BEPU and Safety Margins in Nuclear Reactor Safety

Slides:



Advertisements
Similar presentations
TM/WSP 5-9 Nov Group A3- National position - Stakeholders involvement - Legislative framework - Safeguards QUESTIONS / DIFFICULTIES 1. Difference.
Advertisements

Presented by: Muhammad Ayub Pakistan Nuclear Regulatory Authority Safety Enhancement at Nuclear Power Plants in Pakistan Prospects of Nuclear Energy in.
Dr Jim Briggs Masterliness Not got an MSc myself; BA DPhil; been teaching masters students for 18 years.
Continuous Value Enhancement Process
INSAG DEVELOPMENT OF A DOCUMENT ON HIGH LEVEL SAFETY RECOMMENDATIONS FOR NUCLEAR POWER Milestone Issues: Group C. Nuclear Safety. A. Alonso (INSAG Member)
Iterative development and The Unified process
IAEA International Atomic Energy Agency Regulations Part I: Role and Structure of Regulations Day 8 – Lecture 5(1)
Software Verification and Validation (V&V) By Roger U. Fujii Presented by Donovan Faustino.
Presented by Dorian S. Conger Conger-Elsea, Inc Riveredge Parkway, Suite 740 Atlanta, GA phone fax
Slide No. 1 IAEA Developed by NSNI Division, IAEA under the supervision of Mr. Marco Gasparini (PNRA supported in the development under TC-Project PAK/09/028)
CDU – School of Information Technology HIT241 Professional Practice… - Slide 1 IT Project Management ACS - Core Body of Knowledge In Australia in November.
GSI-191 Status and Lessons Learned Presented by: Donnie Harrison Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Presented at:
Quality Assurance Program National Enrichment Facility Warren Dorman September 19, National Energy and Environmental Conference.
Nuclear Research Institute Řež plc 1 DEVELOPMENT OF RELAP5-3D MODEL FOR VVER-440 REACTOR 2010 RELAP5 International User’s Seminar West Yellowstone, Montana.
LEGAL FRAMEWORK & REGULATORY SYSTEM f or introduction of NPP into Vietnam Le Chi Dung (VARANS, Vietnam) Vienna, December 2008.
VTT-STUK assessment method for safety evaluation of safety-critical computer based systems - application in BE-SECBS project.
EMI INFSO-RI SA2 - Quality Assurance Alberto Aimar (CERN) SA2 Leader EMI First EC Review 22 June 2011, Brussels.
08 October 2015 M. Ammar Mehdi Introduction to Human Resource Management & SSG-16 Actions 4 th Steering Committee on Competence of Human.
Energy Forum 2011, Changing the Energy Paradigm and Outlook for South-Eastern EU Energy Forum 2011 Nuclear Safety Regulation in Romania Recent Developments.
School for drafting regulations Nuclear Safety Operation Vienna, 26 November -7 December 2012 Tea Bilic Zabric.
Project Life Cycles.
Improving Nuclear Safety Through Operating Experience Feedback NEA/IAEA/WANO- Conference Cologne 29 – 31 May 2006 Human and Organisational Factors Including.
School for Drafting Regulations on Radiation Safety Vienna, November 2012 EU Requirements Jiří Veselý, SONS, Czech republic.
IAEA International Atomic Energy Agency. IAEA Outline Learning Objectives Introduction IRRS review of regulations and guides Relevant safety standards.
IAEA International Atomic Energy Agency Summary and Overview of TECDOC Russel Edge Decommissioning and Remediation Unit Division of Radiation,Transport.
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.5/1 Design Geoff Vaughan University of Central Lancashire,
17 October 2011A.-C. Lacoste – Conference Transport1 Safety, Security and Response a View of the IAEA Today André-Claude Lacoste President of the French.
Specific Safety Requirements on Safety Assessment and Safety Cases for Predisposal Management of Radioactive Waste – GSR Part 5.
IAEA International Atomic Energy Agency Methodology and Responsibilities for Periodic Safety Review for Research Reactors William Kennedy Research Reactor.
IAEA International Atomic Energy Agency IAEA Safety Standards for Research Reactors W. Kennedy Research Reactor Safety Section Division of Nuclear Installation.
International Atomic Energy Agency Irina Sanda Education and Training in the Area of Safety Assessment Irina Sanda Safety Assessment Section Division of.
International Atomic Energy Agency M. El-Shanawany IAEA Technical Support & Capacity Building Programme M. El-Shanawany Department of Nuclear Safety &
The FDES revision process: progress so far, state of the art, the way forward United Nations Statistics Division.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop Defence in Depth Safety Culture Lecturer.
1 Public Meeting with ASME to Discuss Pump Inservice Testing Issues NRC Headquarters OWFN Room 1F22 June 4, 2007.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop Safety Assessment Process. Plant Modification.
IAEA International Atomic Energy Agency Development of the Basis Document for Periodic Safety Review for Research Reactors William Kennedy Research Reactor.
By Annick Carnino (former Director of IAEA Division of Nuclear Installations Safety) PIME, February , 2012.
Use and Conduct of Safety Analysis IAEA Training Course on Safety Assessment of NPPs to Assist Decission Making Workshop Information IAEA Workshop Lecturer.
DEVELOPMENT AND MAINTENANCE OF THE TECHNICAL AND SCIENTIFIC KNOWLEDGE BASE NECESSARY FOR TSO.
“PREEV” PROJECT: REGULATORY PRACTICES ON AGEING AND LIFE EXTENSION (LTO) 3RD INTERNATIONAL CONFERENCE ON NPP LIFE MANAGEMENT SALT LAKE CITY (USA),
Status and Prospect of Korean Korea Electric Power Research Institute
Panel Discussion: Discussion on Trends in Multi-Physics Simulation
Prescriptive vs Performance-Based Regulatory Approaches
International Topical Conferences on Nuclear Safety, IAEA, June 6-9, 2017, Vienna Workshop 2: An Introduction and Further Explanation on Design Extension.
The Systems Engineering Context
THE ROLE OF TSOs IN THE NATIONAL SAFETY ORGANIZATION
Flooding Walkdown Guidance
Pressurized Water Reactor Owners Group
Dept. of Nuclear and Quantum Engineering
Diversity analysis for advanced reactor design
Introduction to Software Testing
Armenia Training and Tutoring Feedback
Communication and Consultation with Interested Parties by the RB
RCF Plenary Session 21 September 2018
IAEA General Conference Regulatory Cooperation Forum Regulatory Approach Prescriptive vs Performance Based David Senior Executive Director -
International Atomic Energy Agency - IAEA
Introducing ISTQB Agile Foundation Extending the ISTQB Program’s Support Further Presented by Rex Black, CTAL Copyright © 2014 ASTQB 1.
USNRC IRRS TRAINING Lecture18
VICTOR HUGO SANCHEZ ESPINOZA and I. GÓMEZ-GARCÍA-TORAÑO
Considerations on the Reference Plant Concept
Safety Management System Implementation
IAEA – Safety Demonstration of Advanced Water Cooled Nuclear Power Plants Session: Digital I&C Systems Topic: Defence in Depth & Diversity – Challenges.
Legal and Regulatory Framework for Nuclear Installations in IRAN
Education and Training in the Area of Safety Assessment Irina Sanda
TRTR Briefing September 2013
Pressurized Water Reactor Owners Group
IAEA Technical Support & Capacity Building Programme M. El-Shanawany
Status of the IAEA safety standards and Relation to the CRAFT project
A Canadian Perspective
Presentation transcript:

BEPU and Safety Margins in Nuclear Reactor Safety University of Pisa DESTEC-GRNSPG Nuclear Research Group in San Piero a Grado (Pisa) - Italy BEPU and Safety Margins in Nuclear Reactor Safety F. D’Auria, N. Debrecin, H. Glaeser Int. Conf. on Topical Issues in Nuclear Installation Safety: Safety Demonstration of Advanced Water Cooled Nuclear Power Plants IAEA Headquarters , Vienna 6-9 June, 2017

ACTIVITY EMBEDDED INTO A BROADER FRAMEWORK WHICH INCLUDES: PREFACE – 1 of 2 ACTIVITY EMBEDDED INTO A BROADER FRAMEWORK WHICH INCLUDES: ALARA (As-Low-As-Reasonably-Achievable) is an early principle. IA (Independent Assessment) is a requirement . IN ADDITION TO: BEPU (Best Estimate Plus Uncertainty) is a key approach [the term took its origin within the nuclear thermal-hydraulics and the Accident Analysis framework during the ‘90s]. SM (Safety Margin) is an established concept. 2/21 2

ISSUES CONNECTED WITH THE TERMS: PREFACE – 2 of 2 ISSUES CONNECTED WITH THE TERMS: ALARA: adopted for Radioprotection & disconnected from Deterministic Safety Analysis. BEPU: not commonly accepted. SM: (sometimes-somewhat) ambiguous & comprehensive and systematic definition missing. IA: pursued only in principle: this is a wish rather than an achievement. 3/21 3

FOR THE ACTIVITY (IN PROGRESS): To integrate ALARA, BEPU, SM and IA. OBJECTIVES FOR THE ACTIVITY (IN PROGRESS): To integrate ALARA, BEPU, SM and IA. FOR THE PRESENTATION: To provide snapshot insights - advancements. To emphasize advantages (of the integration). 4/21 4

LIST OF CONTENT A view for NRS (role of ALARA, BEPU, SM and IA) The BEPU features - Key elements of BEPU (V&V; Scaling; Unc.; Coupling; DB / Application) - ALARA BEPU - Expanding BEPU (or BEPU-FSAR) Enhancing the SM concept (E-SM) Issues with current IA Integrating ALARA, BEPU, E-SM and IA - The additional safety barrier 5/21 5

Making ‘concrete’ the role of ALARA A VIEW FOR NRS Region for IA Making ‘concrete’ the role of ALARA Role for BEPU SM / E-SM 6/21 6

NRC – Interim Acceptance Criteria THE BEPU FEATURES A HISTORIC OUTLINE 1970 NRC – Interim Acceptance Criteria NRC – Appendix K to 10 CFR 50.46 NRC – RG 1.157 1990 Angra-2 BE LB-LOCA NRC – RG 1.203 Atucha-2 BEPU Chapter 15 2010 7/21 2020 BEPU-FSAR 7

THE BEPU FEATURES – Accident Analysis SAFETY ANALYSIS / LICENSING – IAEA SSG-2, 2010 BEPU 8/21 8

THE BEPU FEATURES WHAT IS BEPU? 9/21 BEPU ≡ ALARA  The BEPU is a logical process which connects the understanding in NRS (and licensing) with nuclear TH.  The starting point for BEPU are the physical phenomena. This implies the DBA envelope.  BEPU implies the existence of qualified computational tools dealing with different disciplines, input decks or nodalizations and a method to evaluate the uncertainty.  BEPU needs the existence of qualified procedures for the application of the computational tools.  BEPU needs the existence of qualified code users and of maven capable of evaluating the acceptability of analysis.  BEPU needs the existence of ’legal’ acceptance criteria.  The application of BEPU implies the knowledge of the licensing process.  The structure of the FSAR must be adapted to BEPU including the design of the core, the experimental data drawn during the commissioning, the design of EOP, etc.  Any BEPU report should be a living document. BEPU ≡ ALARA 9/21 9

CONSTITUTIVE ELEMENTS THE BEPU FEATURES WHAT IS BEPU? CONSTITUTIVE ELEMENTS V & V; UNC; COUPLING; DB; SCALING 10/21 10

KEY ELEMENTS OF BEPU V & V 11/21 DRAFT-IAEA V&V – 2017 VERIFICATION ESTABLISHED QA PRACTICE VALIDATION: STARTING FROM SETF & ITF CCVM + FFTBM FOR ACCURACY QUANTIFICATION RECENT CONCEPTS: ASSESSMENT OF VALIDATION (MINIMUM) INDEPENDENT ASSESSMENT FOR CODE USER 11/21 11

HIERARCHY & KNOWLEDGE MANAGEMENT ‘BRIDGES’ & ACHIEVEMENTS KEY ELEMENTS OF BEPU SCALING HIERARCHY & KNOWLEDGE MANAGEMENT ‘BRIDGES’ & ACHIEVEMENTS OECD/NEA/CSNI S-SOAR – 2017 11/21 12/21 12

KEY ELEMENTS OF BEPU UNCERTAINTY IAEA SRS-52 – 2008 13/21 13

KEY ELEMENTS OF BEPU CODE COUPLING EC-NEA CRISSUE-S – 2004 14/21 14

(TH) DATABASE / APPLICATION ARN (REGULATORY BODY) - APPROVED 2012 KEY ELEMENTS OF BEPU (TH) DATABASE / APPLICATION NA-SA / UNIPI ARN (REGULATORY BODY) - APPROVED 2012 5/21 15/21 15

ENHANCING THE SM CONCEPT E-SM CONTRIBUTED BY BEPU-FSAR A ‘FEW’ 10E4 E-SM DEFINITIONS 16/21 16

ENHANCING THE SM CONCEPT E-SM CONTRIBUTED BY BEPU-FSAR 17/21 17

ISSUES WITH CURRENT IA ISSUES NPP COMPLEXITY (efforts needed for IA ‘too large’ out of industry) SAFETY DEPENDING UPON DETAILS (details un-known out of industry; issue is proprietary information) INDUSTRY ENGAGED IN CONTINUOUS CHANGES / IMPROVEMENTS (changes not necessarily qualified, e.g. passive systems) IA ONLY POSSIBLE WITH LATEST BE TECHNIQUES (expertise may not be available out of industry) EXPERT ANALYSTS NOT NECESSARILY AWARE OF LICENSING DETAILS (the licensing framework is complex, too) 23/21 18/21 18

Integrating ALARA, BEPU, SM and IA ADDITIONAL SAFETY BARRIER NPP UNIT ALARA NRS REQUIREMENTS BEPU [BEPU-FSAR] SM [E-SM] ASSESSMENT INDEPENDENT LEGEND Philosophy Software Hardware Writing FSAR ADDITIONAL SAFETY BARRIER 19/21 19

Integrating ALARA, BEPU, SM and IA THE ADDITIONAL SAFETY BARRIER The Emergency Rescue Team (ERT) (not discussed here) and The BEPU-based Independent FSAR (BEPU & IA) coupled with The Safety Margins Detection & Control (E-SM) INTRODUCE A NEW SAFETY BARRIER WHICH MAY HELP TO RE-ESTABLISH THE PUBLIC TRUST TOWARDS NUCLEAR ENERGY 20/21 20

CONCLUSIONS ALARA at the origin of BEPU. BEPU based on V&V, Scaling, Code Coupling, Uncertainty, and Database. BEPU extended to the entire FSAR (analytical parts). E-SM (comprehensive and systematic set) derivable with support from BEPU. IA based on BEPU. SUMMARY BEPU: must be pursued. Any further delay is not justifiable for NRS. Safety Assessment (Licensing) must be independent of Vendor-Owner  BEPU-based I-FSAR & E-SM. 21/21 21