CNSC Evaluation of Plant-Specific SAMG

Size: px
Start display at page:

Download "CNSC Evaluation of Plant-Specific SAMG"

Transcription

1 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 # nuclearsafety.gc.ca

2 Outline Summarize CNSC experience with severe accident management guidance (SAMG) evaluation Cover Regulatory basis and requirements Approach to and insights from recent SAMG evaluation Focus of ongoing work on severe accident management (SAM) 2

3 Post Fukushima Actions related to SAMG Implement key SAM provisions at each station by 2015 Expand scope of SAMG to include accidents triggered by multi-unit events and irradiated fuel bay events Completed for all NPPs in Canada Integrate Emergency Mitigating Equipment (EME) into overall SAM (e.g., EMEG/SAMG) Validate SAMG (e.g., through exercises and drills) to demonstrate their adequacy Regular activity 3

4 REGDOC Accident Management Sets requirements and guidance for licensees to develop, implement and evaluate integrated accident management Includes management of accidents in design basis Focuses on beyond design basis accidents, in particular, requiring SAM International guidance used IAEA NS-G-2.15, SRS-32, SSS-9 NEA Task Group on Accident Management WANO criteria for SAM Input from recognized experts Connects to emergency response 4

5 Verification and Validation (V&V) of SAMG (1) REGDOC V2 requires licensees (3.2) identify and implement reactor-specific accident management measures to ensure that adequate capabilities are maintained to cope with scenarios ranging from AOOs to severe accidents (3.4) develop, verify and validate accident management procedures and guidelines, including EOPs, emergency mitigating equipment guidelines (EMEGs) and SAMGs as applicable Integrated accident management helps ensure that personnel is trained and have necessary information, guidelines and resources 5

6 Verification and Validation (V&V) of SAMG (2) REGDOC V2 provides guidance for SAMG V&V The objectives of the verification and validation of accident management procedures and guidelines are to: demonstrate that procedures and guidelines achieve the goals for which they were developed confirm their usability (in terms of being easily understood and followed by their users) verify technical accuracy (meaning identification of the correct equipment and line-ups) assure completeness of scope (that is, to provide adequate guidance for expected activities) confirm that specified actions consider possible challenges and threats to the personnel and identify alternatives, where appropriate 6

7 Means to Increase SAMG V&V Tabletop exercises Plant walk-through Simulator training Plant drills, exercises, field rounds Independent peer review (e.g., WANO, IAEA) Analytical simulations Regulatory evaluation One method alone may be insufficient to assess SAMG effectiveness 7

8 Ongoing Improvement Regular exercises and drills feed back to strengthen ability to respond to accidents effectively and efficiently Regulatory (CNSC) evaluation of SAMG Single-unit CANDU-6 NPP in Involved independent experts with recent international experience In 2015, CNSC completed an evaluation of SAMG at a multi-unit NPP Intent to undertake similar evaluations at other NPPs 8

9 Objectives of Regulatory Evaluation Assess technical basis including station-specific aspects Assess adequacy of station-specific SAMG implementation, including Station-specific guidance Enhancements arising from Fukushima lessons Plan for SAMG drills and exercises Completeness of documentation Integration with other procedures/guidelines Personnel readiness 9

10 Scope and Overall Approach 10

11 Not in the scope, yet Past evaluations did not include Still ongoing SAMG updates to include multi-unit and irradiated fuel bay events PSA SAMG inter-influence Instrument and equipment survivability Performed assessment but Facility habitability assessment separately 11

12 Criteria Used Detailed review criteria developed from requirements Reflect CNSC staff experience obtained from the SAMG evaluations conducted to date Incorporate key insights from international publications Examples given below 12

13 Examples of Criteria For each of SAM goals: Is there adequate operational guidance to personnel involved in SAM? Are there sufficient design provisions and equipment to accomplish SAM actions? Is personnel prepared to perform actions identified in SAM? Are procedures and equipment adequate to deal with prolonged station blackout, SGTR, LOCA, etc. Are entry and exit conditions for different guidelines defined? 13

14 Examples of Evaluation Outcome The review of EMEG and its integration with other procedures and guidelines were undertaken through observation of EME storage and deployment locations, connection points, EME drills and a full-scale plant severe accident exercise during which EME was used. The review team also interviewed the site staff responsible for EME deployment. As a result, the review team concluded that The EME scope and deployment processes are well established. The licensee s emergency response team is well trained and qualified. Based on drill results, the team has demonstrated its capability to deploy the necessary EME as required. 14

15 Examples of Evaluation Outcome Interviews with site staff were found to be an effective means to gain insights into the strengths of SAM team. Examples of observations: The interviewees showed station personnel understanding of roles and responsibilities and their competence in fulfilling them. The interviews indicated a strong leadership within the technical support group (TSG). However, there appeared to be only one highly qualified TSG lead. It was not clear how the licensee would maintain leadership within the TSG if the specific expert is unavailable. 15

16 Examples of Evaluation Outcome A multi-unit drill was carried out involving: two (A &B) stations, two different reactor core designs, two groups of staff, and two sets of manuals, procedures, and guidelines. During the drill, there were two authorized nuclear operators (ANOs) with the TSG. The ANOs presence was not a requirement. It was observed that their presence added detailed knowledge of plant configuration and operation, and also helped speak the same language as the control room staff, thus enhancing communication. Therefore, participation of ANO in TSG was considered as a commendable practice. 16

17 Examples of Evaluation Outcome A number of technical questions arose during review of documentation What is the impact of an earlier or later initiation of the action that has been selected from the SAMG by the TSG for implementation? What are the environmental conditions at the time of an action? What are the potential positive and negative consequences resulting from SAMG-specified actions? CNSC staff undertook limited analyses to gain insights in accident progression and impact from SAM actions, and concluded: Simulations of SAMG actions allowed improved understanding of the temporal constraints and environmental conditions under which actions may be carried out and thus helped with evaluation of SAMG feasibility and efficiency 17

18 Focus of Ongoing Work on SAM Accident management in case of external events Earthquakes, tornado, flooding, fire, man-made events Irradiated fuel bay (long time available for make-up) Multi-unit Hydrogen control and mitigation Containment venting strategies 18

19 Examples of Design Enhancement for SAM Point Lepreau emergency filtered vent stack Containment cooling enhancement through repowering Containment Air Coolers Hydrogen Control and Mitigation Licensees have enhanced hydrogen control through installation of PARs. 19

20 Conclusions CNSC evaluation to date has identified strengths of the SAM program as well as several opportunities for improvement Station-specific SAM programs have been developed based on the generic CANDU SAMG with consideration of factors specific to the plant design SAM programs have been implemented at all sites. The organizational structure of SAM program with the roles and responsibilities of all participants clearly established Tabletop exercises and plant drills have been conducted to validate the plant-specific SAMG, including EMEG, and demonstrate their effectiveness CNSC will continue to evaluate the SAM programs for other NPPs 20

21 nuclearsafety.gc.ca facebook.com/canadiannuclearsafetycommission youtube.ca/cnscccsn CNSC Copyright 2015

Development and use of SAMGs in the Krško NPP

Development 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 information

Highlights of the Technical Meeting on the Verification and Validation of Severe Accident Management Guidelines

Highlights of the Technical Meeting on the Verification and Validation of Severe Accident Management Guidelines Highlights of the Technical Meeting on the Verification and Validation of Severe Accident Management Guidelines Lovell Gilbert Vienna International Centre, Austria 14 December 2016 Meeting highlights Opening

More information

GUIDELINES FOR REGULATORY REVIEW OF EOPs AND SAMGs

GUIDELINES 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 information

International Atomic Energy Agency. Impact of Extreme Events on Nuclear Facilities following Fukushima. Dr C H Shepherd Nuclear Safety Consultant, UK

International 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 information

Meetings for Sharing International Knowledge and Experience on Stress Tests

Meetings 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 information

Belgian Stress Test Nuclear Power Plants (BEST)

Belgian 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 information

European level recommendations Sect. in NAcP 2 Generic recommendation for WENRA, Finland participates and follows the work.

European 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 information

Guidance on the Use of Deterministic and Probabilistic Criteria in Decision-making for Class I Nuclear Facilities

Guidance on the Use of Deterministic and Probabilistic Criteria in Decision-making for Class I Nuclear Facilities DRAFT Regulatory Document RD-152 Guidance on the Use of Deterministic and Probabilistic Criteria in Decision-making for Class I Nuclear Facilities Issued for Public Consultation May 2009 CNSC REGULATORY

More information

CNE Cernavoda Response to Fukushima Event/EU Stress Test Requirements

CNE 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 information

Background. Introduction. Overview of vendor design review process

Background. Introduction. Overview of vendor design review process Executive Summary A pre-licensing review of a new nuclear power plant (NPP), also referred to as a vendor design review (VDR), provides an opportunity for CNSC staff to assess a design prior to any licensing

More information

The Evolution of System Safety in the Canadian Nuclear Industry

The Evolution of System Safety in the Canadian Nuclear Industry Canadian Nuclear Safety Commission Commission canadienne de sûreté nucléaire The Evolution of System Safety in the Canadian Nuclear Industry System Safety Society, Eastern Canada Chapter, June 18, 2009

More information

Également publié en français sous le titre de : Rapport de surveillance réglementaire des centrales nucléaires au Canada : 2014

Également publié en français sous le titre de : Rapport de surveillance réglementaire des centrales nucléaires au Canada : 2014 Canadian Nuclear Safety Commission (CNSC) 2015 PWGSC catalogue number CC171-25E-PDF ISSN 2369-5579 Extracts from this document may be reproduced for individual use without permission provided the source

More information

Swedish action plan. for nuclear power plants

Swedish 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 information

Major: Title change does not reflect that the intent of the document is the design of NEW nuclear power plants.

Major: Title change does not reflect that the intent of the document is the design of NEW nuclear power plants. REGDOC-2.5.2, Design of Reactor Facilities: Nuclear Power Plants / Conception d'installations dotées de réacteurs : centrales nucléaires Comments received from additional consultation / Commentaires reçus

More information

EVALUATION OF SAFETY CULTURE IN WANO PRE-STARTUP REVIEWS

EVALUATION 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 information

Proposed Regulations to Ship Large Objects as Surface Contaminated Objects

Proposed Regulations to Ship Large Objects as Surface Contaminated Objects Proposed Regulations to Ship Large Objects as Surface Contaminated Objects The 18 th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2016) Kobe, Japan nuclearsafety.gc.ca

More information

Ontario Power Generation Inc. Darlington Nuclear Generating Station. Ontario Power Generation Inc. Centrale nucléaire de Darlington

Ontario Power Generation Inc. Darlington Nuclear Generating Station. Ontario Power Generation Inc. Centrale nucléaire de Darlington UNPROTECTED/NON PROTÉGÉ ORIGINAL/ORIGINAL CMD: 15-H8 Date signed/signé le : 8 JULY 2015 A Licence Renewal Un renouvellement de permis Ontario Power Generation Inc. Darlington Nuclear Generating Station

More information

Probabilistic Safety Assessment Safety & Regulatory Framework

Probabilistic Safety Assessment Safety & Regulatory Framework Probabilistic Safety Assessment Safety & Regulatory Framework Presentation to the CNSC August 2017 Dr. V.G. Snell 1 Purpose To summarize work done under CNSC contract 87055-16-0251: Role of the Probabilistic

More information

The Stress Test Process in France (CSA*) Its impact on Research Facilities

The Stress Test Process in France (CSA*) Its impact on Research Facilities BgNS International Conference NUCLEAR POWER FOR THE PEOPLE 10 13 October 2012, AUGUSTA SPA Hotel, Hissar, Bulgaria The Stress Test Process in France (CSA*) ---- Its impact on Research Facilities G. Cognet

More information

Brazilian Operator s Response to Fukushima Daiichi Accident Luiz Soares Technical Director

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 information

Regulatory Guide Monitoring the Effectiveness of Maintenance at Nuclear Power Plants

Regulatory 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 information

Reactor Facilities Licence to Prepare Site and Site Evaluation for New Reactor Facilities REGDOC-1.1.1

Reactor Facilities Licence to Prepare Site and Site Evaluation for New Reactor Facilities REGDOC-1.1.1 Reactor Facilities Licence to Prepare Site and Site Evaluation for New Reactor Facilities REGDOC-1.1.1 August 2016 Licence to Prepare Site and Site Evaluation for New Reactor Facilities Regulatory document

More information

The EU-Stresstest Dr. Christoph Pistner

The 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 information

Workshop Information IAEA Workshop

Workshop Information IAEA Workshop IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Overview of Deterministic Safety Analysis: Input Data, Verification & Validation, Conservative/BE Approaches (Part. 2) Lecturer

More information

Ageing Management and Long Term Operation of Nuclear Power Plants

Ageing Management and Long Term Operation of Nuclear Power Plants Ageing Management and Long Term Operation of Nuclear Power Plants Senior Regulators Meeting 17 September 2015 Jan BENS AGENDA Belgian Nuclear Reactor Sites LTO Legal Framework LTO Regulatory Framework

More information

WGRISK Site-Level Project: Status update and Preliminary insights for the Risk Aggregation focus area

WGRISK Site-Level Project: Status update and Preliminary insights for the Risk Aggregation focus area WGRISK Site-Level Project: Status update and Preliminary insights for the Risk Aggregation focus area S. Yalaoui, Y. Akl (CNSC, Canada), D. Hudson (US NRC), and M. Roewekamp (GRS, Germany) PSA 2017 Pittsburgh,

More information

Belgian stress tests. National report on nuclear power plants. Man-made events

Belgian 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 information

Readiness for Regulating Small Modular Reactors

Readiness 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 information

Applicability of PSA Level 2 in the Design of Nuclear Power Plants

Applicability 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 information

Efficiency Bulletin: Maximizing the Benefit of Portable Equipment

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 information

Overview of IAEA's Projects on Safety Goals and Integrated Risk Informed Decision Making

Overview of IAEA's Projects on Safety Goals and Integrated Risk Informed Decision Making Overview of IAEA's Projects on Safety Goals and Integrated Risk Informed Decision Making Presented by: Irina Kuzmina, PhD, Safety Officer Safety Assessment Section/ Division of Nuclear Installation Safety/

More information

The Fukushima Daiichi Accident

The Fukushima Daiichi Accident The Fukushima Daiichi Accident A matter of unchallenged basic assumptions Monica Haage, Division of Nuclear Installation Safety, International Atomic Energy Agency Objectives Provide a background on the

More information

SNC-Lavalin Nuclear Comments on Draft Discussion Paper DIS Small Modular Reactors: Regulatory Strategy, Approaches and Challenges

SNC-Lavalin Nuclear Comments on Draft Discussion Paper DIS Small Modular Reactors: Regulatory Strategy, Approaches and Challenges 2016 September 21 Mr Brian Torrie Director General, Regulatory Policy Directorate Canadian Nuclear Safety Commission P.O. Box 1046, Station B 280 Slater Street Ottawa, Ontario, Canada K1P 5S9 Dear Mr Torrie,

More information

For reference, the key elements of a StarCore Nuclear (StarCore) reactor plant project are:

For reference, the key elements of a StarCore Nuclear (StarCore) reactor plant project are: StarCore Nuclear Response and Comments, 23 September 2016, On CNSC Discussion Paper DIS-16-04, March 2016 Small Modular Reactors: Regulatory Strategy, Approaches and Challenges Introduction The discussion

More information

OPG Proprietary Report

OPG 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 information

SYSTEMATIC AND DESIGN SAFETY IMPROVEMENTS OF NPPS IN CZECH REPUBLIC

SYSTEMATIC 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 information

Challenges for Regulators

Challenges for Regulators Challenges for Regulators Past, Present and Future Dr. Michael Binder President and Chief Executive Officer Canadian Nuclear Safety Commission Presentation to the Federal Provincial Territorial Radiation

More information

CMMI-DEV V1.3 CMMI for Development Version 1.3 Quick Reference Guide

CMMI-DEV V1.3 CMMI for Development Version 1.3 Quick Reference Guide processlabs CMMI-DEV V1.3 CMMI for Development Version 1.3 Quick Reference Guide CMMI-DEV V1.3 Process Areas Alphabetically by Process Area Acronym processlabs CAR - Causal Analysis and Resolution...

More information

Post-Fukushima Assessment of the AP1000 Plant

Post-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 information

Enhancement of Nuclear Safety

Enhancement 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 information

Improvement and Harmonisation in Nuclear Safety through Peer Reviews Key Note 2 Dr. Anton von Gunten, Mühleberg NPP BKW FMB Energie AG

Improvement and Harmonisation in Nuclear Safety through Peer Reviews Key Note 2 Dr. Anton von Gunten, Mühleberg NPP BKW FMB Energie AG Improvement and Harmonisation in Nuclear Safety through Peer Reviews Key Note 2 Dr. Anton von Gunten, Mühleberg NPP BKW FMB Energie AG Brussels, 25 April 2013 Plant Information Chronology of the Mühleberg

More information

SAFETY GUIDES. Deterministic Safety Assessment РР - 5/2010 ÀÃÅÍÖÈß ÇÀ ßÄÐÅÍÎ ÐÅÃÓËÈÐÀÍÅ BULGARIAN NUCLEAR REGULATORY AGENCY

SAFETY 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 information

Research on Integration of NPP Operational Safety Management Performance Systems

Research on Integration of NPP Operational Safety Management Performance Systems Research on Integration of NPP Operatioanl Safety Management Performance System Research on Integration of NPP Operational Safety Management Performance Systems Miao CHI 1, Liping SHI 2 1. School of Economics

More information

APPROACH TO PRACTICAL ELIMINATION IN FINLAND

APPROACH TO PRACTICAL ELIMINATION IN FINLAND M-L. JÄRVINEN et al. APPROACH TO PRACTICAL ELIMINATION IN FINLAND M-L. JÄRVINEN Radiation and Nuclear Safety Authority (STUK) Helsinki, Finland Email: marja-leena.jarvinen@stuk.fi N. Lahtinen Radiation

More information

Safety Framework for Nuclear Power Source Applications in Outer Space

Safety Framework for Nuclear Power Source Applications in Outer Space Safety Framework for Nuclear Power Source Applications in Outer Space NASA/ESA/ASI/JPL The IAEA Safety Glossary clarifies and harmonizes terminology and usage in the IAEA safety standards. To this end,

More information

DECOMMISSIONING OF NUCLEAR FACILITIES IN UKRAINE

DECOMMISSIONING OF NUCLEAR FACILITIES IN UKRAINE DECOMMISSIONING OF NUCLEAR FACILITIES IN UKRAINE Tatiana Kilochytska State Nuclear Regulatory Committee of Ukraine Annual Forum for Regulators and Operators in the Field of Decommissioning International

More information

Licensing Nuclear Power Plants in Canada. Ensuring Safe and Environmentally Acceptable Operations

Licensing Nuclear Power Plants in Canada. Ensuring Safe and Environmentally Acceptable Operations Licensing Nuclear Power Plants in Canada Ensuring Safe and Environmentally Acceptable Operations Nuclear Power the ultimate Energy Source It s been around a long time Nuclear power closer to home Needs

More information

ISO 14001: 2015 Environmental Gap Analysis

ISO 14001: 2015 Environmental Gap Analysis Environmental Gap Analysis The revised ISO 14001 standard was published on 14 TH September 2015. How to use this document This document provides an overview of the changes between ISO 14001:2004 and ISO

More information

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C August25, 2016

UNITED 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 information

The Nuclear Safety Authority (ASN),

The 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 information

Probabilistic 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 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 information

Power 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) 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 information

IAEA SAFETY STANDARDS for protecting people and the environment. Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities

IAEA 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 information

Rapport national du Canada pour la Convention sur la sûreté nucléaire Quatrième Rapport

Rapport national du Canada pour la Convention sur la sûreté nucléaire Quatrième Rapport Rapport national du Canada pour la Convention sur la sûreté nucléaire Quatrième Rapport Ministre des Travaux publics et Services gouvernementaux Canada 2007 Numéro de catalogue CC172-18/2007E-PDF ISBN

More information

Development of a Data Standard for V&V of Software to Calculate Nuclear System Thermal-Hydraulic Behavior

Development of a Data Standard for V&V of Software to Calculate Nuclear System Thermal-Hydraulic Behavior Development of a Data Standard for V&V of Software to Calculate Nuclear System Thermal-Hydraulic Behavior www.inl.gov Richard R. Schultz & Edwin Harvego (INL) Ryan Crane (ASME) Topics addressed Development

More information

FUKUSHIMA 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 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 information

Introduction to Level 2 PSA

Introduction 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 information

Safety Performance Indicators Program. Vidal, P.G.

Safety Performance Indicators Program. Vidal, P.G. Safety Performance Indicators Program Vidal, P.G. Presentado en: Technical Meeting on NPP Safety Performance Indicators for Use by the Regulatory Organizations. Viena, Austria, 17-21 noviembre 2003 SAFETY

More information

SAFETY REQUIREMENTS IN FRANCE FOR THE PROTECTION AGAINST EXTREME EARTHQUAKES

SAFETY REQUIREMENTS IN FRANCE FOR THE PROTECTION AGAINST EXTREME EARTHQUAKES SAFETY REQUIREMENTS IN FRANCE FOR THE PROTECTION AGAINST EXTREME EARTHQUAKES French Safety Authority Nuclear Power Plants Department Radioprotection and Nuclear Safety Institute IRSN/PRP-DGE/SCAN/BERSSIN

More information

CMMI-SVC V1.3 CMMI for Services Version 1.3 Quick Reference Guide

CMMI-SVC V1.3 CMMI for Services Version 1.3 Quick Reference Guide processlabs CMMI-SVC V1.3 CMMI for Services Version 1.3 Quick Reference Guide CMMI-SVC V1.3 Process Areas Alphabetically by Process Area Acronym processlabs CAM - Capacity and Availability Management...

More information

The Nuclear Safety Authority (ASN - Autorité de Sûreté Nucléaire),

The 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 information

SASOR Canada Ltd. Tetra Tech Inc. 4S reactor applications - Economic case studies. May 2009

SASOR Canada Ltd. Tetra Tech Inc. 4S reactor applications - Economic case studies. May 2009 SASOR Canada Ltd Tetra Tech Inc. 4S reactor applications - Economic case studies May 2009 Agenda Roles of Tetra Tech and SASOR Canada Why the 4S Reactor and not others Size Production and Cost Environmental

More information

RESULTS OF THE GRADUAL UPGRADING AT BOHUNICE WWER - 440/230 NPP

RESULTS 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 information

TABLE OF CONTENTS ABBREVIATIONS 1.0 DEFINITIONS PURPOSE AND SCOPE GUIDELINES FOR PRACTICE REFERENCES AND RELATED DOCUMENTS 12

TABLE OF CONTENTS ABBREVIATIONS 1.0 DEFINITIONS PURPOSE AND SCOPE GUIDELINES FOR PRACTICE REFERENCES AND RELATED DOCUMENTS 12 TABLE OF CONTENTS ABBREVIATIONS iii 1.0 DEFINITIONS 1 2.0 PURPOSE AND SCOPE 3 3.0 GUIDELINES FOR PRACTICE 6 3.1 WHAT IS THE PURPOSE OF CHECKING 6 3.2 HOW MUCH CHECKING IS REQUIRED 6 3.2.1 Level of Checking

More information

INTEGRITY MANAGEMENT CONTINUOUS IMPROVEMENT. Foundation for an Effective Safety Culture

INTEGRITY MANAGEMENT CONTINUOUS IMPROVEMENT. Foundation for an Effective Safety Culture INTEGRITY MANAGEMENT CONTINUOUS IMPROVEMENT Foundation for an Effective Safety Culture June 2011 Foundation for an Effective Safety Culture describes the key elements of organizational culture and business

More information

DEVELOPMENT AND APPLICATION OF PROBABILISTIC SAFETY ASSESSMENT PSA IN DAYA BAY NUCLEAR POWER STATION

DEVELOPMENT AND APPLICATION OF PROBABILISTIC SAFETY ASSESSMENT PSA IN DAYA BAY NUCLEAR POWER STATION 18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18) Beijing, China, August 7-12, 2005 SMiRT18-A01-2 DEVELOPMENT AND APPLICATION OF PROBABILISTIC SAFETY ASSESSMENT PSA

More information

Independent Verification and Validation (IV&V)

Independent Verification and Validation (IV&V) Independent Verification and Validation (IV&V) 12 th Annual NDIA CMMI Conference November 2012 - Denver, CO The MITRE Corporation The author s affiliation with The MITRE Corporation is provided for identification

More information

XII. Lessons Learned From the Accident Thus Far

XII. 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 information

OPG Proprietary Report

OPG 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 information

European Council Stress Tests for UK nuclear power plants

European Council Stress Tests for UK nuclear power plants European Council Stress Tests for UK nuclear power plants National Final Report December 2011 National Final Report on European Council Stress Tests for UK Nuclear Power Plants Crown copyright 2011 First

More information

FOLLOW-UP TO THE FRENCH NUCLEAR POWER PLANT STRESS TESTS UPDATE OF THE ACTION PLAN OF THE FRENCH NUCLEAR SAFETY AUTHORITY (ASN) DECEMBER 2017

FOLLOW-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 information

ANTICIPATED 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 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 information

Top 10 Signs You're Ready (or Not)

Top 10 Signs You're Ready (or Not) Top 10 Signs You're Ready (or Not) For an Appraisal Gary Natwick Harris Corporation Gary Natwick - 1 Government Communications Systems Division DoD s Strategic and Business Development CMMI Technology

More information

WORK PLAN AND IV&V METHODOLOGY Information Technology - Independent Verification and Validation RFP No IVV-B

WORK PLAN AND IV&V METHODOLOGY Information Technology - Independent Verification and Validation RFP No IVV-B 1. Work Plan & IV&V Methodology 1.1 Compass Solutions IV&V Approach The Compass Solutions Independent Verification and Validation approach is based on the Enterprise Performance Life Cycle (EPLC) framework

More information

Generic Guidelines for the Preparation of an Environmental Impact Statement. pursuant to the Canadian Environmental Assessment Act, 2012

Generic Guidelines for the Preparation of an Environmental Impact Statement. pursuant to the Canadian Environmental Assessment Act, 2012 Generic Guidelines for the Preparation of an Environmental Impact Statement pursuant to the Canadian Environmental Assessment Act, 2012 May 2016 Canadian Nuclear Safety Commission (CNSC) 2016 PWGSC catalogue

More information

Digital Industries Apprenticeship: Occupational Brief. Software Tester. March 2016

Digital Industries Apprenticeship: Occupational Brief. Software Tester. March 2016 Digital Industries Apprenticeship: Occupational Brief Software Tester March 2016 1 Digital Industries Apprenticeships: Occupational Brief Level 4 Software Tester Apprenticeship Minimum Standards and Grading

More information

CMMI FOR SERVICES, THE PREFERRED CONSTELLATION WITHIN THE SOFTWARE TESTING FUNCTION OF A SOFTWARE ENGINEERING ORGANIZATION

CMMI FOR SERVICES, THE PREFERRED CONSTELLATION WITHIN THE SOFTWARE TESTING FUNCTION OF A SOFTWARE ENGINEERING ORGANIZATION CMMI FOR SERVICES, THE PREFERRED CONSTELLATION WITHIN THE SOFTWARE TESTING FUNCTION OF A SOFTWARE ENGINEERING ORGANIZATION NAME: Nestor K. Ovalle, PhD TITLE: Leadership & Corporate Change Consultant; CMMI

More information

Applying Systems Engineering to ITS Projects: Advancing Beyond Federal Rule 940. INCOSE IW Transportation Working Group January 27, 2015

Applying Systems Engineering to ITS Projects: Advancing Beyond Federal Rule 940. INCOSE IW Transportation Working Group January 27, 2015 Applying Systems Engineering to ITS Projects: Advancing Beyond Federal Rule 940 William Gleckler Deputy Systems Engineering Officer, NYCT Capital Program Management Vincent Cavataio, CCM Deputy Systems

More information

Audit and Advisory Services Integrity, Innovation and Quality

Audit and Advisory Services Integrity, Innovation and Quality Audit and Advisory Services Integrity, Innovation and Quality Follow-up Progress Assessment of the Audit of IM/IT Project Life Cycle Controls 1577-13/14-101 Table of Contents EXECUTIVE SUMMARY 1 1. Introduction

More information

Reactor Technology: Materials, Fuel and Safety. Dr. Tony Williams

Reactor 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 information

Lessons Learned from Fukushima Daiichi Nuclear Power Station Accident and Consequent Safety Improvements

Lessons 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 information

PALLAS A nuclear reactor

PALLAS 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

Research on software systems dependability at the OECD Halden Reactor Project

Research on software systems dependability at the OECD Halden Reactor Project Research on software systems dependability at the OECD Halden Reactor Project SIVERTSEN Terje 1, and ØWRE Fridtjov 2 1. Institute for Energy Technology, OECD Halden Reactor Project, Post Box 173, NO-1751

More information

Recent Approaches related to Safety Enhancement of Operating NPPs in Korea Tae Eun JIN KEPCO E&C

Recent 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 information

Session Nine: Functional Safety Gap Analysis and Filling the Gaps

Session Nine: Functional Safety Gap Analysis and Filling the Gaps Session Nine: Functional Safety Gap Analysis and Filling the Gaps Presenter Colin Easton ProSalus Limited Abstract Increasingly regulatory and competent authorities are looking to hazardous Installation

More information

Decommissioning of Nuclear Facilities: The Work Ahead and How to Succeed

Decommissioning of Nuclear Facilities: The Work Ahead and How to Succeed Decommissioning of Nuclear Facilities: The Work Ahead and How to Succeed William D. Magwood, IV Director General Nuclear Energy Agency International Workshop on Decommissioning of Nuclear Power Plants

More information

Developing Competencies for Nuclear Safe Operation. October 2015

Developing Competencies for Nuclear Safe Operation. October 2015 Developing Competencies for Nuclear Safe Operation October 2015 Content 1. Introduction to Tecnatom Group 2. Relevant Current Activities in Training 3. The Elements in Developing Competencies for Safe

More information

Reliability Programs for Nuclear Power Plants

Reliability Programs for Nuclear Power Plants REGULATORY STANDARD Reliability Programs for Nuclear Power Plants S 98 REV.1 July 2005 2005-30.ho TYPES OF REGULATORY DOCUMENTS The legal framework within which the Canadian Nuclear Safety Commission (CNSC)

More information

Monitoring of the EU Stress test improvement actions in neighbouring countries

Monitoring 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 information

Highlights of CMMI and SCAMPI 1.2 Changes

Highlights of CMMI and SCAMPI 1.2 Changes Highlights of CMMI and SCAMPI 1.2 Changes Presented By: Sandra Cepeda March 2007 Material adapted from CMMI Version 1.2 and Beyond by Mike Phillips, SEI and from Sampling Update to the CMMI Steering Group

More information

IAEA HONG-KONG IAEA APPROACH ON NUCLEAR POWER INTRODUCTION

IAEA HONG-KONG IAEA APPROACH ON NUCLEAR POWER INTRODUCTION HONG-KONG APPROACH ON NUCLEAR POWER INTRODUCTION February, 2014 International Atomic Energy Agency V. NKONG-NJOCK INTRODUCTION International Atomic Energy Agency WORLD CHALLENGES - NUCLEAR OPPORTUNITIES

More information

Plant-specific safety review (RSK-SÜ) of German nuclear power plants in the light of the events in Fukushima-1 (Japan)

Plant-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 information

IAEA SUPPORT OF GLOBAL DECOMMISSIONING ACTIVITIES

IAEA SUPPORT OF GLOBAL DECOMMISSIONING ACTIVITIES International Conference ECED 2015 Eastern and Central European Decommissioning, 23-25 June 2015, Trnava, Slovakia IAEA SUPPORT OF GLOBAL DECOMMISSIONING ACTIVITIES Ian Gordon Head of Waste Technology

More information

FOSH Forsmark Safety Enhancement Project Post-Fukushima actions at Forsmark NPP

FOSH 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 information

Isolation Condenser; water evaporation in the tank and steam into the air. Atmosphere (in Severe Accident Management, both P/S and M/S)

Isolation 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 information

16th International Conference on Harmonisation within Atmospheric Dispersion Modelling for Regulatory Purposes 8-11 September 2014, Varna, Bulgaria

16th International Conference on Harmonisation within Atmospheric Dispersion Modelling for Regulatory Purposes 8-11 September 2014, Varna, Bulgaria 16th International Conference on Harmonisation within Atmospheric Dispersion Modelling for Regulatory Purposes 8-11 September 2014, Varna, Bulgaria UPDATES ON COST ACTION ES1006. EVALUATION, IMPROVEMENT

More information

PART THREE: Work Plan and IV&V Methodology (RFP 5.3.3)

PART THREE: Work Plan and IV&V Methodology (RFP 5.3.3) PART THREE: Work Plan and IV&V Methodology (RFP 5.3.3) 3.1 IV&V Methodology and Work Plan 3.1.1 NTT DATA IV&V Framework We believe that successful IV&V is more than just verification that the processes

More information

IAEA-TECDOC Managing modernization of nuclear power plant instrumentation and control systems

IAEA-TECDOC Managing modernization of nuclear power plant instrumentation and control systems IAEA-TECDOC-1389 Managing modernization of nuclear power plant instrumentation and control systems February 2004 The originating Section of this publication in the IAEA was: Nuclear Power Engineering Section

More information