United States Industry Perspectives on Implementation of Post-Fukushima Actions
|
|
- Jasper James
- 6 years ago
- Views:
Transcription
1 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, Arizona Public Service 28 March 2017 Vienna, Austria
2 Highlights Bias for action Regulatory response FLEX: Cornerstone of U.S. response Strategic solutions Summary 2
3 The Nuclear Energy Institute s Mission Foster the beneficial uses of nuclear technology before Congress, the White House and executive branch agencies, federal regulators, and state policy forums; proactively communicate accurate and timely information; and provide a unified industry voice on the global importance of nuclear energy and nuclear technology. 3
4 An Industry United The Way Forward: Building Blocks Maintain Focus on Excellence in Existing Plant Performance (INPO) Develop and Issue Lessons Learned from the Fukushima Events (INPO) Improve the Effectiveness of U.S. Industry Response Capability to Global Nuclear Events (INPO/NEI) Develop and Implement a Strategic Communications Plan (NEI) Develop and Implement the Industry's Regulatory Response (NEI) Participate and Coordinate with International Organizations (INPO/EPRI) Provide Technical Support and R&D Coordination (EPRI/NSSS Owners Groups) 4
5 A Bias for Action The Way Forward: Guiding Principles Ensure equipment and guidance, enhanced as appropriate, result in improvements in response effectiveness, using a diverse, flexible and performance-based approach for beyond design bases activities Address guidance, equipment and training to ensure long-term viability of safety improvements. Develop response strategies that are performance-based, risk-informed and account for unique site characteristics. Maintain a strong interface with federal regulators to ensure regulatory actions are consistent with safety significance and that compliance can be achieved in an efficient manner. Coordinate with federal, state and local government and their emergency response organizations on industry actions to improve overall emergency response effectiveness. Communicate aggressively the forthright approach the U.S. industry is taking to implement the lessons from the Fukushima Daiichi accident. 5
6 Regulatory Response 90 day report Near Term Task Force Recommendations Orders Address adequate protection 10 CFR 50.54(f) Request information to support regulatory decision making 6
7 NRC Orders Mitigating Strategies for beyond design basis events (FLEX) EA Reliable Hardened Vent for Mark I and II containments EA Spent Fuel Pool Level Instrumentation EA Severe Accident Capable Hardened Containment Vent System EA
8 NRC Request for Information - 10 CFR 50.54(f) Seismic and Flooding - Walkdowns confirm design basis - Hazard Reevaluations, utilize current methods of evaluation Emergency Preparedness - Staffing and Communications 8
9 Implementation Activities: All On or Ahead of Schedule 2019 VENTS - PHASE 2 LONG-TERM OVERSIGHT 2018 HARDENED VENTS - PHASE 1 SUPPLEMENTAL HAZARD EVALUATIONS 2017 NRC POST-COMPLIANCE INSPECTIONS NRC DOCUMENTATION OF REVIEWS MITIGATION OF BEYOND DESIGN BASIS EVENTS RULE 2016 MITIGATION STRATEGIES SPENT FUEL POOL LEVEL INSTRUMENTATION EMERGENCY PLANNING/RESPONSE UPGRADES REEVALUATION OF FLOODING AND SEISMIC HAZARDS DISPOSITION TIER 2&3 ACTIVITIES 9
10 Current Challenges Knowledge Transfer and Knowledge Management Sustainability Preservation and capitalization of significant investments Consistency in implementation inspections underway 10
11 Cornerstone of U.S. Response: FLEX NSRC Call from Affected Site Requesting NSRC Support FedEx ships from NSRC to either Staging Area or to Memphis or Phoenix Airport 11
12 NEI 12-06: Diverse and Flexible Coping Strategies (FLEX) Implementation Guide Defined external hazards, challenges and considerations including warning time Assumed initial conditions FLEX capabilities and storage requirements FLEX strategies and timing, phased approach Defense in depth concept Procedure integration On and off-site resources and capabilities Mitigation Strategy Assessments 12
13 Issue Resolution Battery Duty Cycles Boron Mixing BWR Anticipatory Venting CENTS Code FLEX Maintenance MAAP Analysis Shutdown Modes NOTRUMP Code SHIELD RCP Seals FLOWSERVE RCP Seals Westinghouse RCP Seals National SAFER Response Centers Change processes Maintenance rule Hoses and Cables 13
14 Suite of NEI Guidance NEI 12-01: Guideline for Assessing Beyond-Design-Basis Accident Response Staffing and Communications Capabilities NEI 12-02: Industry Guidance for Compliance with NRC Order EA to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation NEI 12-06: Diverse and Flexible Coping Strategies (FLEX) Implementation Guide NEI 13-06: Enhancements to Emergency Response Capabilities for Beyond- Design-Basis Accidents and Events NEI 14-01: Emergency Response Procedures and Guidelines for Beyond- Design-Basis Events and Severe Accidents NEI 14-06: Developing an Organization Approach to Beyond-Design-Basis Event Planning and Response Requirements NEI 16-06: Crediting Mitigating Strategies in Risk-Informed Decision Making NEI 16-08: Guidance for Optimizing the Use of Portable Equipment 14
15 FLEX Approach Phase Strategies 15
16 FLEX Approach Capability and Storage Capability - Diverse set of equipment with flexible deployment options and common connection points - Maintain core, containment and SFP cooling to mitigate the effects of beyond-design-basis external events Storage - Diverse locations or reasonably protected in structures consistent with commercial standards - Able to be functional in a time frame to preclude core damage 16
17 Protected Storage Example Monolithic Dome 17
18 National SAFER Response Centers Two national response centers capable of delivering equipment to any site in the U.S. within 24 hours Enough equipment to support (2) 2-unit sites simultaneously plus maintenance spares Each piece is designed to be flown in fixed wing aircraft and externally by helicopter Trained personnel deployed with equipment Standardized color coded connections Commercial grade equipment Support from other nuclear stations 18
19 National SAFER Response Center FLEX Equipment 19
20 SAFER Program and Equipment Electrical TPC Connectors Mechanical Storz Fittings 20
21 SAFER Program and Equipment National Response NSRC Center Memphis or Phoenix Call from Affected Site Requesting NSRC Support FedEx ships from NSRC to either Staging FedEx ships from NSRC to either Staging Area Area or to Memphis or Phoenix Airport or to Memphis or Phoenix Airport 21
22 Strategic Solutions Improve SAFETY and efficiency of the nuclear fleet with the use of portable equipment Maximize Areas of Credit Expand operational and regulatory credit given to mitigating strategies Maximize FLEXibility Expand where portable equipment is used in plant operations FLEX and Beyond Be inclusive of all portable equipment beyond just FLEX 22
23 Industry Framework Guidance Improving plant safety and operations using portable equipment Evaluating portable equipment in risk informed decision making 23
24 Example: Risk RCS Makeup Flowpath RWT CH Pumps (3) RCS 2A COLD LEG CS LPSI Other SI Train SDC HX CS Hdr 2B COLD LEG 1A COLD LEG HPSI 1B COLD LEG 24
25 Example: SFP RISK Makeup Flowpath DWST Demineralized Water Storage Tank ALTERNATE HEADER PRIMARY HEADER FLEX+1 Pump FLEX Pump Spent Fuel Pool 25
26 Summary Safety is our highest priority Significant safety enhancements achieved Substantial completion of Fukushima actions in 2016 Committed to timely completion of actions to comply with the NRC rulemaking Remarkable stakeholder involvement since 2011 has enabled U.S. success We appreciate the opportunity to participate in this important forum 26
Efficiency Bulletin: Maximizing the Benefit of Portable Equipment
March 23, 2017 Color Code: Green Efficiency Bulletin: 17-10 Maximizing the Benefit of Portable Equipment Utilize portable equipment, including equipment procured as a part of the B.5.b and FLEX programs,
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 informationUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C December
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 17. 2013 Mr. Michael J. Pacilio Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: THREE MILE ISLAND NUCLEAR
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 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 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 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 informationUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C August25, 2016
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August25, 2016 Mr. Jon A. Franke Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467 SUBJECT:
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 informationAre We Safer Now? The Future of Nuclear Power in the Northwest 3.5 Years After Fukushima
Are We Safer Now? The Future of Nuclear Power in the Northwest 3.5 Years After Fukushima Edwin S. Lyman Senior Scientist Union of Concerned Scientists October 2014 Fukushima: Why should we care? Because
More information12-051, To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, August 2012
Steven P. Kraft SENIOR DIRECTOR FUKUSHIMA RESPONSE COORDINATION & STRATEGY August 24, 2012 Ms. Cindy K. Bladey Chief, Rules, Announcements and Directives Branch Office of Administration U.S. Nuclear Regulatory
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 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 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 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 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 informationIndustry Guidance for Compliance with NRC Order EA , To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation
NEI 12-02 [Revision B] Industry Guidance for Compliance with NRC Order EA-12-051, To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation ACKNOWLEDGEMENTS The Nuclear Energy Institute
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 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 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 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 informationFrequently Asked Questions: Japanese Nuclear Energy Situation
NUCLEAR ENERGY INSTITUTE Frequently Asked Questions: Japanese Nuclear Energy Situation 1. What will be the impact of the Fukushima Daiichi accident on the U.S. nuclear program? It is premature to draw
More informationNuclear Power A Journey of Continuous Improvement
Nuclear Power A Journey of Continuous Improvement Westinghouse Non Proprietary Class 3 Our Place in Nuclear History Innovation 1886 and forever Implementation & Improvement 1957 through Today Renaissance
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 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 informationLow-Level Waste and Radiation Management
Low-Level Waste and Radiation Management Program Description Program Overview Nuclear power plants face significant regulatory, economic, environmental, and public perception pressures with respect to
More informationMarch 16, Mr. William M. Dean Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC
ANTHONY R. PIETRANGELO Senior Vice President and Chief Nuclear Officer 1201 F Street, NW, Suite 1100 Washington, DC 20004 P: 202.739.8081 arp@nei.org nei.org March 16, 2015 Mr. William M. Dean Director,
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 informationA DYNAMIC ASSESSMENT OF AUXILIARY BUILDING CONTAMINATION AND FAILURE DUE TO A CYBER-INDUCED INTERFACING SYSTEM LOSS OF COOLANT ACCIDENT
A DYNAMIC ASSESSMENT OF AUXILIARY BUILDING CONTAMINATION AND FAILURE DUE TO A CYBER-INDUCED INTERFACING SYSTEM LOSS OF COOLANT ACCIDENT Z.K. Jankovsky The Ohio State University Columbus, USA Email: jankovsky.3@osu.edu
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 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 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 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 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 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 informationWestinghouse SMR & Nuclear Fuel Overview
Westinghouse SMR & Nuclear Fuel Overview Carlos Leipner, Westinghouse VP Latin America Presented at LAS-ANS July 2014 Rio de Janeiro, Brasil 2014 Westinghouse Electric Company LLC, All Rights Reserved.
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 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 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 informationDOE Small Modular Reactor Licensing Technical Support Program Overview for National Conference of State Legislatures June 19, 2014
DOE Small Modular Reactor Licensing Technical Support Program Overview for National Conference of State Legislatures June 19, 2014 Tim Beville Office of Nuclear Energy U.S. Department of Energy Administration
More informationWestinghouse AP1000. Reactor
Westinghouse AP1000 A Third Generation Nuclear Reactor International Council on Systems Engineering (INCOSE) September 18, 2013 Andrew Drake, PMP Director, AP1000 Engineering Completion Engineering, Equipment
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 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 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 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 informationEVALUATION OF SAFETY CULTURE IN WANO PRE-STARTUP REVIEWS
EVALUATION OF SAFETY CULTURE IN WANO PRE-STARTUP REVIEWS Todd Brumfield World Association of Nuclear Operators (WANO) Atlanta, Georgia, USA ABSTRACT: The requirements for performance of pre-startup reviews
More informationPOLICY FOR SOFTWARE QUALITY ASSURANCE IN THE NUCLEAR POWER INDUSTRY
NUCLEAR ENERGY INSTITUTE NUCLEAR INFORMATION TECHNOLOGY STRATEGIC LEADERSHIP POLICY FOR SOFTWARE QUALITY ASSURANCE IN THE NUCLEAR POWER INDUSTRY NITSL-SQA-2005-01 Revision 0 March 7, 2005 ACKNOWLEDGEMENTS
More informationReadiness for Regulating Small Modular Reactors
Readiness for Regulating Small Modular Reactors Nuclear Energy Agency Workshop: Multilateral Cooperation in the Regulatory Reviews of Small Modular Reactors August 10-11, 2017 Ottawa, Ontario, Canada Ramzi
More informationPower Generation. Ronaldo Jenkins Electrical Engineering Branch Chief Office of New Reactors (NRO)
Power Generation Ronaldo Jenkins Electrical Engineering Branch Chief Office of New Reactors (NRO) Agenda Overview Design Considerations 10 Code of Federal Regulations (CFR) 50 10 CFR 50, General Design
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 informationASME As a Help to Export! Our Topic today: Nuclear Quality Assurance ASME NQA 1
ASME As a Help to Export! Our Topic today: Nuclear Quality Assurance ASME NQA 1 Karte: Wikipedia CIS GmbH Experts in ASME Code Consulting CIS GmbH Consulting Inspection Services 3 rd Party Inspection Training
More informationFOLLOW-UP TO THE FRENCH NUCLEAR POWER PLANT STRESS TESTS UPDATE OF THE ACTION PLAN OF THE FRENCH NUCLEAR SAFETY AUTHORITY (ASN) DECEMBER 2017
43 FOLLOW-UP TO THE FRENCH NUCLEAR POWER PLANT STRESS TESTS UPDATE OF THE ACTION PLAN OF THE FRENCH NUCLEAR SAFETY AUTHORITY (ASN) DECEMBER 2017 UPDATED NATIONAL ACTION PLAN OF THE FRENCH NUCLEAR SAFETY
More informationZion Project Overview S. Chris Baker VP EH&S
Zion Project Overview S. Chris Baker VP EH&S 1 Agenda Asset Sale Agreement Organization Nuclear Decommissioning Process Overview of Zion Station Decommissioning Schedule Near Term Activities Spent Fuel
More informationTHE NATIONAL REPORT OF SOUTH AFRICA FOR THE SECOND EXTRAORDINARY MEETING OF THE CONVENTION FOR NUCLEAR SAFETY
THE NATIONAL REPORT OF SOUTH AFRICA FOR THE SECOND EXTRAORDINARY MEETING OF THE CONVENTION FOR NUCLEAR SAFETY South African National Report August 2012 1 Table of Contents Executive Summary... 5 1 Purpose...
More informationNRC INSPECTION MANUAL INSPECTION PROCEDURE 35065
NRC INSPECTION MANUAL INSPECTION PROCEDURE 35065 DQASIP PROCUREMENT, RECEIVING, AND STORAGE PROGRAM APPLICABILITY: 2512 35065-01 INSPECTION OBJECTIVES To determine whether equipment procurement specifications
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 informationConcern 1 Additional Heat Load on the Containment Fears of Fission Rise at Stricken Nuclear Plant in Japan
Page 2 of 17 Introduction The AP1000 Oversight Group has previously identified serious concerns regarding the inability of the AP1000 Shield Building to act as an effective Ultimate Heat Sink (Sterrett)
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 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 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 informationWestinghouse Holistic Approach to the Nuclear Fuel Cycle
Westinghouse Holistic Approach to the Nuclear Fuel Cycle Dr. Thomas Congedo Director, Research and Technology Operations Westinghouse Electric Company LLC Symposium on the Future of Nuclear Energy Georgia
More informationPlant Life Management Canada
2017/02/22 TWG on LM for NPP Plant Life Management Canada - Copyright - General Utility Focus/Concerns Expanded focus last few years: Still driven primarily by desire to improve Equipment Reliability Index
More informationREGULATORY GUIDE An Approach for Using Probabilistic Risk Assessment In Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis
REGULATORY GUIDE 1.174 An Approach for Using... Page 1 of 38 July 1998 REGULATORY GUIDE 1.174 An Approach for Using Probabilistic Risk Assessment In Risk-Informed Decisions On Plant-Specific Changes to
More informationDOE TRANSPORTATION PROTOCOLS AN UPDATE
ABSTRACT DOE TRANSPORTATION PROTOCOLS AN UPDATE Carol A. Peabody U.S. Department of Energy, 1000 Independence Ave., S.W., Washington, D.C. 20585 Larry G. Blalock U.S. Department of Energy, 19901 Germantown
More informationAppendix B. Aging Management Programs and Activities
Appendix B Aging Management Programs and Activities This page is intentionally blank. TABLE OF CONTENTS Table of Contents...i Appendix B: Aging Management Programs and Activities... B.1-1 B.1 INTRODUCTION...
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 informationAccepting Supplier ISO 9000 Quality Programs
Accepting Supplier ISO 9000 Quality Programs IEEE Subcommittee on Qualification October 7-8, 2004 Leigh A. Aparicio PSE Technical Leader aparicio@epri.com Project Overview ISO 9000 Phase I Initiated in
More informationNuclear Power after Fukushima
Nuclear Power after Fukushima Michael Corradini American Nuclear Society President: http://ans.org UW Energy Institute Chair: http://www.energy.wisc.edu 1 ANS Special Committee on Fukushima The special
More informationNRC Activities. Matthew McConnell Senior Electrical Engineer Office of Nuclear Reactor Regulation
NRC Activities Matthew McConnell Senior Electrical Engineer Office of Nuclear Reactor Regulation Agenda Nuclear Power Plant Reviews Inspection News Regulatory Guide News Research Activities IEC/IEEE Joint
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 informationUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C SAFETY EVALUATION REPORT
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION REPORT Docket No. 72-1040 HI-STORM UMAX Canister Storage System Holtec International, Inc. Certificate of Compliance
More informationCurrent and Future Application of Seismic Research Activities at the NRC in Response to the Accident at the Fukushima Dai-ichi Nuclear Power Plant
Current and Future Application of Seismic Research Activities at the NRC in Response to the Accident at the Fukushima Dai-ichi Nuclear Power Plant Jon Ake, Jose Pires and Clifford Munson U.S. Nuclear Regulatory
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 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 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 informationINPO s Approach to Human Performance in the U.S. Commercial Nuclear Industry
INPO s Approach to Human Performance in the U.S. Commercial Nuclear Industry Tony Muschara Principal Program Manager Hu Institute of Nuclear Power Operations INPO s Mission to promote the highest levels
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 informationOffice of Nuclear Energy Research and Development. Jay Jones Office of Nuclear Energy Nuclear Fuels Storage and Transportation Planning Project
Office of Nuclear Energy Research and Development Jay Jones Office of Nuclear Energy Nuclear Fuels Storage and Transportation Planning Project Nuclear Energy Tribal Working Group Meeting January 27, 2016
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 informationInitiators and all barriers: a dynamic method for all PSAs
Initiators and all barriers: a dynamic method for all PSAs - A practitioners view on the practical implication on our PSAs Presented at the CRA s 8 th annual Risk Forum, 4 th -5 th October 2017 Presenter:
More informationJuly 29, 2011 R. William Borchardt, Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, DC
July 29, 2011 R. William Borchardt, Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT: Petition Pursuant to 10 CFR 2.206 Demand For Information Regarding
More informationIAEA SAFETY STANDARDS for protecting people and the environment. Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities
DS447 Date: 20 February 2015 IAEA SAFETY STANDARDS for protecting people and the environment STATUS: SPESS STEP 12 For submission to CSS Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle
More informationCaroline Schlaseman. MPR Associates Inc.
Small Modular Reactors Caroline Schlaseman Facilitator MPR Associates Inc. HI-SMUR 140: A Safe, Secure, Economic Small Modular Reactor Joy Russell Director, Corporate Business Development Holtec International
More informationThe Common Language of Nuclear Safety Culture (and how it affects you!) 8/13/2012. The Problem: The Uncommon Language of Nuclear Safety
The Common Language of Nuclear Safety Culture (and how it affects you!) Tom Houghton Certrec Corporation The Problem: The Uncommon Language of Nuclear Safety NRC looks at inspection results using cross
More informationEfficiency Bulletin: 16-27b Optimized Corporate Oversight and Assessment
Dec. 2, 2016 Color Code: GREEN Efficiency Bulletin: 16-27b Optimized Corporate Oversight and Assessment Oversight and assessment activities performed by corporate organizations and stations (for single-site
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 informationApplicability of EPRI Decommissioning Pre-Planning Manual to International Decommissioning Projects
Applicability of EPRI Decommissioning Pre-Planning Manual to International Decommissioning Projects Leo Lessard Manager, Commercial Decommissioning Operations, AREVA Inc. 16th February 2016 International
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 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 informationIntroduction to Level 2 PSA
Introduction to Level 2 PSA Dr Charles Shepherd Chief Consultant, Corporate Risk Associates CRA PSA/HFA FORUM 13-14 September 2012, Bristol Accident sequences modelled by the PSA INITIATING EVENTS SAFETY
More informationOSART Good Practices OPERATIONAL EXPERIENCE FEEDBACK Utilization and dissemination of operating experience
OSART Good Practices OPERATIONAL EXPERIENCE FEEDBACK Utilization and dissemination of operating experience St. Laurent, France Mission Date; 27 Nov.-14 Dec., 2006 Operational experience during outages
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 informationFedEx Express System Form
National Defense Transportation Association FedEx Express System Form Frank LeRose VP Global Network Planning and Operations Control What is System Form? Term used to describe the planned movement of all
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 informationThe Materials Initiative NEI Overview
The Materials Initiative NEI 03-08 Overview Robin Dyle EPRI Annual Materials/NRC Technical Exchange June 2, 2015 Overview Primary system materials integrity is vital to plant performance and reliability
More informationTechnical Working Group on Life Management of Nuclear Power Plants. Feb
Technical Working Group on Life Management of Nuclear Power Plants Feb. 25-27 2015 Safety Pre-Job Briefing Emergency Reporting : # 99 VIC Medical Service Emergency # 22222 Duty Security Office #3903 Meeting
More informationUse of PSA to Support the Safety Management of Nuclear Power Plants
S ON IMPLEMENTATION OF THE LEGAL REQUIREMENTS Use of PSA to Support the Safety Management of Nuclear Power Plants РР - 6/2010 ÀÃÅÍÖÈß ÇÀ ßÄÐÅÍÎ ÐÅÃÓËÈÐÀÍÅ BULGARIAN NUCLEAR REGULATORY AGENCY TABLE OF CONTENTS
More informationFAA/HSAC PART 135 SYSTEM SAFETY RISK MANAGEMENT SAFETY ELEMENT REQUIRED INSPECTION ITEMS (RII) JOB AID
SAFETY ELEMENT 1.3.4 REQUIRED INSPECTION ITEMS (RII) JOB AID The Federal Aviation Administration (FAA) is proactively moving away from compliance based safety surveillance programs to Systems Safety Risk
More informationOVER VIEW OF ACCIDENT OF FUKUSHIMA DAI-ICHI NPSs AND FUTURE PLANNING TOWARD D&D
OVER VIEW OF ACCIDENT OF FUKUSHIMA DAI-ICHI NPSs AND FUTURE PLANNING TOWARD D&D 16 NOVEMBER, 2011 Hiroshi RINDO JAPAN ATOMIC ENERGY AGENCY Table of Contents 1. What s happened at Fukushima Dai-Ichi NPSs
More informationNRC Participation and Perspectives on Codes and Standards for Nuclear Construction
NRC Participation and Perspectives on Codes and Standards for Nuclear Construction Emerging Technologies in Civil Infrastructure ACI Fall 2014 Convention October 26, 2014 Mrs. Carol Moyer Office of Nuclear
More information