Eletronuclear ( Brazil) Fukushima Response Plan
|
|
- Gilbert Maxwell
- 6 years ago
- Views:
Transcription
1 Eletronuclear ( Brazil) Fukushima Response Plan Edmundo Selvatici Site Manager Mario de Mello Ferreira Junior Manager, Materials Engineering Technical Meeting on Operational Experience with Implementation of Post-Fukushima Actions in Nuclear Power Plants march
2 Angra Nuclear Power Station (single NPP site in Brazil) ANGRA 1 PWR Power: 640 MW Technology: Westinghouse Operation start: Jan ANGRA 2 PWR Power: 1,350 MW Technology: KWU/ Siemens Operation start: Jan ANGRA 3 PWR Power: 1,405 MW Technology: KWU/ Siemens/ Areva Under construction Planned start of operation: 2022 (illustrative view) ANGRA 1 ANGRA 2 RADIOACTIVE WASTE STORAGE CENTER 500kV Switchyard 2
3 Plan in Full Integration with Nuclear Industry Initiatives Brazilian Nuclear Authority 3
4 Response to Fukushima Main Safety Goals
5 Response to Fukushima Evaluation of ST Report Basis: WENRA Specification for Stress Test Report FORO Angra 1 and Angra 2 NPPs Stress Test Report Evaluation 5
6 Protection from Hazard Events External Events Earthquakes; Rainfalls; Landslides; Tidal Waves; Tornadoes. Assessment of existing DB external event scope and design criteria for completeness and updating Assessment of safety margins of existing design in case of BD external events 1st step: simplified calculations, engineering/expert judgement 2nd step: detailed deterministic and probabilistic analyses. Internal Events Fire; Internal Flooding. Reevaluation considering up-to-date safety requirements; Identification of design gaps. 6
7 Protection from Hazard Events - Results Earthquakes Plants Seismic Design Low seismicity site (intraplaque region). Largest recorded earthquake 5.2 Richter scale at 300 km (PGA 0.002g at site); Design PGA for SSE: 0.1g (p< 10-4 /yr) based on deterministic seismic response spectrum. Evaluation of margins estimated safety margins relative to Design PGA by expert walkdown and judgement : for Angra 1 and for Angra 2; Extensive updating of geological and seismological database (three-years program completed); PGMRS( Probabilistic Ground Motion Response Spectrum) determined for use in the Seismic PSA; Seismic PSA for Angra 2 completed (safety margin: up to 4xDesign PGA) 8
8 Protection from Hazard Events - Results Rainfall and Landslides Evaluation of margins Studies considering heavy rains and consequential or seismic induced landslides concluded. Extreme case of full rupture of slope covering material evaluated. Slopes very steep around the site Residual and colluvial soils High rainfall rates Station protected by slope stabilization works and slope monitoring system 8 Results: For worst case switchyard and discharge channels may be affected however no impact on Plants buildings; Recommendation for enlargement of slope drainage system and reinforcement of some stabilization works (ongoing) 9
9 Protection from Hazard Events - Results External Flooding plant construction level access to safety buildings Angra 1 and m m 0 CNG Evaluation of margins: Reevaluation of flooding level under more severe conditions concluded (rainfall rate higher than 10,000 years rainfall, blockage of site drainage channels and circulating water discharge tunnel due to landslides, highest sea level). Results: Current design flooding level includes sufficient safety margin (up to years rainfall); Recommendation for checking and reinforcement of existing flooding barriers (finished). 9
10 Protection from Hazard Events - Results Tidal Waves calculation of tidal waves for severe metereological conditions( sea storms and hurricanes) at Ilha Grande Bay concluded; largest waves> maximum design wave for wave breaker design evaluation of wave breaker stability through physical model by international lab being contracted; Results may lead to recommendation of breaker structural reinforcement Angra NP Station Ilha Grande Bay Bay area, natural protection from Atlantic Ocean 11
11 Protection from Hazard Events - Results Tornadoes Tornadoes were not originally considered for Angra 1 and 2 due to low probability (~10-7/y); Tornado hazard study developed for Angra 3; Impact on Angra 1 and 2 evaluated and actions plans issued for further evaluation and/or protection of selected structures and components. Internal Fire Internal Flooding Fire Hazard of Angra 1 revised by EPRI (risk based evaluation); design modification packages under evaluation. Reevaluation of Angra 1 design against internal flooding; Recommendation to increase the safety margins under evaluation 11
12 Evaluation of Station Blackout Scenarios (SBO) Existing power supply conditions for Angra 1 and Angra 2 (Design or backfit) Cachoeira Paulista São José SE 500kV Zona Oeste SE 138kV Santa Cruz Off site Power Angra 1: 2x100% DG ( Plant Design) + 2x100% DG (backfit) Same cooling system for all DG A2 A1 Angra 2 Angra 1 4 x 50% 2 x 100% 4x 2x M G M G UBP D1 EDE 3/4 A2 A1 Emergency Diesels 1 st Emergency Power System Angra 2: 4x50% EDG + 4x50% EFDG in dedicated bunkered building with independent cooling system. M 4x G ULB D2 Minimum batery duration 2x 2x M G EAS 1A/1B 2,5h 4,0h 2 nd Emergency Power System both meet NRC requirements for exclusion of SBO 14
13 Existing SBO Emergency Procedures SG feeding through steam turbine driven pumps (Auxiliary Feedwater Turbine Pumps) in Angra 1 and Diesel Driven Emergency Feedwater Pumps in Angra 2); at least 20 hours in Angra 1 and 33 hours in Angra 2 of feeding from, respectively, Auxiliary Feedwater Tank - AFT and Demineralized Water Pools - DWP; possibility of AFT and DWP refilling from Fire Fighting Water Supply System - FFWS (5,000 m 3 reservoir, located on an elevation 110 m above the site level); possibility of full passive secondary B&F from the FFWS reservoir (connection before SG becomes empty, in case AF-2 or LAS pump fails, about 50 minutes). 15
14 Evaluation of Loss of Main Heat Sink Existing design conditions: water intake structures protected from open sea hazards (Ilha Grande Bay); water intake structures protected by wave breaker 8.0 m high above average seawater level; Availability of alternative heat sink by means of Fire Fighting Water Supply System - FFWS (5,000 m 3 reservoir, located on an elevation 110 m above the site level); alternative already incorporated in Emergency procedures for both Plants. Not designed for earthquake.. Main implications for the plants: Angra 1: failure of both Emergency Diesel Generator Systems (failure of common cooling system); Angra 2: Only EDG fail. Bunkered Emergency Feedwater Diesels (EFDG) not dependent of Service Water; impossibility of operating the RHR chain. 16
15 Provision of Cooling Capacity extreme conditions Deterministic evaluation approach (WENRA/FORO guidelines) no credit given to special design features or former backfits at the Angra plants no possibility of external support within 72h after the accident onset; Event Initial Conditions Loss of Offsite and Onsite Power (SBO) and Loss of Ultimate Heat Sink (LUHS) Plant in Power Operation 100% reactor power; Plant at Refueling (worst condition for fuel pool temperature) full core transferred to fuel pool; full loading of fuel pool storage racks; 15
16 Stress Test results Based on the Stress Tests results mobile equipment to provide additional means to supply power and cooling capacity for the core and the fuel pools were identified, specified and purchased, comprising different sizes of Diesel Generators, Diesel driven pumps and associated connection fixtures. General Concept adopted for Mobile equipment Equipment stored on site in location that is not affected by the external events that would affect the site, housed in a light tent-like structure commercial grade equipment; Mobile equipment connections specified in accordance to the Requirement Category of the systems where the connection is applied. Mobile equipment incorporated to the decision trees of the EOPs; Mobile equipment have specific procedures; not incorporated to the Tec Specs. 16
17 Stress Test results Design modification processes have been developed for the short and medium term strategies, in case of loss of all AC power and/or UHS, as follows: Short term (1 to 3 hours): recharging of batteries and Steam Generator feed. Mobile equipment : one 250 KVA DG and 2 Diesel Driven pumps per Plant; Countermeasure: Bleed and Feed through the secondary side. Medium term (1 to 2 days): in case of available UHS. Countermeasure: repowering one RHR cooling train Mobile equipment: 3 large DG, of 600 KVA each for Angra 1; 2 large DG, of 600 KVA each for Angra 2. Medium term (1 to 2 days): in case UHS is unavailable Countermeasure: continue Secondary B&F and replenish source of water for SG cooling (tank/pool) with sea water; Mobile equipment: 2 submergible Diesel powered pumps 16
18 Stress Test results The implementation of a new water reservoir of 4000 m 3 meeting seismic requirements located at a height able to provide means of feeding the steam generators in a totally passive way, is in phase of design completion. An alternative means of cooling the Diesel Groups in Angra 1, in case of loss of the Service Water System (SWS), was developed by installing a connection in the SWS piping for sea water injection with a mobile Diesel powered pump. 16
19 Overview of Additional Emergency Supply Alternatives Mobile DG (Emergency Power Supply for essential Safety Systems) 2017 status (completed) 2017 status (completed) Mobile DG (Emergency Power Supply for essential Safety Systems) Interconnection of Diesel Systems D1 and D2 (intended) 2017 status (design concluded) Alternative cooling chain for Angra 1 Emergency Power DG ANGRA 2 ANGRA 1 Mobile DG (extension of batteries autonomy) 2017 status (final implementation) 2017 status (final implementation) Mobile DG (extension of batteries autonomy) 17
20 Additional Alternatives for Reactor Cooling Alternatives for Reactor Cooling Via Steam Generators Angra 1 and Angra 2: Secondary side bleed-and-feed through the Steam Generators. (2017 status final implementation) Alternatives for Direct Reactor Cooling Angra 2 Primary side bleed-and-feed : Installation of additional valves in the Pressurizer valve station with dedicated power supply and I&C. (2017 status completed). Ensures depressurization of Primary System(bleed). 18
21 Additional Alternatives for Reactor Cooling Mobile Pumps for SG Feeding Mobile Pumps for Refilling Water Reservoirs Fire Hoses Mobile Ar Compressor for Remote Valve Actuation (Angra 1) 19
22 Mobile Equipment maintenance and storage Testing and Maintenance activities: - All tests and maintenance are being performed according the equipment supplier manuals; - Weekly sequence of DG performance tests, mobile pumps and mobile air compressor; 21
23 Loss of Fuel Pool Cooling Fuel Pool Temperature Increase after Loss of Cooling Unit Plant condition Time until start boiling Time until fuel element exposure Angra 1 Angra 2 Power Operation 28 h 179 h Refueling (*) 9 h 56 h Power Operation 23 h 136 h Refueling (*) 5 h 31 h (*) Full core unloaded and full occupation of pool racks Fuel Pool Cooling alternatives : Angra 1 (SFP in external Fuel Building): Feed to the SFP from outside fire fighting FF) water reservoir or FF truck. (2017) Angra 2( SFP inside Containment): fuel pool cooling using fire fighting water 2018) 22
24 Mitigation of Radiological Consequences Containment Protection: Passive H2 catalytic recombiners (PARs) already installed in Angra 1 and 2 (completed) Containment Filtered Venting (CFV): AREVA CFV (wet option) under design for Angra 2. Implementation in steps due to budget limitations Not yet decided for Angra 1. Severe Accident Management Guidelines (SAMGs): Angra 1: WOG SAMGs have been implemented and integrated with the Emergency Planning (EP) procedures. Angra 2: AREVA SAMGs have been developed, implemented and integrated with the Emergency planning procedures. Other improvements of the infrastructure for Emergency Planning Implementation of trails in emergency planning zones (completed) Improvements in Emergency Centers (underway) Improvements in radiological protection controls for Severe accident situations( underway) 23
25 Thank you for your attention. 24
Brazilian 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 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 informationPost Fukushima actions in India. Mukesh Singhal, Chief Engineer, Reactor Safety & Analysis Directorate NPCIL
Post Fukushima actions in India Mukesh Singhal, Chief Engineer, Reactor Safety & Analysis Directorate NPCIL 14 th Meeting of IAEA-TWG on advance technologies, IAEA, Vienna, June 18-20, 2013 Presentation
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 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 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 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 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 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 informationPost-Fukushima Actions in Korea
Post-Fukushima Actions in Korea IAEA TWG-LWR Vienna, June 18-20, 2013 Presented by Jong-Tae Seo 1. Impacts on National Energy Policy and NPP Plan 2. Actions Taken after Fukushima Accident 3. Findings and
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 information3 Steps Approach : KHNP s Implementation of Post Fukushima Actions. ST(Sung-Tae) Yang. General Manager Corporate Safety Department KHNP
3 Steps Approach : KHNP s Implementation of Post Fukushima Actions ST(Sung-Tae) Yang General Manager Corporate Safety Department KHNP Status of Nuclear Power Plants (As of Jan 2016) In Operation Under
More informationPreliminary 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 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 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 informationIndia s HWR Activities S.G.Ghadge Executive Director (Reactor Safety & Analysis) Nuclear Power Corporation of India Limited
India s HWR Activities S.G.Ghadge Executive Director (Reactor Safety & Analysis) Nuclear Power Corporation of India Limited 13 th Meeting of the Technical Working Group on Advanced Technologies for HWRs
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 informationThe Risk of Nuclear Power
13 th International Conference on Probabilistic Safety Assessment and Management [PSAM13] The Risk of Nuclear Power Soon Heung Chang Handong Global University Oct 4, 2016 Contents 1 2 3 4 Introduction:
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 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 informationLessons learned from Angra 1 & Angra 2 NPP s Outages
Lessons learned from Angra 1 & Angra 2 NPP s Outages DO Diretoria de Operação SM.O Superintendência de Manutenção Preparado por: Luciano Junqueira Calixto Email: lucical@eletronuclear.gov.br Angra 1: Angra
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 informationDr.-Ing. Rainer Kaulbarsch, Gösgen Power Plant (CH) August, 26th, 2013, Vienna
Safety Examinations and Improvements after Fukushima, Status Dr.-Ing. Rainer Kaulbarsch, Gösgen Power Plant (CH) August, 26th, 2013, Vienna Folie 1 Overview Introduction Examinations easures Outlook and
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 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 informationIAEA Training in level 1 PSA and PSA applications. Other PSA s. Low power and shutdown PSA
IAEA Training in level 1 PSA and PSA applications Other PSA s Low power and shutdown PSA Content Why shutdown PSA? Definitions Plat damage states and Plant operational states Specific modelling tasks of
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 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 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 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 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 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 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 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 informationComprehensive Safety Assessment for Kashiwazaki Kariwa NPS
Comprehensive Safety Assessment for Kashiwazaki Kariwa NPS International Experts Meeting on Reactor and Spent Fuel Safety in the Light of the Accident at the Fukushima Daiichi Nuclear Power Plant IAEA,
More informationINSIGHTS FROM COMPARISON OF TURBINE HALL FIRE RISK EVALUATED BY THE SIMPLIFIED AND DETAILED APPROACHES
INSIGHTS FROM COMPARISON OF TURBINE HALL FIRE RISK EVALUATED BY THE SIMPLIFIED AND DETAILED APPROACHES Gurgen Kanetsyan 1, Shahen Poghosyan 1, Armen Amirjanyan 1, Hovhannes Hovhannisyan 1 1 Nuclear and
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 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 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 informationResearch Article Extended Station Blackout Coping Capabilities of APR1400
Science and Technology of Nuclear Installations, Article ID 941, 1 pages http://dx.doi.org/1.1155/214/941 Research Article Extended Station Blackout Coping Capabilities of APR14 Sang-Won Lee, Tae Hyub
More informationSAMGs for German NPPs Main Features and Implementation Engineering & Projects (E&P)
SAMGs for German NPPs Main Features and Implementation Engineering & Projects (E&P) H. Plank, M. Braun, M. Loeffler Senior Advisor Severe Accidents Management Guidance AREVA GmbH, PEPA-G In collaboration
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 informationHarmonized EUR revision E requirements corresponding to currently available technical solutions
Harmonized EUR revision E requirements corresponding to currently available technical solutions Csilla TOTH - EUR Steering Committee MVM Paks II Ltd., Hungary, Technical Director IAEA International Conference
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 informationTHE FUKUSHIMA ACCIDENT: IMPLICATIONS FOR NUCLEAR SAFETY. Edwin Lyman Union of Concerned Scientists May 26, 2011
THE FUKUSHIMA ACCIDENT: IMPLICATIONS FOR NUCLEAR SAFETY Edwin Lyman Union of Concerned Scientists May 26, 2011 The accident: many unknowns Many of the details of the Fukushima Daiichi accident are still
More informationNuclear Power in Taiwan
East-Asian Nuclear Energy Forum Nuclear Safety after the Fukushima Accident Nuclear Power in Taiwan Lin Cheng-Chung April 26, 2013 Outline National Energy Policy Nuclear Power Performance in 2012 Safety
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 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 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 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 informationSafety Challenges for New Nuclear Power Plants
Implementing Design Extension Conditions and Fukushima Changes in the Context of SSR-2/1 Michael Case Office of Nuclear Regulatory Research United States Nuclear Regulatory Commission Outline of Presentation
More informationAttachment VIII-1. July 21, 2011 Nuclear and Industrial Safety Agency
Assessment Procedures and Implementation Plan Regarding the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities Taking into Account the Accident at Fukushima Dai-ichi Nuclear
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 informationExample Pressurized Water Reactor Defense-in-Depth Measures For GSI-191, PWR Sump Performance
Example Pressurized Water Reactor Defense-in-Depth Measures For GSI-191, PWR Sump Performance ATTACHMENT Introduction This paper describes a range of defense-in-depth measures that either currently exist
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 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 informationSmall Modular Reactors: A Call for Action
Small Modular Reactors: A Call for Action Overview of Five SMR Designs by Dr. Regis A. Matzie Executive Consultant Adapted May 2015 for the Hoover Institution's Reinventing Nuclear Power project from a
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 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 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 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 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 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 informationSafety Provisions for the KLT-40S Reactor Plant
6th INPRO Dialogue Forum on Global Nuclear Energy Sustainability: Licensing and Safety Issues for Small and Medium-sized Nuclear Power Reactors (SMRs) 29 July - 2 August 2013 IAEA Headquarters, Vienna,
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 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 informationRandy Lockwood, Senior Vice President CMD 18-H6.1A. PICKERING NUCLEAR GENERATING STATION Part I Hearing Licence Renewal April 4, 2018
Randy Lockwood, Senior Vice President CMD 18-H6.1A PICKERING NUCLEAR GENERATING STATION Part I Hearing Licence Renewal April 4, 2018 Presentation Outline Opening Remarks Performance Highlights Our Request
More informationTsunami Countermeasures at Hamaoka Nuclear Power Station
Tsunami Countermeasures at Hamaoka Nuclear Power Station Reference Reactor No. 5 Reactor No. 4 Reactor No. 3 Reactor No. 2 Reactor No. 1 March 16, 2012 2011 Chubu Electric Power Co., Inc. All rights reserved.
More informationIV. Occurrence and Development of the Accident at the Fukushima Nuclear Power Stations
IV. Occurrence and Development of the Accident at the Fukushima Nuclear Power Stations 1. Outline of Fukushima Nuclear Power Stations (1) Fukushima Daiichi Nuclear Power Station Fukushima Daiichi Nuclear
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 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 informationAP1000 European 15. Accident Analysis Design Control Document
15.2 Decrease in Heat Removal by the Secondary System A number of transients and accidents that could result in a reduction of the capacity of the secondary system to remove heat generated in the reactor
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 informationMain Steam & T/G Systems, Safety
Main Steam & T/G Systems, Safety Page 1 This steam generator, built for the Wolsong station in Korea, was manufactured in Canada by the Babcock and Wilcox company. In Wolsong 2,3, and 4 a joint venture
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 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 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 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 informationApplication of the Defense-in-Depth Concept in the Projects of New-Generation NPPs Equipped with VVER Reactors. JSC ATOMENERGOPROEKT Moscow
Application of the Defense-in-Depth Concept in the Projects of New-Generation NPPs Equipped with VVER Reactors Yu. Shvyryaev V. Morozov A. Kuchumov JSC ATOMENERGOPROEKT Moscow Content General information
More informationCANDU Safety #6 - Heat Removal Dr. V.G. Snell Director Safety & Licensing
CANDU Safety #6 - Heat Removal Dr. V.G. Snell Director Safety & Licensing 24/05/01 CANDU Safety - #6 - Heat Removal.ppt Rev. 0 vgs 1 Overview the steam and feedwater system is similar in most respects
More informationThe Nuclear Crisis in Japan
The Nuclear Crisis in Japan March 21, 2011 Daniel Okimoto Alan Hanson Kate Marvel The Fukushima Daiichi Incident 1. Plant Design 2. Accident Progression 3. Radiological releases 4. Spent fuel pools " Fukushima
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 informationMeasures against Earthquakes and Tsunamis in View of the Accident at Fukushima Daiichi Nuclear Power Station
Nuclear and Industrial Safety Agency Ministry of Economy, Trade and Industry IEM 3: International Expert s Meeting (Earthquakes / Tsunamis) 4-7 September, 2012 Vienna Measures against Earthquakes and Tsunamis
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 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 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 informationIAEA GIF Design Extension in Post Fukushima Scenario
IAEA GIF 26-2-13 Design Extension in Post Fukushima Scenario PrabhatKumar Chairman & Managing Director, BHAVINI Distinguished Scientist Department of atomic energy of India 1 Costal Earthquake of higher
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 informationFUKUSHIMA DAI-ICHI ACCIDENT: LESSONS LEARNED AND FUTURE ACTIONS FROM THE RISK PERSPECTIVES
FUKUSHIMA DAI-ICHI ACCIDENT: LESSONS LEARNED AND FUTURE ACTIONS FROM THE RISK PERSPECTIVES JOON-EON YANG Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, Daedeok-daero 989-111,
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 informationCNSC Evaluation of Plant-Specific SAMG
CNSC Evaluation of Plant-Specific SAMG Quanmin Lei IAEA Technical Meeting on Verification and Validation of SAMG Vienna, Austria December 12-14, 2016 e-docs # 5104918 nuclearsafety.gc.ca Outline Summarize
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 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 informationSpent Fuel and Spent Fuel Storage Facilities at Fukushima Daiichi
Spent Fuel and Spent Fuel Storage Facilities at Fukushima Daiichi The National Academies Lessons Learned from the Fukushima Nuclear Accident for Improving Safety and Security of U.S. Nuclear Plants: Phase
More informationThe Westinghouse AP1000 : Passive, Proven Technology to Meet European Energy Demands
BgNS TRANSACTIONS volume 20 number 2 (2015) pp. 83 87 The Westinghouse AP1000 : Passive, Proven Technology to Meet European Energy Demands N. Haspel Westinghouse Electric Germany GmbH, Dudenstraße 6, 68167
More informationSeismic PRA Insights and Lessons Learned
PSA 2015 International Topical Meeting On Probabilistic Safety Assessment and Analysis April 26-30, Sun Valley, ID Session 20-2: Seismic II, Paper 12324 Seismic PRA Insights and Lessons Learned Presentation:
More informationGUIDELINES FOR REGULATORY REVIEW OF EOPs AND SAMGs
GUIDELINES FOR REGULATORY REVIEW OF EOPs AND SAMGs CNCAN, ROMANIA 2016 1 TABLE OF CONTENTS 1. INTRODUCTION 1.1. Background 1.2. Purpose and scope of the guidelines 1.3. Structure of the guidelines 1.4.
More informationApplicability of PSA Level 2 in the Design of Nuclear Power Plants
Applicability of PSA Level 2 in the Design of Nuclear Power Plants Estelle C. SAUVAGE a, Gerben DIRKSEN b, and Thierry COYE de BRUNELLIS c a AREVA-NP SAS, Paris, France b AREVA-NP Gmbh, Erlangen, Germany
More informationSENIOR REGULATORS MEETING Strengthening the Implementation of Defence in Depth IAEA Perspective
SENIOR REGULATORS MEETING Strengthening the Implementation of Defence in Depth IAEA Perspective 58th IAEA General Conference 25 September 2014 James Lyons Director of the Division of Nuclear Installation
More information