IAEA Contributions on Ageing Management Activities

April 11 2006April 11 2006

Scientific Secretary of TWG LM-NPP, Scientific Secretary of TWG LM-NPP, Ki-Sig KANG, Ki-Sig KANG,

Division of Nuclear PowerDivision of Nuclear Power

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IAEA Safety Standards and Guidance Documents on Plant Life Management and AM Programme

ProgrammaticGuidelines (5)

ComponentSpecificGuidelines (13)

AMP Review guideline (1)

DS 382 under developing

SG on AMP

Safety Guideon PSR

Safety of NPP Design NS R-1

Safety of NPP Operation NS R-2

Maintenance I&C (10)

RPV and PLiM (8)

Safety Guideon MSI

Safety Guideon Personal Qualification

Human Ageing Guideline (10)

NENPNSNI

Safety Requirement

Safety Guide

Tech. Guidelines

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Term of License

Limited Term Unlimited Term

Canada ( 3 - 5 years) Belgium ( 10 years)

Hungary ( 30 years) France ( 10 years)

Finland ( 10- 20 years) Germany( 10 years)

The Republic of Korea ( 30, 40 years)

Japan( 10 years)

United States ( 40 years) Sweden( 8 - 10 years)

United Kingdom ( 10 years) India ( 9 years)

Argentina ( 30 years) Spain (10 years)

Switzerland ( 10 years)

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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

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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

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• 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

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PSR Overall Process and Inputs

Plant1. Plant design2. Actual condition of SSCs3. Equipment Qualification4. Ageing

Safety Analysis5. Deterministic Safety Analysis6. Probabilistic Safety Analysis7. Hazard Analysis

Performance & Feedback experience8. Safety performance9. Use of experience from other NPP

Management10.Organization and administration11.Procedures12.Human factor13.Emergency planning

Environment14.Radiological impact and environment

Global Assessment

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.

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List of MS of PSR implementation

Status of PSR Implementation

Member States (MS)

PSRs have been completed in MS

Belgium, China (Qinshan NPP), Czech Republic, Finland, France, Germany, India, Japan, Republic of Korea, Netherlands, South Africa, Spain, Sweden, Switzerland and the United Kingdom, Slovenia (Krsko NPP), and Slovak Republic.

Other countries are either planning to use or considering using PSR within their regulatory systems

Brazil, Bulgaria, , Pakistan, Romania, and Ukraine

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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

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Process for renewal of operating permit beyond design life time in Spain

Part 1: Ageing Management and EvaluationScoping and Screening Aging Management Review (AMRs)Time Limited Ageing Analysis (TLAAs)

Part 4: PSROE ReviewOE Analysis to Rad. ImpactRegulatory Changes AnalysisEquipment Perfor. Eval.Design Mod. AnalysisPSA Improvement and Safety Evaluation Programs

Part 2: Radiological Impact Evaluation

Updated Radiological Impact ReportWaste Management Plan

Part 3: New Regulation AnalysisCost benefit analysis for plant upgradings derived from new regulations analysis, proposed by CSN.

Current Requirements to Renew Operating License (within design life)

Long Term Operating Requirements(beyond design life)

Long Term Operating Requirements(beyond design life)

Applicationfor Long Term

Operation

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PLiM Guideline for LWR

1. Introduction2. Current Trend for PLiM 3. General Approach to PLiM 4. Issues of PLIM (Tec. Reg,

Eco. )5. Relation between

Maintenance & PLiM 6. Research requir. for PLiM 7. Cons. and Recomms.

Appendix: • Summary of good practices

PARTICIPATING COUNTRIES:Belgium, Bulgaria, Czech, Hungary, Japan, Germany, France, Korea, Russia, Slovakia, Spain, Switzerland, USA

1. Introduction2. PLiM Overview 3. General Approach to PLiM4. Components Specific

Technology consideration• Pressure tube• Large scale fuel channel

replacement• Feeders and conventional piping• Steam Generator, etc.

5. Conclusions & Recoms.

PARTICIPATING COUNTRIES: Argentina, Canada, India, KoreaPakistan, Romania

PLiM Processes and Practices for HWR

PLiM Guidelines for LWR and HWR

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• CRP 8 : Master Curve Approach to monitor the Fracture Toughness of RPV in Npps (2004 – 2007)

• 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)

• CRP 9 : Review and Benchmark of calculation methods for structural integrity assessment of RPVs during PTS (2005 - 2007)

• CRP 5 : Surveillance Programme Results Application to Reactor Pressure Vessel Integrity Assessment (2003)

• CRP 5 : Surveillance Programme Results Application to Reactor Pressure Vessel Integrity Assessment (2003)

CRP- RPV Structural Integrity since 1975

• CRP 6 : Mechanism of Ni effect on radiation embrittlement of RPV materials (1999-2003)

• 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 7 : Evaluation of Radiation damage of RPV using IAEA DB on RPV materials (2001 - 2004)

• Over 100 organizations and institutes

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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.

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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

0 20 40 60 80 100 120 140 160 180 200 2200

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High flux Low flux

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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

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• 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)

Technical Meetings held from 2003 to 2005

WORKING MATERIAL

Technical Meeting held in Daya Bay, Shenzhen City,

China 29 November- 02 December 2004

Technical Meeting on "Strategies and Tools for

Predictive Maintenance

347 experts participation

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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

Irradiation-Assisted Stress-Corrosion

Cracking

Stress-Corrosion Cracking

Irradiation-Enhanced Stress

Relaxation

CASS Thermal Aging & Irradiation

Embrittlement

Irradiation Embrittlement

Irradiation-Induced Void Swelling

Baffle-BoltsWelds

Thermal Shield & Core Barrel

Bolts

Bolted Joints

CASS Components

(Synergistic Effect)

Internals Components

(Increased Strength & Loss of Ductility)

Baffle-Former Plates and Bolts (High Fluence and

Temp. Regions)

IASCC SCC SR CASS TA/IE IE VS

Use Data, Generic Analyses, and Models to Screen and Select Most-Affected Internals Components

Determine Critical Locations, Critical Crack Sizes, and Flaw Tolerance for Actual Stresses, Fluences, and Temperatures

Aging Management of Reactor Internal components

* CASS : Cast Austenitic Stainless Steel

Source : The U.S. NRC’s Research and Regulatory Perspectives on the Degradation of Reactor InternalsAuthor : W.H. Cullen, Sr. Materials Engineer

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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 outstanding

material issues • Management system and

outstanding managerial issues • Roles and responsibilities among

parties involved & polices on reg. aspects.

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Rust in stagnant water

Mihama #3 NPP Pipe Rupture Opening

• 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

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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

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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)

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2nd Int. Conference on Plant Life Management

• 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

• Date : 15-18 Oct. 2007

• Place : Shanghai, China• Invite all of you and ask travel grant for

participation (only TC recipient MSs)

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Knowledge management : Structure & Major Contents

1. Nuclear Safety Standards and Guides• Relevant IAEA Safety Standards, INSAG• National Requirements, International

Recommendations

2. Basic Knowledge and Guidance• Abbreviations and terminologies• Key basic reference documents• IAEA Guidance documents

3. Relevant Activities• IAEA AMAT missions• IAEA Meeting proceedings

4. Research and Development• IAEA CRP reports• Other national/ international reports

5. Education and Training• Standard training modules on Ageing

Management & EQ• Past workshop/ seminar materials

6. 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