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IAEA Contributions on Ageing Management Activities

This document provides guidelines and recommendations for effectively managing ageing in nuclear power plants, ensuring the maintenance of required safety functions. It covers topics such as plant design, equipment qualification, safety analysis, maintenance procedures, human factors, emergency planning, and environmental impact.

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IAEA Contributions on Ageing Management Activities

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  1. IAEA Contributions on Ageing Management Activities April 11 2006 Scientific Secretary of TWG LM-NPP, Ki-Sig KANG, Division of Nuclear Power

  2. IAEA Safety Standards and Guidance Documents on Plant Life Management and AM Programme Safety of NPP Operation NS R-2 Safety of NPP Design NS R-1 Safety Requirement DS 382 under developing Safety Guide SG on AMP Safety Guide on PSR Safety Guide on MSI Safety Guide on Personal Qualification Tech. Guidelines Component Specific Guidelines (13) AMP Review guideline (1) Programmatic Guidelines (5) Human Ageing Guideline (10) Maintenance I&C (10) RPV and PLiM (8) NSNI NENP

  3. Term of License

  4. 1. Licensing Renewal Application (USA) : 39 units approved by NRC (Feb. 2006) 10 other applications under NRC review 27 other units have issued letters of intent 2. Periodic Safety Review Belgium, CZ, France, Japan, Switzerland Central European countries and Russia. 3. Combined PSR and LRA Spain, Hungary and Korea Expect the Synergy effects between PSR and LRA PLiM Approaches for Long Term Operation 75% approved or requested for LRA

  5. What are the final products to be submitted to Licensing Authority ? • Licence Renewal Rule (10CFR54), • Maintenance Rule (10CFR50.65), • Generic Ageing Lessons Learned (GALL) report (NUREG-1801), • Industry Guidelines • (NEI 95-10). No. of page : about 1800 ~ 2000 Review duration : 18~ 20 M

  6. Section 1 : Administration information • Section 2 : Structure and Component subject to AM review • Scoping and screening methodology • Plant level scoping results • Scoping and screening results: Mech. Struct. Elec. • Section 3 : Ageing management review results • Section 4 : Time-limited ageing analyses • RPV neutron embrittlement • Metal fatigue • EQ on elec. Equipment • Containment fatugue • Appendix A : Updated FASR • Existing AM activities • Enhanced AM activities • New AM activities • TLAA activities

  7. Plant Plant design Actual condition of SSCs Equipment Qualification Ageing Safety Analysis Deterministic Safety Analysis Probabilistic SafetyAnalysis Hazard Analysis Performance & Feedback experience Safety performance Use of experience from other NPP Management Organization and administration Procedures Human factor Emergency planning Environment Radiological impact and environment Global Assessment PSR Overall Process and Inputs Objective : The objective of the review is to determine whether ageing in a nuclear power plant is being effectively managed so that required safety functions are maintained, and whether an effective ageing management programme is in place for future plant operation. • Description : • Operation within operating guidelines with the aim of minimizing the rate of degradation; • Inspection and monitoring consistent with the applicable requirements with the aim of the timely detection and characterization of any degradation; • Assessment of the observed degradation in accordance with appropriate guidelines to assess integrity and functional capability; • Maintenance (repair or replacement of parts) to prevent or remedy unacceptable degradation. • Internal hazards: • fire (prevention, • detection, suppression) • Flooding • pipe whip • Missiles • steam release • Spray • toxic gas • explosion.

  8. List of MS of PSR implementation

  9. Combined Approach with LRA and PSR • Normal PSR • Physical condition • Safety assessment • Equipment qualification • Aging effect • Safety Performance • Use of operation experience & research results • O&M procedure • Organization & administration • Human factors • Emergency plan • Environmental effects • Additional Req. beyond design life • Time-limited aging analysis • Aging management program • Back-fitting rules • Newly assessed regulatory requirements at international level • Radiation environmental effects • Field inspection + Intensified PSR

  10. Long Term Operating Requirements (beyond design life) Part 2: Radiological Impact Evaluation Updated Radiological Impact Report Waste Management Plan Part 1: Ageing Management and Evaluation Scoping and Screening Aging Management Review (AMRs) Time Limited Ageing Analysis (TLAAs) Application for Long Term Operation • Part 3: New Regulation Analysis Cost benefit analysis for plant upgradings derived from new regulations analysis, proposed by CSN. Part 4: PSR OE Review OE Analysis to Rad. Impact Regulatory Changes Analysis Equipment Perfor. Eval. Design Mod. Analysis PSA Improvement and Safety Evaluation Programs Current Requirements to Renew Operating License (within design life) Process for renewal of operating permit beyond design life time in Spain

  11. Introduction Current Trend for PLiM General Approach to PLiM Issues of PLIM (Tec. Reg, Eco. ) Relation between Maintenance & PLiM Research requir. for PLiM Cons. and Recomms. Appendix: Summary of good practices Introduction PLiM Overview General Approach to PLiM Components Specific Technology consideration Pressure tube Large scale fuel channel replacement Feeders and conventional piping Steam Generator, etc. Conclusions & Recoms. PLiMGuideline for LWR PLiM Guidelines for LWR and HWR PLiM Processes and Practices for HWR PARTICIPATING COUNTRIES: Belgium, Bulgaria, Czech, Hungary, Japan, Germany, France, Korea, Russia, Slovakia, Spain, Switzerland, USA PARTICIPATING COUNTRIES: Argentina, Canada, India, Korea Pakistan, Romania

  12. CRP- RPV Structural Integrity since 1975 • CRP 5 : Surveillance Programme Results Application to Reactor Pressure Vessel Integrity Assessment (2003) • CRP 6 : Mechanism of Ni effect on radiation embrittlement of RPV materials (1999-2003) • CRP 7 : Evaluation of Radiation damage of RPV using IAEA DB on RPV materials (2001 - 2004) • CRP 8 : Master Curve Approach to monitor the Fracture Toughness of RPV in Npps (2004 – 2007) • CRP 9 : Review and Benchmark of calculation methods for structural integrity assessment of RPVs during PTS (2005 - 2007) • Over 100 organizations and institutes

  13. CRP– 5 Results & Achievements • Some reactors w/o surveillance specimen. • Direct measurement of fracture toughness using small surveillance specimen by use of Master Curve approach. • Guidelines for application of the Master Curve have been completed and published by TRS-429 in 2005 • The Master Curve descibes a distribution of toughness values around median curve. • Master Curve Weibull distribution can be used to determine probabilistic distribution of Prob. of failure (Pf) for applied Stress Intensity KIapp given material KIC.

  14. Guidelines for Prediction of Radiation Embrittlement of Operating WWER-440 RPVs, TECDOC – 1442, May 2005 • Collection of complete WWER-440 surveillance data • Analysis of radiation embrittlement data of WWER-440 RPV materials • Evaluation of predictive formulae depending on material chemical composition, neutron fluence and neutron flux, • Development of the guidelines including methodology for evaluation of surveillance data for prediction of radiation embrittlement of NPPs Comparison of all experimental data with the prediction by Fit-5

  15. Effects of Ni on Irradiation Embrittlement of RPV Steels (TECDOC – 1441, May 2005) • Determine the mechanism for and quantify the Nickel content on the deteriorating effect in radiation embrittlement of RPV steels of Ni-Cr-Mo-V or Mn-Ni-Cr-Mo types. • Clearly showing the significantly higher radiation sensitivity of the high nickel weld metal (1.7 wt%) compared with the lower nickel base metal (1.2 wt%). • Regardless of the increased sensitivity of the WWER-1000 high nickel weld metal (1.7 wt%), the transition temperature shift for the WWER-1000 RPV design fluence is still below the predicted curve from the Russian Guide. 11 institutes from 8 countries and the EU participated / Irradiation at 6 institutes

  16. WORKING MATERIAL Technical Meeting held in Daya Bay, Shenzhen City, China29 November- 02 December 2004 Technical Meeting on "Strategies and Tools for Predictive Maintenance Technical Meetings held from 2003 to 2005 • Organized Six Int. WS or Tech. Meetings; 6 CD-ROM Proceedings • Corrosion, Fatigue and other time and load dependent degradation mechanisms other than irradiation (Mar. 2003, UK, 53 experts) • Irradiation effects and mitigation in RPV & Internals ( May 2004, Russia, 60 Experts) • RPV Internals behaviour and Technology for Repair and Replacement in NPPs (Oct. 2004, Germany, 52 experts) • Strategies and tools for Predictive Maintenance( Oct. 2004, China, 61 experts) • Recent material degradation and related managerial issues on NPPs (Feb. 2005, Austria, 40 experts) • External Flooding Hazards at Nuclear Power Plant Sites (Aug. 2005, India, 81 experts) 347 experts participation

  17. Irradiation-Assisted Stress-Corrosion Cracking Stress-Corrosion Cracking Irradiation-Enhanced Stress Relaxation CASS Thermal Aging & Irradiation Embrittlement Irradiation Embrittlement Irradiation-Induced Void Swelling IASCC SCC SR CASS TA/IE IE VS Use Data, Generic Analyses, and Models to Screen and Select Most-Affected Internals Components Thermal Shield & Core Barrel Bolts Internals Components(Increased Strength & Loss of Ductility) Baffle-Former Plates and Bolts (High Fluence and Temp. Regions) Baffle-Bolts Welds Bolted Joints CASS Components (Synergistic Effect) Determine Critical Locations, Critical Crack Sizes, and Flaw Tolerance for Actual Stresses, Fluences, and Temperatures Workshop on RPV Internals behaviour and Technology for Repair and Replacement in NPPs • 6-8 October 2004 @ Erlangen, Germany • Presented papers : 25 • 52 specialists participating from 18 MSs & 2 International Organs Source : The U.S. NRC’s Research and Regulatory Perspectives on the Degradation of Reactor Internals Author : W.H. Cullen, Sr. Materials Engineer Aging Management of Reactor Internal components * CASS : Cast Austenitic Stainless Steel

  18. Recent material degradation and related managerial issues • 15 - 18 Febururay 2005, VIC • Presented papers : 34 • Participants : 40 specialists • Countries : 23 MSs & 1 Int. Org. • Main contents • Recent real incidents involving mat. & mana. Issues • Technical update and outstandingmaterial issues • Management system and outstanding managerial issues • Roles and responsibilities among parties involved & polices on reg. aspects.

  19. Mihama #3 NPP Pipe Rupture Opening Rust in stagnant water • Mihama #3 : there was the omission of the ruptured portion in the check list from the beginning and the omission had never been corrected until the accident took place. • 5 workers were killed and 6 were injured by scald

  20. 2006 - 2007 PLiM Programme Engineering Plant Life Management • Main components replacement • SG, Reactor Vessel Head, RPV Internal • Power Uprate and Side effects of PU • Ageing management of Cables and I&C equipments/electric penetration • Decommissioning Review Maintenance / ISI-NDE • Steam Generator Tube Examination • Methodology for risked informed ISI program of NPPs • Water chemistry, corrosion control for secondary side of WWER • Configuration Management using IT technology

  21. 2006 - 2007 PLiM Programme Research Material • Material Sciences of the Metallic Structures for IGSCC, IASCC • Synergy effect of Nickel and Manganese on radiation embrittlement of RPV materials (Material and machining provided by EC/ JRC) Continuation of CRP • Master Curve Approach to Monitor the Fracture Toughness of RPVs (2004 - 2007) • Review and Benchmark of calculation methods for structural integrity assessment of RPVs during PTS (2005- 2007)

  22. Main topics to be discussed in Conf. Approaches of Plant Life Management Operation, Inspection and Maintenance on PLiM I&C Modernization and Ageing management Managerial issues to apply the approach of PLiM Regulatory issues to apply the approach of PLiM Economics of PLiM Overview on Decommissioning as Part of PLiM 1st TCM : Apr. 6-8 2006 at Vienna 2nd TCM : China in 2007. First call for papers: June 10 2006 2nd Int. Conference on Plant Life Management • Date : 15-18 Oct. 2007 • Place : Shanghai, China • Invite all of you and ask travel grant for participation (only TC recipient MSs)

  23. Knowledge management : Structure & Major Contents • Nuclear Safety Standards and Guides • Relevant IAEA Safety Standards, INSAG • National Requirements, International Recommendations • Basic Knowledge and Guidance • Abbreviations and terminologies • Key basic reference documents • IAEA Guidance documents • Relevant Activities • IAEA AMAT missions • IAEA Meeting proceedings • Research and Development • IAEA CRP reports • Other national/ international reports • Education and Training • Standard training modules on Ageing Management & EQ • Past workshop/ seminar materials • Links to IAEA data-base and other sites A limited scope version is already available at the IAEA web page (SALTO page):http://www.ns.iaea.org/projects/salto/default.htm

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