Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June 2006 1 LESSONS LEARNED FROM AGING MANAGEMENT ACTIVITIES.

Slides:



Advertisements
Similar presentations
Electrical Cable Aging: What does IAEA Recommend? Module 2 Dr. John H. Bickel Evergreen Safety & Reliability Technologies, LLC.
Advertisements

Preventing Equipment Failures
1 KRB-A (Grundremmingen, Germany). 2 Type:Boiling Water Reactor Power: 250 MW(e) Started in 1966, shut down in 1977 First commercial power reactor in.
Steam Generation – Operational Flexibility and Lifetime Extension Considerations Kevin Murray Senior Integrity Engineer Marsh Power Forum – Istanbul, October.
1 Component Design Basis Inspection (CDBI) Graydon Strong 6/17/14.
Summer Co-op Experience: OPG Aditi Garg. Darlington Nuclear G.S Located in Bowmanville, ON.
1 Heat Exchangers. Standards of Conduct in Training 2.
NRC PERSPECTIVE ON RELIEF AND SAFETY VALVES Charles G. Hammer Component Performance & Testing Branch Division of Component Integrity Office of Nuclear.
ERT 312 SAFETY & LOSS PREVENTION IN BIOPROCESS ACCIDENT INVESTIGATION Prepared by: Miss Hairul Nazirah Abdul Halim.
School for drafting regulations Nuclear Safety Decommissioning Vienna, 2-7 December 2012 Tea Bilic Zabric.
RIM ) - REWRITE OF SECTION XI, DIVISION II, USING RISK INFORMED METHODOLOGY - FRANK J. SCHAAF,JR, P.E. ASME CHAIRMAN, SWGRIM CONSULTANT, STERLING REFRIGERATION.
Regulatory Body MODIFIED Day 8 – Lecture 3.
1 Regulatory Challenges During and Following a Major Safety or Security Event Muhammad Iqbal Pakistan Nuclear Regulatory Authority Presentation at General.
Experimental Class 5 Steam Generator
TECHNICAL ASSOCIATION OF THE EUROPEAN NATURAL GAS INDUSTRY Development of a Eurogas-Marcogaz Methodology for Estimation of Methane Emissions Angelo Riva.
Fukushima Incident Preliminary Analysis, Consequences and Safety Status of Indian NPPs Part-1 Dr. S.K.Jain Chairman & Managing Director NPCIL & BHAVINI.
Regulatory Approach to the Lifetime Management of the Nuclear Power Plants in Korea June 30, 2004 Choi, Kyung Woo Korea Institute of Nuclear Safety International.
U.S. DOE Light Water Reactor Sustainability Program: Advanced Instrumentation & Controls and Human System Interfaces Research Pathway Bruce Hallbert, Idaho.
Maintenance Optimisation At Rovno NPP Robert Hudson.
Monitoring of Radiologically Contaminated Scrap Material in the Czech Republic Zuzana Pašková State Office for Nuclear Safety Prague, Czech Republic International.
License Renewal at Paks NPP Project Technical Tasks Project Technical Tasks Sándor RÁTKAI, LR project technical head, PAKS NPP Telephone: 75/508576, fax:
Risk-Informed In- Service Inspection (RI-ISI) Ching Guey.
Nuclear Research Institute Řež plc 1 DEVELOPMENT OF RELAP5-3D MODEL FOR VVER-440 REACTOR 2010 RELAP5 International User’s Seminar West Yellowstone, Montana.
IRSN STRATEGY TO ASSESS A NEW MAINTENANCE POLICY / Nesebar, Bulgaria Presented by Naoëlle MATAHRI, IRSN.
Opting for “Long Term Operations” Technical, economic and regulatory considerations MARC Conference June 8, 2010 Sean Bushart, EPRI Sr. Program Manager.
Technical Working Group on Nuclear Power Plant Instrumentation and Control Vienna, May 2009 NATIONAL REPORT ON NUCLEAR POWER PLANT INSTRUMENTATION AND.
TWG-NPPIC, May 2009, Vienna: UK status1 Current status of NPP I&C in the United Kingdom T P Smyth AMEC, Knutsford, Cheshire, UK 22 nd Meeting of the Technical.
School for drafting regulations Nuclear Safety Operation Vienna, 26 November -7 December 2012 Tea Bilic Zabric.
Managing deviations from the Design Target with the Safety Case IAEA GEOSAF II Plenary 2014.
J1879 Robustness Validation Hand Book A Joint SAE, ZVEI, JSAE, AEC Automotive Electronics Robustness Validation Plan The current qualification and verification.
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.5/1 Design Geoff Vaughan University of Central Lancashire,
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.
Regional Meeting on Applications of the Code of Conduct on Safety of Research Reactors Lisbon, Portugal, 2-6 November 2015 Diakov Oleksii, Institute for.
06/01/20161 Benny Hoff TÜV NORD Sweden AB AFS 2002:1 Use of pressure equipment.
IAEA International Atomic Energy Agency INTRODUCTION Module 2.
Risk-informed On-Line Maintenance at Cofrentes NPP IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA.
IAEA International Atomic Energy Agency AGEING MANAGEMENT ASSESSMENT Module 9 Session 9 Resource document: AMAT Guidelines, Reference document for Ageing.
1 Safety factors for periodic safety review for research reactors Group A: SF1 – SF4.
IAEA International Atomic Energy Agency AGEING MANAGEMENT METHODOLOGY Module 3.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Diablo Canyon NPP Probabilistic Risk Assessment Program Workshop Information.
I & C.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Overview of Risk Informed Inspection Workshop Information IAEA Workshop City,
IAEA International Atomic Energy Agency Technical Meeting on Regulatory Oversight of Human and Organizational Factors Vienna, Austria | December.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop Safety Assessment Process. Plant Modification.
Equipment Life Optimization Program (ELOP) Doug Hilleman February 10, 2011.
G. Sliter, EPRI N. Wilmshurst, EPRI J. Carey, EPRI F. Polaski, Exelon Corp. Nuclear Safety Symposium Seoul, Korea 1 April 2005 Status of License Renewal.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Diablo Canyon NPP Maintenance Rule Program Workshop Information IAEA Workshop.
ALARA IMPLEMENTATION AT UKRAINIAN NPPs T. Lisova, Nuclear Energy Department, Ministry of Fuel and Energy of Ukraine Y. Roshchyn, National Nuclear Energy.
By Annick Carnino (former Director of IAEA Division of Nuclear Installations Safety) PIME, February , 2012.
Process Safety Management Soft Skills Programme Nexus Alliance Ltd.
Reduction of the collective doses in Almaraz Nuclear Power Plant through source term reduction and the work load reduction.
Workshop on Risk informed decision making on nuclear power plant safety January 2011 SNRC, Kyiv, Ukraine Benefits and limitations of RIDM by Géza.
Use and Conduct of Safety Analysis IAEA Training Course on Safety Assessment of NPPs to Assist Decission Making Workshop Information IAEA Workshop Lecturer.
Contents Regulatory Position and Utilities’ Action
Version 1.0, May 2015 BASIC PROFESSIONAL TRAINING COURSE Module XII Plant renewals, modifications and upgrades, ageing Case Study This material was prepared.
REACTOR PRESSURE VESSEL
Status and Prospect of Korean Korea Electric Power Research Institute
International Topical Conferences on Nuclear Safety, IAEA, June 6-9, 2017, Vienna Workshop 2: An Introduction and Further Explanation on Design Extension.
Project General Data Beneficiary: Rosenergoatom
Mild Environment Qualification and Maintenance
BASIC PROFESSIONAL TRAINING COURSE Module XIV Surveillance Case Studies Version 1.0, May 2015 This material was prepared by the IAEA and co-funded.
Flooding Walkdown Guidance
Role of the TSO in Public Information/ Debate Openness, Transparency Technical support to regulatory body for the new NPP (OL3) project Keijo Valtonen.
Tutorial Irradiation Embrittlement and Life Management of RPVs
Session Name: Ageing Management
Regulatory Oversight of HOF in Finland
Session Name: Lessons Learned from Mega Projects
VICTOR HUGO SANCHEZ ESPINOZA and I. GÓMEZ-GARCÍA-TORAÑO
BASIC PROFESSIONAL TRAINING COURSE Module XII Plant renewals, modifications and upgrades, ageing Case Study Version 1.0, May 2015 This material.
Presentation transcript:

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June LESSONS LEARNED FROM AGING MANAGEMENT ACTIVITIES MODERNISATION OF THE WWER 440 UNITS CONSIDERING ASPECTS OF THE LTO J.ZDAREK, P.KADECKA

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June SUMMARY Existing NPPs are secure source of energy. Their Long Term Operation is strategic goal for any utility. The US License Renewal process is closely followed by the IAEA activity and WWER operating countries. Recent lessons learned from several Aging Management Programmes (US, IAEA, WWER) will be summarized.

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June INTEGRATED PLANT REVIEW Systems, components, and structures within the scope of 10CFR54 : Safety-Related Non-Safety Related that could prevent safety function Regulated Events – SBO, EQ, Fire, PTS, ATWS SCOPE Passive or Active? Periodically Replaced? Managed by existing activities? Aging Management Review Modify existing or add new programs Structures & Components not subject to Additional Aging Management Review Demonstration that the effects of aging are adequately managed ScopeScreenAging Mgmt. Review Passive Active No Yes No Yes

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June  RPV  RPV internals  pressurizer  main coolant pump  main coolant loop  auxiliary primary piping  containment  electrical containment penetration  large openings in the containment  nuclear civil engineering structures  cables  I&C 12 DETAILED AGING ANALYSIS

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June THE LTO DATABASE  Together 6000 SSCs divided to 60 LTO groups  It is not possible to provide assessment for all selected 6000 SSCs  Based on engineering judgement and operation experience 215 type groups defined  For the type groups detailed assessment and conclusions prepared

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June KEY RECOMMENDATIONS FROM THE NPP  For the type groups where replacement of the SSCs is standard practice without large cost is proposed to cancel them from the LTO database. About 25 out of 215 type groups.  In the assessment to account for existing changes of material, including all means to prevent different damage mechanisms e.g. corrosion

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June FIRST SET OF REQUIREMENTS FROM THE NPP  To assure enough spare parts or new components in case that regular replacement is possible  In all high damage exposed places to accomplish material replacement with higher damage resistance  On all components with higher degradation occurrence to increase maintenance and testing requirements

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June LIST OF PROGRAMMES WITH INPUT TO MODERNISATION  DB Collation  Equipment Qualification  PTS/WPS  P/T curves  Civil structures  SG monitoring  Sealing Programme  UT/EC Qualification  RI ISI  Cable monitoring

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June DB COLLATION  Detail knowledge of the DB Requirements and DB Parameters will assure correct modernization programme  The configuration management programme requires to have DB data  The License Renewal for the LTO also requires the DB Collation

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June EQ  Qualification status for about 2200 equipment per unit within EQ list is established  All equipment from the EQ list is classified in following categories Qualified Qualified if specified conditions are fulfilled Non qualified  Modernization Programme has to assure qualified categories within EQ list as principle requirement for the LTO

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June PRIMARY SIDE FAILURES DOMINATE PTS RISK We need PTS conclusion for WWER. Presented conclusion is for US PWRs.  Primary side failures dominate Low embrittlement: stuck open valves that later re-close Higher embrittlement: medium & large diameter pipe breaks  Secondary main steam line breaks stuck open valves of much smaller consequence, & only at extremely high embrittlement levels

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June P-T CURVES 2 types of p-T curves created for NPP Dukovany: 1)for constant temperature (serving for protection against low-temperature-over- pressurisation) 2)for step cool down (serving for protection against PTS) Westinghouse methodology applied New set of p-T curves generated in 2005 for underclad cracks with depth 15 mm

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June CIVIL STRUCTURES Ageing management programme and monitoring shall be applied on the following components of NPP structures  soil – structure interaction  design, construction and performance of: basemat vertical concrete constructions (shrinkage, creep) ceilings roofs ways  operation mode of NPP  preventive and corrective maintenance  influence of components modernization

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June SG MONITORING On-line / periodical –Chemistry of feed water, blow down During shut down –HOR (Hide out return) + MULTEQ = pH in crevices Outage –NDT (Visual control, Eddy current.) –Analyses of removed deposits, withdrawn tubes Statistical evaluation of new damage indications Database of chemical regimes and tube damage Electrochemical Evaluation System + on-line information on crevice status ? + on-line solution sampling from crevice ?

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June SEALING PROGRAMME  complex approach to seal assessment MITesHT  serrated profile gaskets with pure-graphite facing MITesHT applications: main circulation pump, steam generator replace of nickel seals low level of stress for leakage rate class low torque verification of seal parameters great numbers of seal renovation

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June UT/EC QUALIFICATION  NDT Qualification focused on UT/ET qualification of equipment, inspection procedures (IP) and additional personnel qualification  UT/ET qualification has to be completed for majority of inspection areas in 2006 (incl. PHARE ISI 2002)  In all above aspects Qualified inspections of Safety Significant and Safety Related inspection areas required for extended inspection intervals as principle requirement for the LTO  Missing: additional personnel qualification (especially by blind tests) verification and evidence by computer modelling (CIVA simulations) for early completed UT/ET qualifications verification on realistic type defects for some qualifications

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June RI ISI  Current Status: Verification of selected RI ISI approach / EPRI methodology for WWER type plants based on the following pilot studies: LP ECCS at Temelin NPP (ETE) Primary piping including pressuriser piping for Dukovany NPP Steam and feed water piping (as High Energy piping) at ETE  Participation in a worldwide benchmark of RI ISI methodologies and verification on at least 4 selected systems at Ringhals NPP in (RISMET)  Transition to commercial RI ISI applications after completion of RISMET project and in case of approval by SUJB as a requirement for the LTO  Verification of other risk/RI-ISI approaches: BER RI ISI, Streamlined RI ISI, RI Repair/Replacement

Nuclear Research Institute Rez plc. Division of Integrity and Technical Engineering BULATOM June CABLE MONITORING  Systematic cable ageing management programme is needed at all NPPs based on cable deposits, environmental monitoring, cable ageing monitoring and software system for cable life assessment.  Replacement of degraded cables.  Relocation of cables to avoid hot spots.  Modify environment to reduce severe conditions.