Assessing and Managing Severe Accidents in Nuclear Power Plant Harri Tuomisto Fortum, Finland IAEA Technical Meeting on Managing the Unexpected - From the Perspective of the Interaction between Individuals,
More informationSYSTEMATIC AND DESIGN SAFETY IMPROVEMENTS OF NPPS IN CZECH REPUBLIC
SYSTEMATIC AND DESIGN SAFETY IMPROVEMENTS OF NPPS IN CZECH REPUBLIC 3.10.2016 ČEZ, a. s. Meeting at IAEA Vienna Overview of topics ČEZ nuclear fleet (basic features) Systematic measures targeted to improve
More informationDevelopment and use of SAMGs in the Krško NPP
REPUBLIC OF SLOVENIA Development and use of SAMGs in the Krško NPP Tomaž Nemec Slovenian Nuclear Safety Administration tomaz.nemec@gov.si IAEA TM on the Verification and Validation of SAMGs, Vienna, 12
More informationIsolation Condenser; water evaporation in the tank and steam into the air. Atmosphere (in Severe Accident Management, both P/S and M/S)
Loss of Ultimate Heat Sink ANS AESJ AESJ Fukushima Symposium, March h4, 2012 Hisashi Ninokata, Tokyo Institute of Technology Available ultimate heat sinks at 1F1~3 1F1 (Fukushima Dai ichi Unit 1) Sea water
More informationAP1000 European 19. Probabilistic Risk Assessment Design Control Document
19.39 In-Vessel Retention of Molten Core Debris 19.39.1 Introduction In-vessel retention of molten core debris through water cooling of the external surface of the reactor vessel is a severe accident management
More informationPreparedness at PFBR Kalpakkam to meet the challenges due to Natural events Prabhat Kumar, Project Director, PFBR, Director construction BHAVINI
BHARATIYA NABHIKIYA VIDYUT NIGAM LIMITED (A Government of India Enterprise) Preparedness at PFBR Kalpakkam to meet the challenges due to Natural events Prabhat Kumar, Project Director, PFBR, Director construction
More informationEXPERIMENTS ON THE PERFORMANCE SENSITIVITY OF THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF AN ADVANCED INTEGRAL TYPE REACTOR
EXPERIMENTS ON THE PERFORMANCE SENSITIVITY OF THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF AN ADVANCED INTEGRAL TYPE REACTOR HYUN-SIK PARK *, KI-YONG CHOI, SEOK CHO, SUNG-JAE YI, CHOON-KYUNG PARK and MOON-KI
More informationSUMMARY OF SE NNEGC ENERGOATOM PERFORMANCE IN POST-FUKUSHIMA PERIOD
МИНИСТЕРСТВО ЭНЕРГЕТИКИ И УГОЛЬНОЙ ПРОМЫШЛЕННОСТИ УКРАИНЫ НАЦИОНАЛЬНАЯ АТОМНАЯ ЭНЕРГОГЕНЕРИРУЮЩАЯ КОМПАНИЯ SUMMARY OF SE NNEGC ENERGOATOM PERFORMANCE IN POST-FUKUSHIMA PERIOD D.V. Biley Inspector General
More informationThe ESBWR an advanced Passive LWR
1 IAEA PC-Based Simulators Workshop Politecnico di Milano, 3-14 October 2011 The ES an advanced Passive LWR Prof. George Yadigaroglu, em. ETH-Zurich and ASCOMP yadi@ethz.ch 2 Removal of decay heat from
More informationSMR/1848-T03. Course on Natural Circulation Phenomena and Modelling in Water-Cooled Nuclear Reactors June 2007
SMR/1848-T03 Course on Natural Circulation Phenomena and Modelling in Water-Cooled Nuclear Reactors 25-29 June 2007 Applications of Natural Circulation Systems N. Aksan Paul Scherrer Institut (PSI), Villingen,
More informationin China Nuclear and Radiation Safety Center, Ministry i of Environmental Protection, ti P. R. China August , Vienna
Post-Fukushima Safety Improvement Measures for NPPs in China ZHENG Lixin Nuclear and Radiation Safety Center, Ministry i of Environmental Protection, ti P. R. China August 26-2929 2013, Vienna 1 Background
More informationOPG Proprietary Report
N/A R001 2 of 114 Table of Contents Page List of Tables and Figures... 5 Revision Summary... 6 Executive Summary... 7 1.0 INTRODUCTION... 9 1.1 Objectives... 10 1.2 Scope... 10 1.3 Organization of Summary...
More informationPost-Fukushima Action Plan in Korea. WNU-SI 2011, August 11 Christ Church, Oxford
Post-Fukushima Action Plan in Korea WNU-SI 2011, August 11 Christ Church, Oxford Contents Korean nuclear overview BK Kim Government action plan BS Jeong Post-Fukushima action plan MK Jo Nuclear Power Plants
More informationChapter VI. VI.Situation regarding efforts to address lessons learned (28 items)
VI.Situation regarding efforts to address lessons learned (28 items) Japan is making its greatest possible efforts to address the 28 lessons learned indicated in the June report. The state of progress
More informationModule 05 WWER/ VVER (Russian designed Pressurized Water Reactors)
Module 05 WWER/ VVER (Russian designed Pressurized Water Reactors) 1.3.2016 Prof.Dr. Böck Technical University Vienna Atominstitut Stadionallee 2, 1020 Vienna, Austria ph: ++43-1-58801 141368 boeck@ati.ac.at
More informationModule 06 Boiling Water Reactors (BWR)
Module 06 Boiling Water Reactors (BWR) 1.10.2015 Prof.Dr. Böck Vienna University oftechnology Atominstitute Stadionallee 2 A-1020 Vienna, Austria ph: ++43-1-58801 141368 boeck@ati.ac.at Contents BWR Basics
More informationXII. Lessons Learned From the Accident Thus Far
XII. Lessons Learned From the Accident Thus Far The Fukushima NPS accident has the following aspects: it was triggered by a natural disaster; it led to a severe accident with damage to nuclear fuel, Reactor
More informationCAREM: AN INNOVATIVE-INTEGRATED PWR
18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18) Beijing, China, August 7-12, 2005 SMiRT18-S01-2 CAREM: AN INNOVATIVE-INTEGRATED PWR Rubén MAZZI INVAP Nuclear Projects
More informationEnsuring Spent Fuel Pool Safety
Ensuring Spent Fuel Pool Safety Michael Weber Deputy Executive Director for Operations U.S. Nuclear Regulatory Commission American Nuclear Society Meeting June 28, 2011 1 Insights from Fukushima Nuclear
More informationNuclear Power and Nuclear Safety Post Fukushima
Nuclear Power and Nuclear Safety Post Fukushima C. Pistner, M. Englert, Öko-Institut e.v. DPG AKE AGA: Nuclear Energy and Security Münster, 29.03.2017 Agenda 1 2 3 4 5 Status of Nuclear Power Today Review
More informationIntroduction to the 2015 Darlington NGS Probabilistic Safety Assessment. Carlos Lorencez and Robin Manley Ontario Power Generation August 2015
Introduction to the 2015 Darlington NGS Probabilistic Safety Assessment Carlos Lorencez and Robin Manley Ontario Power Generation August 2015 Introduction to the 2015 Darlington NGS Probabilistic Safety
More informationFlamanville 3 EPR Safety assessment and on-site inspections
Corine PIEDAGNEL - François TARALLO Bernard MONNOT Institut de Radioprotection et de Sûreté Nucléaire Flamanville 3 EPR Safety assessment and on-site inspections Flamanville 3 EPR Safety assessment and
More informationSAFETY GUIDES. Deterministic Safety Assessment РР - 5/2010 ÀÃÅÍÖÈß ÇÀ ßÄÐÅÍÎ ÐÅÃÓËÈÐÀÍÅ BULGARIAN NUCLEAR REGULATORY AGENCY
S ON IMPLEMENTATION OF THE LEGAL REQUIREMENTS Deterministic Safety Assessment РР - 5/2010 ÀÃÅÍÖÈß ÇÀ ßÄÐÅÍÎ ÐÅÃÓËÈÐÀÍÅ BULGARIAN NUCLEAR REGULATORY AGENCY TABLE OF CONTENTS 1. GENERAL PROVISIONS...2 LEGAL
More informationThe Nuclear Safety Authority (ASN - Autorité de Sûreté Nucléaire),
REPUBLIQUE FRANÇAISE ASN Resolution 2014-DC-0406 of 21 th January 2014 instructing Electricité de France - Société Anonyme (EDF-SA) to comply with additional prescriptions applicable to the Gravelines
More informationBelgian stress tests. National report on nuclear power plants. Man-made events
Belgian stress tests National report on nuclear power plants Man-made events This national report is issued by the Belgian regulatory body as part of the the programme of stress tests carried out on Belgian
More informationAPR1400 Safe, Reliable Technology
APR1400 Safe, Reliable Technology OECD/NEA Workshop on Innovations in Water-cooled Reactor Technology Paris, Feb 11 12, 2015 Presented by Shin Whan Kim Contents 1. Introduction 2. Major Safety Design Characteristics
More informationLessons learned from the accident at the Fukushima Daiichi Nuclear Power Plant
May 9, 2011 Lessons learned from the accident at the Fukushima Daiichi Nuclear Power Plant Technical Analysis Subcommittee Committee for Investigation of Nuclear Safety Atomic Energy Society of Japan We
More informationRisks Associated with Shutdown in PWRs
International Conference Nuclear Option in Countries with Small and Mi Opatija, Croatia, 1996 Risks Associated with Shutdown in PWRs Igor Grlicarev Slovenian Nuclear Safety Administration Vojkova 59, 1113
More informationSafety Enhancement of Nuclear Power Plant Post Fukushima. Kumiaki Moriya
International Conference on Nuclear Governance Post-Fukushima Marina Bay Sands, Singapore, 31 October 2013 Safety Enhancement of Nuclear Power Plant Post Fukushima October 31,2013 Kumiaki Moriya Hitachi-GE
More informationFRANCE LWR activities
FRANCE LWR activities Norbert NICAISE with contributions from AREVA-NP ASN French Nuclear Safety Authority, IRSN French Institute for Radiation Protection and Nuclear Safety (TSO of ASN), CEA French Atomic
More informationRegulation of existing and new nuclear power stations in South Africa in the light of the Fukushima Accident
Regulation of existing and new nuclear power stations in South Africa in the light of the Fukushima Accident O Phillips: Senior Executive Manager - National Nuclear Regulator The Fukushima Ministerial
More informationDesign of Traditional and Advanced CANDU Plants. Artur J. Faya Systems Engineering Division November 2003
Design of Traditional and Advanced CANDU Plants Artur J. Faya Systems Engineering Division November 2003 Overview Canadian Plants The CANDU Reactor CANDU 600 and ACR-700 Nuclear Steam Supply Systems Fuel
More informationNational Nuclear Safety Administration, P. R. China
Current NPPs in China In commercial operation: 32 Under construction: 24 (31 March 2016) 黑龙江 吉林 Hongyanhe Haiyang Shidaowan 新疆 辽宁 Tianwan 青海 甘肃 内蒙古宁夏 山西 北京天津河北山东 Qinshan&Fangjiasha n Qinshan 2 Qinshan
More informationInternational Atomic Energy Agency. Impact of Extreme Events on Nuclear Facilities following Fukushima. Dr C H Shepherd Nuclear Safety Consultant, UK
Impact of Extreme Events on Nuclear Facilities following Fukushima by Dr C H Shepherd Nuclear Safety Consultant, UK CRA PSA/HFA Forum 8-9 September 2011, Warrington Contents of the Presentation IAEA views
More informationControlled management of a severe accident
July 2015 Considerations concerning the strategy of corium retention in the reactor vessel Foreword Third-generation nuclear reactors are characterised by consideration during design of core meltdown accidents.
More informationPRESS CONFERENCE. 3 September Jean-Bernard LÉVY Chairman and CEO. Xavier URSAT Group Senior Executive VP - New Nuclear Projects and Engineering
PRESS CONFERENCE 3 September 2015 Jean-Bernard LÉVY Chairman and CEO Xavier URSAT Group Senior Executive VP - New Nuclear Projects and Engineering EDF, A RESPONSIBLE ELECTRICITY COMPANY, A CHAMPION OF
More informationConcepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant
8 Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant KOZO TABUCHI *1 MASAYUKI TAKEDA *2 KAZUO TANAKA *2 JUNICHI IMAIZUMI *2 TAKASHI KANAGAWA *3 ATMEA1 TM is a 3-loop 1100
More informationCAREM Prototype Construction and Licensing Status
IAEA-CN-164-5S01 CAREM Prototype Construction and Licensing Status H. Boado Magan a, D. F. Delmastro b, M. Markiewicz b, E. Lopasso b, F. Diez, M. Giménez b, A. Rauschert b, S. Halpert a, M. Chocrón c,
More informationThe Nuclear Safety Authority (ASN),
FRENCH REPUBLIC ASN resolution 2012-DC-0276 of 26 June 2012 instructing Électricité de France Société Anonyme (EDF-SA) to comply with additional requirements applicable to the Bugey NPP (Ain département)
More informationDesign Safety Considerations for Water-cooled Small Modular Reactors As reported in IAEA-TECDOC-1785, published in March 2016
International Conference on Topical Issues in Nuclear Installation Safety, Safety Demonstration of Advanced Water Cooled Nuclear Power Plants 6 9 June 2017 Design Safety Considerations for Water-cooled
More informationEnhancement of Nuclear Safety
Enhancement of Nuclear Safety Soon Heung Chang Handong Global University May 6, 2015 Contents 1 2 3 4 Importance of Energy Fundamentals of Nuclear Safety How to Enhance Nuclear Safety Closing Remarks 2
More informationYour partner for the right solution
Your partner for the right solution Project engineering of power stations Environment protection in energy sector Equipment supplying Supervision of installation of the equipment supplied Commissioning
More informationTraining Certification Categories
Training Certification Categories Residential Residential Building Inspector structures are free from hazardous structural conditions and comply with the UCC. Duties include inspection of footings and
More informationGerman Experimental Activities for Advanced Modelling and Validation Relating to Containment Thermal Hydraulics and Source Term
German Experimental Activities for Advanced Modelling and Validation Relating to Containment Thermal Hydraulics and Source Term H.-J. Allelein 1,2, S. Gupta 3, G. Poss 3, E.-A. Reinecke 2, F. Funke 4 1
More informationNUCLEAR POWER NEW NUCLEAR POWER PLANTS IN 2012
NUCLEAR POWER NEW NUCLEAR POWER PLANTS IN 2012 AP1000 IN FEBRUARY 2012, THE FIRST NUCLEAR POWER PLANTS IN THE US IN 35 YEARS WERE LICENSCED TO BEGIN CONSTRUCTION. TWO WESTINGHOUSE AP1000 NUCEAR REACTOR
More informationUnited States Industry Perspectives on Implementation of Post-Fukushima Actions
United States Industry Perspectives on Implementation of Post-Fukushima Actions Andrew Mauer Senior Project Manager, Risk Assessment, Nuclear Energy Institute Michael Powell Director, Fukushima Initiatives,
More informationUpdating on NPP Life Management, Long Term Operation and post-fukushima Issues in Spain
IAEA Technical Working Group on Life Management of Nuclear Power Plants (TWG-LMNPP) Vienna, February 22-24, 2017 Updating on NPP Life Management, Long Term Operation and post-fukushima Issues in Spain
More informationDesign, Safety Technology and Operability Features of Advanced VVERs
Technical Cooperation Project INT/4/142 Interregional Workshop on Advanced Nuclear Reactor Technology for Near Term Deployment IAEA Headquarters, Vienna, Austria, 4-8 July 2011 Design, Safety Technology
More informationPROBABILISTIC SAFETY ANALYSIS IN SAFETY MANAGEMENT OF NUCLEAR POWER PLANTS
PROBABILISTIC SAFETY ANALYSIS IN SAFETY MANAGEMENT OF NUCLEAR POWER PLANTS 1 GENERAL 3 2 PSA DURING THE DESIGN AND CONSTRUCTION OF A NPP 3 2.1 Probabilistic design objectives 3 2.2 Design phase 4 2.3 Construction
More informationNPP Simulators Workshop for Education - Passive PWR NPP & Simulator Overview
NPP Simulators Workshop for Education - Passive PWR NPP & Simulator Overview Wilson Lam (wilson@cti-simulation.com) CTI Simulation International Corp. www.cti-simulation.com Sponsored by IAEA Modified
More informationHigh Temperature Gas-Cooled Reactors Now More Than Ever!
High Temperature Gas-Cooled Reactors Now More Than Ever! Dr. Finis SOUTHWORTH Chief Technology Officer AREVA Inc. On behalf of the NGNP Industrial Alliance, LLC Washington DC Section ANS Rockville, MD
More informationAccident Management under Extreme Events
International Journal of Performability Engineering Vol. 10, No. 7, November 2014, pp. 669-680. RAMS Consultants Printed in India Accident Management under Extreme Events GEORGE VAYSSIER * NSC Netherlands,
More informationApplication for Permission to Extend the Operating Period and Application for Approval of Construction Plans of Unit 3 at Mihama Nuclear Power Station
November 26, 2015 The Kansai Electric Power Co., Inc. Application for Permission to Extend the Operating Period and Application for Approval of Construction Plans of Unit 3 at Mihama Nuclear Power Station
More informationNuScale SMR Technology
NuScale SMR Technology UK IN SMR; SMR IN UK Conference - Manchester, UK Tom Mundy, EVP Program Development September 25, 2014 Acknowledgement & Disclaimer This material is based upon work supported by
More informationRecent Approaches related to Safety Enhancement of Operating NPPs in Korea Tae Eun JIN KEPCO E&C
Int. Conf. on Topical Issues in Nuclear Installation Safety, Vienna Austria, 6~9 Jun. 2017 Recent Approaches related to Safety Enhancement of Operating NPPs in Korea Tae Eun JIN KEPCO E&C Contents 1. Introduction
More informationMeetings for Sharing International Knowledge and Experience on Stress Tests
Meetings for Sharing International Knowledge and Experience on Stress Tests Presented by: Peter Hughes, Ovidiu Coman, Javier Yllera Department of Nuclear Safety and Security Division of Nuclear Installation
More informationOPG Proprietary Report
N/A R001 2 of 121 Table of Contents Page List of Tables and Figures... 5 Revision Summary... 6 Executive Summary... 7 1.0 INTRODUCTION... 9 1.1 Objectives... 10 1.2 Scope... 10 1.3 Organization of Summary...
More informationRegulatory Guide Monitoring the Effectiveness of Maintenance at Nuclear Power Plants
Regulatory Guide 1.160 Revision 2 Page 1 of 14 Revision 2 March 1997 Regulatory Guide 1.160 Monitoring the Effectiveness of Maintenance at Nuclear Power Plants Publication Information (Draft issued as
More informationREGULATION ON ENSURING THE SAFETY OF NUCLEAR POWER PLANTS
REGULATION ON ENSURING THE SAFETY OF NUCLEAR POWER PLANTS Published SG, No. 66 of 30 July 2004, amended SG No. 46 of 12 June 2007, and amended SG No. 53 of 10 June 2008 Chapter One GENERAL PROVISIONS Art.
More informationEvaluation of AP1000 Containment Hydrogen Control Strategies for Post- Fukushima Lessons Learned
Evaluation of AP1000 Containment Hydrogen Control Strategies for Post- Fukushima Lessons Learned James H. Scobel and Hong Xu Westinghouse Electric Company, EEC 1000 Westinghouse Dr. Cranberry Township,
More informationAnalysis of Unprotected Transients in the Lead-Cooled ALFRED Reactor
Analysis of Unprotected Transients in the Lead-Cooled ALFRED Reactor G. Bandini (ENEA/Bologna) E. Bubelis, M. Schikorr (KIT/Karlsruhe) A. Alemberti, L. Mansani (Ansaldo Nucleare/Genova) Consultants Meeting:
More informationCAREM-25: a Low-Risk Nuclear Option. Rivera, S.S. and Barón, J.H.
CAREM-25: a Low-Risk Nuclear Option Rivera, S.S. and Barón, J.H. Presentado en: VI General Congress on Nuclear Energy VII CGEN Minascentro-Bello Horizonte, Brasil, 31 agosto al 3 setiembre 1999 CAREM-25:
More informationPALLAS A nuclear reactor
PALLAS A nuclear reactor fit for the future! IAEA Headquarters, Vienna, Austria 16 May 2011 Ir. Paul G.T. de Jong, Project Director PALLAS 1 Let s introduce myself Paul de Jong, degree in Physics of the
More information