ageing management and safe long term operation of ... management and safe long term operation of...

Ageing Management and Ageing Management and Safe Long Term OperationSafe Long Term Operation

of Japanese Light Water Reactorsof Japanese Light Water Reactors–– Securing the Stability of Ageing Nuclear Power Plants Securing the Stability of Ageing Nuclear Power Plants ––

Naoto Sekimura, Prof., Dr. Department of Quantum Engineering and Systems Science

Department of Nuclear Engineering and ManagementThe University of Tokyo

IAEA IAEA PLiMPLiM 2007 Symposium 2007 Symposium Shanghai, China, October 15Shanghai, China, October 15--18, 200718, 2007

ContentsContents・・・・ General Background of LWR Ageing in Japan・・・・ Regulatory Systems for Ageing Management

・・・・ Improved Ageing Management after Mihama-3 Accident・・・・ Ageing Management Technical Evaluation and Regulatory Documents and Guidelines

・・・・ New Inspection System・・・・ Strategy Maps for Ageing Management

・・・・ Technical Information Basis for Ageing Management・・・・ Research Activities and Good Practices

・・・・ International Collaboration・・・・ ( Impact of Earthquake to Kashiwazaki-Kariwa Plants )・・・・ Summary

2

Nuclear Power Plants in Japan : 55 unitsNuclear Power Plants in Japan : 55 units

10年年年年30年年年年 20年年年年現在現在現在現在0

200

400

600

800

1000

1200

1400

1600

1965 1970 1975 1980 1985 1990 1995 2000 2005 2010Start of Operation

Electr

ical O

utput

(MW ））））

BWR : 32UnitsPWR : 23UnitsCGR, ATR

3

Regulatory Inspection, Periodic Safety ReviewRegulatory Inspection, Periodic Safety Reviewand Ageing Management Technical Evaluationand Ageing Management Technical Evaluation

Utility’s Periodic Safety Review (PSR) (every 10 Years)

10 Years 10 Years10 Years10 Years10 Years

Utility’s Ageing Management Technical Evaluationfor Long-Term Operation before 30 years of Operation

30 Years

Revaluation Every 10 Years

10 Years 10 Years

Regulatory Inspection (every 13 Months)Start of Commercial Operation

4

Japanese Japanese Nuclear Nuclear

Regulatory Regulatory OrganizationsOrganizations

• NISA in METIestablished in Jan. 2001

• JNES established in Oct. 2003

• NSC

5

Committee on Ageing Management in Committee on Ageing Management in NISANISA

•• After the Mihama Unit 3 Accident on August 8, After the Mihama Unit 3 Accident on August 8, 2004,2004, a Committee on Ageing Management was established in NISA.– The Committee reviewed and discussed the basic policy, guidance documents, and the technical base for ageing management.

• Nuclear Power Plant Ageing Management Office (AMO) was established in NISA.

• Nuclear Power Plant Ageing Evaluation Office was established in JNES.

6

New Offices on Ageing Management in New Offices on Ageing Management in NISA and JNES from December, 2004NISA and JNES from December, 2004

• Nuclear Power Plant Ageing Management Office in NISA;– Compilation of Regulatory Guidelines for Ageing Management– Review of utility's Ageing Management Technical Evaluation– Selection of Safety-related Research & Development, reflecting

the Strategy Maps for Ageing Management

• Nuclear Power Plant Ageing Evaluation Office in JNES;– Preparation of Standard Manuals and Procedures for Ageing

Management Technical Evaluation– Technical Evaluation of utility‘s Ageing Management report– Preparation and Consolidation of Principal Database for AM – Implementation of safety-related Research & Development

7

Report on Improved Ageing Management Report on Improved Ageing Management of NISA approved on August 31, 2005of NISA approved on August 31, 2005�The following issues can be considered necessary to improve ageing management.(1) To assure transparency and effectiveness(2) To provide a technical information basis (3) To prevent non-physical degradation (4) To offer clear accountability to the public

�Domestic and International Collaborative actions are encouraged to promote Ageing Management for Safe Long Term Operation.

8

Report on Improved Ageing Management Report on Improved Ageing Management of NISA approved on August 31, 2005of NISA approved on August 31, 2005�Needs for various types of safety researches are also emphasized.�“R&D Roadmaps for Ageing Management and Safe Long Term Operation” developed by the Atomic energy Society of Japan are the excellent references for these wide variety of safety research.�Industries, government and research organization including universities are required to collaborate and share their roles effectively.

9

Ageing Management Technical EvaluationAgeing Management Technical Evaluationon the 3on the 3rdrd and following PSRand following PSR

• Review on Operational Experiences and Ageing Phenomena in SSC

• Reflect Latest Database and Technological Knowledge

• Assumption of Service for 60 years• Prepare Long-Term Maintenance

Programs

10

Ageing Management Technical Evaluation by UtilitiesAgeing Management Technical Evaluation by Utilities1. Classification of SSCs and Ageing Phenomena

1.1 Categorizing, Classifying and Grouping of SSCs

1.2 Clarification of Ageing Phenomena

2. Technical Evaluation of Ageing Management2.1 Technical Evaluation of Integrity of SSCs�Evaluation by actual inspection and monitoring of data�Analyses and calculation on the assumption of long-term operation

2.2 Review of Current Maintenance Program (CMMP)Preservation review of CMMP adequacy against ageing degradation of SSCs on the assumption of long-term operation

3. Long-term Maintenance Program3.1 Confirmation of CMMP to be continued adequately3.2 Clarification of additional maintenance program to CMMP and

establishment of long-term maintenance program3.3 Clarification of Research and Development tasks

11

Regulatory Guidelines, Standard Review Plan Regulatory Guidelines, Standard Review Plan and Review Manuals for Ageing Management and Review Manuals for Ageing Management

and Technical Evaluationand Technical Evaluation

26 December 2005

Ageing Management Implementation Guideline for

Nuclear Power PlantsStandard Review Plan for Ageing

Management Technical Evaluation of

Nuclear Power Plants

Nuclear and Industrial Safety Agency (NISA)

Revised, October 2006

Neutron Irradiation Embrittlementof Reactor Pressure Vessel

Age-related Technical Evaluation Review Manual

Technical Document for Ageing Management Implementation of


Japan Nuclear Energy Safety Organization

(JNES)

Ageing Management Implementation Guideline

・Scope of the Guideline・Implementation, Reevaluation and Revision of the Ageing Management Technical Evaluation (AMTE)・Establishment, Reevaluation and Revision of Long-Term Maintenance Program (LTMP)・Verification Processes of AMTE and LTMP by the Regulatory Authority・Publication of the results of the Review by the Regulatory Authority and Other Matters ・Application of this Guideline・Actions for Progress

Nuclear and Industrial Safety Agency (NISA)

26 December 2005

Standard Review Plan for Ageing Management Technical Evaluation・Purpose・Objectives・Detailed Review Procedures of AMTE •NISA: Review and Site Audit, Report to AMTE-WG•JNES: Report Detailed Review Results on the Technical Evaluation

・Points of View and Criteria for Reviews・Confirmations for Periodical Safety Review


• Neutron Irradiation Embrittlement or Reactor Pressure Vessel

• Stress Corrosion Cracking（（（（SCC））））• Fatigue• Thinning of Piping• Insulation Degradation of Electrical Cables

of Instruments and Control Facilities• Strength and Shielding Capability

Degradation of Concrete• Seismic Safety Evaluation• Viewpoint and Understanding of Approaches

to Prevention for Organization Culture Degradation


• Neutron Irradiation Embrittlement or Reactor Pressure Vessel

• Stress Corrosion Cracking（（（（SCC））））• Fatigue• Thinning of Piping• Insulation Degradation of Electrical Cables

of Instruments and Control Facilities• Strength and Shielding Capability

Degradation of Concrete• Seismic Safety Evaluation• Viewpoint and Understanding of Approaches

to Prevention for Organization Culture Degradation

12

26 December 2005

Nuclear and Industrial Safety Agency

(NISA)

Ageing Management Implementation Guideline for Nuclear Power Plants

Outline of Contents1. Historical Background2. Definition of Terminology3. Scope of the Guideline4. Implementation, Reevaluation and Revision

of the Ageing Management Technical Evaluation (AMTE)

5. Establishment, Reevaluation and Revision of Long-Term Maintenance Program (LTMP)

6. Report of Ageing Management Technical Evaluation (AMTE) Results and LTMP to the Regulatory Authority

7. Implementation of LTMP and Report of its Results

8. Evaluation relating to Ageing Management at the Periodical Safety Review

9. Verification Processes of AMTE and LTMP by the Regulatory Authority

10. Publication of the results of the Review by the Regulatory Authority and Other Matters

11. Application of this Guideline12. Actions for Progress

Original in Japanese

Ageing Management Implementation GuidelineAgeing Management Implementation Guidelinefor Nuclear Power Plants (NISA)for Nuclear Power Plants (NISA)

(December, 2005)(December, 2005) 13

26 December 2005

Standard Review Plan for Ageing Management Technical Evaluation

of Nuclear Power Plants

1. Purpose････Criteria and View-Points on Reviewing by NISA and JNES

2. Objectives･Framework and Organization for AMTE･AMTE Procedures

3. Detailed Review Procedures of AMTE •NISA: Review and Site Audit, Report to AMTE-WG

•JNES: Report Detailed Review Results on the Technical Evaluation

4. Points of View and Criteria for Reviews･Review of AMTE･Review of Long Term Maintenance Program (LTMO)

5. Confirmations for Periodical Safety Review

･Measures against Ageing Degradation Phenomena in Maintenance Program･Measures against Degradation of Organizational Safety Culture

Outline of Contents


Standard Review Plan forStandard Review Plan forAgeing Management Technical Evaluation (NISA)Ageing Management Technical Evaluation (NISA)

Nuclear and Industrial Safety Agency

(NISA)

(December, 2005)(December, 2005) 14

(2) Extract Class 1, 2 and 3 Components and Structures (CSs)

Select one CS

(6) Identify Materials used and Operating & Environmental Conditions on a Part to Part Basis (pressure, temperature flow conditions, operating conditions and structures )

(17) Evaluate Anti-Seismic Safety Considering Ageing Degradation

No Measure Needed

Yes

NoNo

Yes

No

No

Yes

No

Yes

NoYes

No

Yes

Completion

Yes

(7) Select one Part and Extract All Ageing Degradation Phenomena to be occurred or that could not be negated Possibilities absolutely.(8) Extract Evaluation Points for One Ageing Degradation Phenomena

(4) Divide into Composed Parts of CSs by Considering Necessity for Achievement of its Function

(12) Appropriate Current Base Maintenance

(1) Establish Implementation Framework for AM Technical Evaluation

(14) Evaluate All Ageing Degradation Phenomena

(15) Evaluate All Parts of CSs

(16) Evaluate All CSs

(10) Focused Ageing Degradation

(13) Establish a Long Term Maintenance Program Incorporated Additional Maintenance Program

Continue Current Base Maintenance

(19) Establish a Long Term Maintenance Program Incorporated Additional Maintenance Program

(3) Extract Consumables and Periodic Replacement Articles

Appropriate Maintenance Management

Out of Scope of Technical Evaluation

Out of Scope of Technical Evaluation

(5) Active Parts

Continue Current Base Maintenance

(9) Evaluate Occurrence and Progress of the Ageing Degradation Phenomena on Evaluation Points

(18) Appropriate Current Facilities

(11) Evaluate Integrity Assumed up to 60 Year Operation Period (Structural and Functional Integrity)

Yes

No

Standard Review Procedures of Ageing Management Technical EvaluaStandard Review Procedures of Ageing Management Technical Evaluationtion

15

JNES-SS-0507-01 Neutron Irradiation Embrittlementor Reactor Pressure Vessel

JNES-SS-0508-01 Stress Corrosion CrackingJNES-SS-0509-01 FatigueJNES-SS-0510-01 Thinning of PipingJNES-SS-0511-01 Insulation Degradation of Electrical

Cables of Instruments and Control Facilities

JNES-SS-0512-01 Strength and Shielding CapabilityDegradation of Concrete

JNES-SS-0513-01 Seismic Safety EvaluationJNES-SS-0514-00 Viewpoint and Understanding of

Approaches to Prevention for Organization Culture Degradation

Note: The title of the manuals mentioned on my presentations is tentatively named for providing information.

• Conduct Detailed Review of Age-Related Technical Evaluation

• Compile Results of ARTEs conducted previously for 9 Plants and Latest Technical Knowledge

• Including the Following Manuals;

December 2005 Japan Nuclear Energy Safety Organization

(JNES)

Neutron Irradiation Embrittlement of Reactor Pressure Vessel

Ageing Technical Evaluation Review Manual

Technical Document for Ageing Management of Nuclear Power Plants

December 2005 Japan Nuclear Energy Safety Organization

(JNES)


Ageing Technical Evaluation Review Manual

Technical Document for Ageing Management of Nuclear Power Plants

December 2005 December 2005





Technical Document for Ageing Management Implementation of


JNES - SS - 0570 - 01


Technical Evaluation Review Manuals for Ageing ManagementTechnical Evaluation Review Manuals for Ageing Management

Japan Nuclear Energy Safety Organization

(JNES)

(revised versions : October, 2006)(revised versions : October, 2006)

16

Major Degradation Phenomena of Materials in LWRMajor Degradation Phenomena of Materials in LWRfor Technical Evaluation of Ageing Managementfor Technical Evaluation of Ageing Management• Neutron Irradiation Embrittlement of Reactor Pressure Vessel• Stress Corrosion Cracking (SCC)

– IGSCC– PWSCC– IASCC

• Fatigue (including Environmental Fatigue)• Thinning of Piping

– Flow Accelerated Corrosion (FAC)– Liquid Droplet Impingement Erosion– Flashing Erosion– Cavitation Erosion

• Insulation Degradation of Electrical Cables of Instruments and Control Facilities• Strength and Shielding Capability Degradation of Concrete

17

1. Introduction2. Basic Guideline3. Review Process

3.1Technical Evaluation Review Process for Ageing Management3.2 Review of Long Term Maintenance Program

4. Reporting Items and Contents5. Confirmation Items in Periodical Safety ReviewAppendix 1:

Examples of Comparison of Surveillance Test Results and Embrittlemt Prediction FormulaAppendix 2:

Description of Typical Integrity Evaluation Process

Contents



Japan Nuclear Energy Safety Organization(JNES)


Technical Evaluation Review Manual for Ageing Management

Technical Document for Ageing Management Implementation of Nuclear

Power Plants

JNES - SS - 0570 - 01


Technical Evaluation Review Manuals Technical Evaluation Review Manuals Neutron Irradiation Neutron Irradiation EmbrittlementEmbrittlement of Reactor Pressure Vesselof Reactor Pressure Vessel

JNESJNES--SSSS--05070507--01 (revised in October, 2006)01 (revised in October, 2006)


18

Current Codes and Application of New Knowledge Current Codes and Application of New Knowledge in the Technical Evaluation Review Manualsin the Technical Evaluation Review Manuals

for Radiation for Radiation EmbrittlementEmbrittlement• JEAC 4201-2004

“Surveillance test method of structural materials for nuclear power reactors”

• JEAC 4206-2004“Verification test method of fracture toughness of components for nuclear power plants”

•• Introduction of Latest knowledgeIntroduction of Latest knowledge–– A new method based on A new method based on mechanistically guided mechanistically guided model developed by CRIEPI*model developed by CRIEPI* can also be used to can also be used to verify the prediction for possible variation of verify the prediction for possible variation of surveillance data.surveillance data.

19

1. Introduction2. Basic Guideline3. Review Process4. Reporting Items and Contents5. Confirmation Items in Periodical Safety

Review

Appendix 1: Results of Low Cycle Fatigue Evaluation during 60 Year Operation (for Nine Plants)

Appendix 2: Operating Years and the Number pf Occurrence of High Cycle Fatigue

Contents

December 2005


Fatigue

Age-related Technical Assessment Review Manual


Power Plants

JNES - SS - 0570 - 00


Technical Evaluation Review Manuals on FatigueTechnical Evaluation Review Manuals on FatigueJNESJNES--SSSS--05070507--01 (revised in October, 2006)01 (revised in October, 2006)

20

1. Introduction2. Basic Policy3. Seismic Safety Evaluation Process3.1 Selection of Components3.2 Arrangement of Safety Impotence3.3 Selection of Ageing Degradation Phenomena3.4 Seismic Safety Assessment for Every Age-related

Degradation Phenomena3.5 Evaluation of Active Function during Earthquake3.6 Application to All Components3.7 Selection of items to be incorporated into the

Maintenance Measures4. ReportingReference Documents(1) Trend of Codes relative to Seismic Design(2) Example of Seismic Safety Assessment Processes

for Every Age-related Degradation Phenomena(3) Examples of Modeling for each age-related

Degradation Phenomena and Allowable limits in Seismic Safety Assessment

(4) Evaluation Process of Seismic Safety Assessment on Pipe Thinning

Contents

October 2006


Seismic Safety EvaluationAge-related Technical Assessment Review Manual


Power Plants

JNES - SS - 0570 - 01

Original in Japanese,

Technical Evaluation Review Manuals on Technical Evaluation Review Manuals on Seismic Safety AssessmentSeismic Safety Assessment

JNESJNES--SSSS--05130513--01 (revised in October, 2006)01 (revised in October, 2006)

Revised in October 200621

Current Safety Regulation for Maintenance and Current Safety Regulation for Maintenance and Ageing ManagementAgeing Management

*1・・・Legal requirements*2・・・Guideline requirements

Maintenance Management

Policies and goals of maintenance management

Correction

Yes

No

Maintenance

Establishment of maintenance programs

Confirmation &assessment of inspections& repairs

Periodical assessmentof maintenance

Regu

lator

for N

uclea

r Safe

ty

� Long-term maintenance plan � Improvements

Inspection & repair

Establishment of the scope

Technological Assessment,

On-site inspections *2

Report *1

Technological Assessment,

On-site inspections *2

Report of the resultsafter each inspection *1

Confirmation through periodic inspections and

safety management assessment *1

Report *1

After 30 years in operationImplementation of Long-

Term Maintenance Programs as Periodic Inspection by

Utilites*2

Ageing Management Technical Evaluation

Assessment in 30th year and reassessment less than every 10

years thereafter

Periodic Safety Review (PSR)every 10 years

Establishment and Revision of Long-Term Maintenance

Programs *1

Ageing Management

22

New Safety Regulation for Maintenance Program and Ageing Management

Policies and goals of maintenance management

Establishment of the scope

Management of maintenance activities,setting of indicators, establishment ofmonitoring plans

Management of incompatibility,correction

Establishment of the importance

Maintenance Program

Validity assessmentof maintenance

Ageing ManagementContinued improvement of

maintenancemanagement

ImplementationCollecting maintenance data,checking, tests, inspections, repair,replacement, remodeling

(Revision) Application

（Revision）Application

Periodic Safety Review (PSR)every 10 years

Management of maintenance activities,monitoring of indicators

Establishment of plans

Validity assessment of maintenance management

Basic Items

Maintenance plan

Yes No

Regu

lator

for N

uclea

r Safe

ty

Confirmation & assessment

of inspections& repairs

Safety regulations based on the Nuclear Reactor Regulation Act

Confirmation of contentsand implementation

Notification

Safety regulations based on the Electric Utility Act

After 30 years in operationand thereafter

Implementation ofLong-Term Maintenance

Programs

Establishment of Long-Term Maintenance

Programs

Ageing Management Technical Evaluation

Assessment in 30th year and reassessment less than every

10 years thereafter

Synthetic Technical Information BasisSharing and utilization by industry, government and academia

Technical Information Basis for Ageing ManagementTechnical Information Basis for Ageing ManagementAgeing Management

�Ensuring the safety and reliability of NPPs� Implementation of effective safety regulations�Establishment of maintenance technologies �Formulation of evaluation standards and methods �Accumulation and utilization of knowledge and data

2. Research and Development①①①① Inspection and monitoring technologies②②②② Preventive maintenance, and repair

technologies③③③③ Evaluation technology for materials degradation

Reflection of necessity, importance, and urgency of R&DDevelopment of Technical Information Basis

1. Technical Information

①①①① Umbrella aging information ②②②② Plant operation experiences③③③③ Scientific information, etc.

Reflection of Investigation and R&D results

24

Technical Information Base

Comprehensive coordination

Industry � Technical development� Plant information, etc.

Academia

�Basic research �Scientific information, etc.

Government

� Safety research � Information on regulations, etc.

Umbrella NetworkInformation Exchange

Other Industries

International Projects

A Coordinating Committee on Ageing ManagementA Coordinating Committee on Ageing Managementwas established with members from industries, utilities, research organization and regulatory authorities.

25

Continuous Revision of Strategy MapsContinuous Revision of Strategy Maps forforAgeing Management by All the StakeholdersAgeing Management by All the Stakeholders

①①①①Introduction Scenario

②②②②Maps of Technical Issues

Strategy Maps for Ageing ManagementStrategy Maps for Ageing Management

Nuclear Safety Regulatory Standard Committee in NISA

Comments &Participation

Periodic Revision through Latest Knowledge

……

………

……

Publicity

• Needs• Targets• Milestones

• R&D projects• Information Basis• Hardware Resources• Human Resources

Safety Research Sub-Committee inthe Coordinating Committee on Ageing Management

Publication

2006 2006 --

③③③③Roadmaps

• Budgetary Actions forResearch and Infrastructure

• Regulation Systems withCodes and Standards

26

R&D Roadmaps for Ageing ManagementR&D Roadmaps for Ageing Managementand Safe Long Term Operationand Safe Long Term Operation

developed by Atomic Energy Society of Japan in 2004developed by Atomic Energy Society of Japan in 2004--20052005

Database onRegulationProceduresIn OtherCountries

To Keep Safety and Reliability of Nuclear Power PlantsTo Keep Safety and Reliability of Nuclear Power Plantsfor Long Term Operationfor Long Term Operation

EstablishmentEstablishmentof Informationof Information

BasisBasisTechnicalTechnical

DevelopmentDevelopment Codes andCodes andStandardsStandards

SystematicSystematicMaintenanceMaintenance

SystematicAgeing

ManagementProgram

Database forDegradation of

Materials

RPVRadiationEmbrittle-lment

EvaluationEvaluationTechnologyTechnology

for Degradationfor Degradationof Componentsof Components

PerformanceIndex

SchemesTo ApplyNew

Techniques

Standardization ofStandardization ofAgeing ManagementAgeing Management

ProceduresProcedures

HumanResources

Risk-basedMaintenance

Optimization ofOptimization ofMaintenanceMaintenance

IASCC

1.1. 2.2. 3.3. 4.4.

27

Major Roles of Industries, Government and Major Roles of Industries, Government and Academia for Ageing ManagementAcademia for Ageing Management

・・・・To develop, review strategy maps periodically and build a consensus with experts from industries, government and academia

by identifying important issues to be solvedby discussing roles of stakeholders for rational and efficient implementation of research

・・・・To develop and improve codes and standards based on safety research outcome

Academic Societies

• Responsibility to establish and improve safety regulations - by conducting safety researches, - by keeping infrastructure • Responsibility to promote nuclear energy for national energy security

Government

・Responsibility to contribute to safety research activities- to accumulate and expand fundamental knowledge- to keep human resources through the safety research

Academia

• Primary responsibility to keep safe operation of power plants- research and development, and development of the infrastructure for safety and public interests

Industries

28

10⑨

1714130908

T1

2F1 K4SK1

Tsu22F2０

O11F5

2

1F2⑦⑦⑦⑦

8

242322212019181615121110070605040302012000Year

O2K2TM11F42F41F3T4OG12F21F1Tsu1１F6１F4①①①①

1F3T21F2①①①①①①①①

Tsu1

I3K3M2GN2M1O1To2H3M32F3SD1M2②②②②②②②②

O2To2M3②②②②

T1②②②②

3

OG1④④④④④④④④④④④④

O2④④④④④④④④

SD21F2④④④④

5

SD1⑤⑤⑤⑤

GN1T16

9

GN3

2F2

SM1

O4

H4

I2

③③③③

TM2

1F1

K5

Tsu1

SM2

1F6

1F5

H2I1

H1

③③③③

T3

K1

T2

SM1

⑥⑥⑥⑥

I2

③③③③

GN2M1

③③③③

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GN1０

M21F1M1 I1H1SM11

③③③③③③③③

4

7

⑨⑨⑨⑨

29

Strategy Maps 2007 for Ageing Management Scenarios(1)

-- Ageing Management Technical Evaluation for Every 10 Years Ageing Management Technical Evaluation for Every 10 Years --•• Increase in number of plantsIncrease in number of plants•• From initial plants to standardized plantsFrom initial plants to standardized plants

First plant to exceed 40 years of operation

First plant to exceed 50 years of operation

Note: This figure is drawn assuming that all of the plants currently in service will continue their operation.

From METI’s Nuclear Energy Subcommittee “Japanese Nuclear Energy National Plan” August, 2006

From the survey by the Agency for Natural Resources and Energy of METI

A plant with operating experience

of 40 years and above appears.

30 % of Total Electricity

* These values are estimated based on the comparison of total generated electric energy with that of 2014 estimated on the assumption that the utilization rate of 75%.

LWR

Capa

city

[ten-t

hous

and k

W]

Year

The long-term operation of existing plants

Newly-built light water

reactors

Fast Breeder reactors

Year

Instal

led ca

pacit

y [ten

-thou

sand

kW]

–Ageing Management of Current LWR Plants and their Replacements –

Assuming 60 years of operation of current LWR

30

Strategy Maps 2007 for Ageing Management Scenarios (2)

4. Systematic MaintenanceSystematic Maintenance3. Establishment of Information Basis3. Establishment of Information Basis

2. Establishment of Codes and Standards2. Establishment of Codes and Standards1. Safety Research to Solve Ageing Issues1. Safety Research to Solve Ageing Issues

* Advanced designs will be developed based on past operating experience.

* Predication methods and monitoring technology will be upgraded.

* Countermeasures are being taken by rule of thumb based on plant data.

Irradiation embrittlement

* Simulation methods will be established. * ISI technology will be upgraded.

* Use of SCC-resistant materials will be ensured. * Database will be constructed.

* Countermeasures suited to materials in use are being taken. * Database is being constructed.

Stress corrosion crack

* Past records of performance will be reflected in the maintenance technology and durability designs for new plants. * Recycling methods will be established for replaced structures and materials.

The reliability of integrity evaluation methods will be improved or enhanced. CCV integrity evaluation methods will be established.

Intensive study is being made on scarcely known fields.

Decreased strength of concrete

* Monitoring technology will be upgraded.

Deterioration diagnosis technology will be upgraded.

* Countermeasures suited to materials in use are being taken. * Database is being constructed.

Deteriorated cable insulation

* Monitoring technology will be upgraded.

* Mechanism-based predication methods will be established. * Risk-based maintenance methods will be established.

* Countermeasures suited to materials in use are being taken, and database is being constructed. Wall thinning

* Countermeasures suited to materials in use or environment will be taken, and database will be constructed.

* Countermeasures suited to materials in use or environment will be taken, and database will be constructed.

* Countermeasures suited to materials in use or environment are being taken, and database is being constructed. Fatigue

Long-life, next-generation reactor 40th to 50th year Current StatusAging

phenomenon

Strategy Maps 2007 for Ageing Management Maps for Technical IssuesMaps for Technical Issues

31

Strategy Maps 2007 for Ageing Management Roadmaps for Stress Corrosion CrackingRoadmaps for Stress Corrosion Cracking

32

Aps

Phase I (until 40 year operation of early stage NPPs2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015～～～～2019 2020～～～～2029

Phase II (until 50 year operation) Phase III (until 60 year operation)Fiscal Year

Preparation and refinement of initiation data and crack growth data on IASCC

Preparation of infrastructure for IASCC research Preparation and refinement of initiation data and crack growth data on IASCC Confirmation of the data and evaluation technology, and preparation of regulatory criteria

Understanding of IASCC mechanism

Simulation technology of IASCC initiation and propagation

Establishment of code and standards, and regulatory criteria

IASCC initiation test methods

Refurbishment of laboratory facility including JMTR

Extended IASCC crack initiation data and its refinement

Extended IASCC crack growth data and its refinementCorrelation between laboratory data and field events

Obtaining of crack growth data for ex-plant materials In-core IASCC Initiation and growth evaluation

IASCC evaluation technology confirmation Understanding and modeling of IASCC crack

Study of accelerated irradiation validity

Understanding and modeling of IASCC crack initiation and growth mechanism

Development of simulation technology of IASCC initiation and growth

Study of IASCC mechanism at high fluence region

Establishment of CS for fitness-for-service

IASCC integrity evaluation guide

Establishment of CS for fitness-for-serviceCoding of IASCC initiation and growth simulationSCC long term integrity evaluation guide


1. Integrity Evaluation : IASCC1. Integrity Evaluation : IASCC2. Integrity Evaluation : IGSCC2. Integrity Evaluation : IGSCC3. Integrity Evaluation : 3. Integrity Evaluation : NiSCCNiSCC4. Inspection Technologies on SCC4. Inspection Technologies on SCC5. Monitoring Technologies on SCC5. Monitoring Technologies on SCC6. Repair & Replacement Technologies6. Repair & Replacement Technologies

Strategy Maps 2007 for Ageing ManagementRoadmap of Research and of Code Development for IASCCRoadmap of Research and of Code Development for IASCC

Phase I (until 40 year operation of early stage NPPs2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015～～～～2019 2020～～～～2029

Phase II (until 50 year operation) Phase III (until 60 year operation)Fiscal Year

Preparation and refinement of initiation data and crack growth data on IASCC

Preparation of infrastructure for IASCC research Preparation and refinement of initiation data and crack growth data on IASCC Confirmation of the data and evaluation technology, and preparation of regulatory criteria

Understanding of IASCC mechanism

Simulation technology of IASCC initiation and propagation


IASCC initiation test methods

Refurbishment of laboratory facility including JMTR

Extended IASCC crack initiation data and its refinement

Extended IASCC crack growth data and its refinementCorrelation between laboratory data and field events

Obtaining of crack growth data for ex-plant materials

In-core IASCC Initiation and growth evaluation

IASCC evaluation technology confirmation Understanding and modeling of IASCC crack

Study of accelerated irradiation validity

Understanding and modeling of IASCC crack initiation and growth mechanism

Development of simulation technology of IASCC initiation and growth

Study of IASCC mechanism at high fluence region

Establishment of CS for fitness-for-serviceIASCC integrity evaluation guide

Establishment of CS for fitness-for-service

Coding of IASCC initiation and growth simulationSCC long term integrity evaluation guide


33

Development of Development of Technical Information InfrastructureTechnical Information Infrastructure

Human Resources

Technical Information Infrastructure

Safety Research & Development

SystematicMaintenanceImprovement

Development of Codes and Standards

Selection of Research Theme

Research result

-Maintenance Information -Case Maintenance -Operating Experience

Latest Information

Tacit Knowledge Tools for Education

Latest Information

Technical Evaluation Result

34

Development of Development of Technological Technological Information Information InfrastructureInfrastructure

Establishment of Establishment of the information the information network securing network securing disinterested partydisinterested partyand responses to and responses to internationalizationinternationalization

●Information system of ageing

●International collaboration

Promotion of Promotion of Technology Technology DevelopmentDevelopment

Systematic technology Systematic technology development baseddevelopment basedon the roadmapon the roadmapfollowed by reviewfollowed by review

●Assessment and promotion of safety research and technology development

Systematic Systematic Maintenance Maintenance ImprovementImprovement

Development of Development of optimized optimized maintenance plan maintenance plan Education to keepEducation to keephuman resource human resource

●Improvement and education of integrated maintenance

Development of Development of Codes & StandardsCodes & Standards

●●Effective regulationEffective regulation

●●Improvement of Improvement of current standards and current standards and criteriacriteria

Dynamical Use Dynamical Use of Knowledgeof Knowledge

StructurizationStructurizationof Knowledgeof Knowledge

Realization of Realization of knowledgeknowledge

Social Environment and Business EnvironmentSocial Environment and Business EnvironmentSocial Environment and Business EnvironmentSocial Environment and Business EnvironmentSocial Environment and Business EnvironmentSocial Environment and Business EnvironmentSocial Environment and Business EnvironmentSocial Environment and Business Environment

Basic Structure of the Strategy MapsBasic Structure of the Strategy MapsAcademic Meaning of the Strategy Maps

35

Recent Progress of Research CoordinationRecent Progress of Research Coordinationand Saand Safety Research Projects in JapanResearch Projects in Japan

• A Coordinating Committee on Ageing Management was established with members from industries, utilities, research organization and regulatory authorities.

• Research Projects on Fundamentals of Ageing Management funded by NISA started from 2006 in 4 districts in Japan.• Organized R&D projects by Utilities have started.

36

PLM research promotion council board 【【【【Policies regarding research promotion】】】】

［［［［Secretariat: JANTI (FEPCO)］］］］

PLM research administrative review meeting

【【【【Discussing research strategies】】】】［［［［Secretariat: CRIEPI］］］］

10 Sub Group (SG): Examination team【【【【Individual Issues.】】】】

Providing future directionsEvaluation results

Industrial Efforts to Promote PLMIndustrial Efforts to Promote PLM--related R&D Activities *related R&D Activities *

＜＜＜＜Electric power companies, manufacturers and organizations that are involved in the support system＞＞＞＞

Nine electric power companies, JAPC, Electric Power Development CO., CRIEPI and JANTI

Technology information coordination committee

Collaboration

Collaboration

Nuclear energy development committee Comprehensive

task force

Nuclear energy development committee

Equipment maintenance committee

＜＜＜＜The Federation of Electric Power Companies of Japan＞＞＞＞

Chairman and deputy chairman of promotion council board participate in the committee.

37

* * KamadaKamada et al; this Symposiumet al; this Symposium

Research ProjectResearch Projecton Fundamentals of Ageing Managementon Fundamentals of Ageing Management

General Review Session on Ageing Management Infrastructure Improvement

Review Session on Ageing Management Database and Knowledge Base Review Session on Seismic Effects on Piping ThinningReview Session on Condition Monitoring and Safety Preservation Technology Review Session on Irradiation Embrittlement

Review Session on Cable Degradation

Review Session on Stress Corrosion Cracking

Tohoku ClusterICR

Fukui ClusterINSS

East Japan Cluster

MRI

Ibaraki ClusterJAEA

General Review Session WG

InformationExchange

ProgressReportAdvice

ProgressReportAdvice

TechnicalInformationCoordinationCommitteeSafety ResearchWGIn JNES

Outcome

NISA (Nuclear and Industrial Safety Agency) in METI

Academic Societies etc.

InformationExchange

38

OECD/NEA OECD/NEA SCAP ProjectSCAP Project **

• The main objectives of SCAP are to:– Establish a complete database with regard to major ageing phenomena for SCC and degradation of cable insulation through collective efforts by OECD/NEA members– Establish a knowledge-base by compiling and evaluating collected data and information systematically, with regard to major ageing phenomena for SCC and degradation of cable insulation– Perform an assessment of the data and identify the basis for commendable practices which would help regulators and operators to enhance ageing management

SCAP: Stress Corrosion Cracking and Cable Ageing Project

*Yamamoto et al; this Symposium 39

(Members)・Belgium・Canada・Czech Republic・Finland・France・Germany・Japan・Korea・Mexico・Norway・Slovak Republic・Spain・Sweden・U.S

Management Board

Cable WGSCC WG

(Observers) IAEA, EC

MB Chair Prof.Sekimura

(Japan)

SCC Chair Mrs. Gott (Sweden)

SCAP Consultant Mr. Shultz (Germany)

Cable Chair Mr. Koshy (U.S)

Clearing House

ERIN（U.S)

Clearing HouseOECD Halden

Reactor ProjectIFE(Norway)

Management of the SCAPManagement of the SCAP

Technical Secretariat 40

KashiwazakiKashiwazaki--KariwaKariwa Nuclear Power PlantsNuclear Power Plants

� 7 units, 8,212 MWe� Reactor type

Units 1-5: BWR Units 6, 7: ABWR

41

Layout of Layout of KashiwazakiKashiwazaki--KariwaKariwa sitesite

42

KashiwazakiKashiwazaki--KariwaKariwa Nuclear Power PlantsNuclear Power PlantsUnit Start ofOperation Type Output Main ContractorNo.1 1985/9/18 BWR-5 1,100MWe / 3,293MWt ToshibaNo.2 1990/9/2 BWR-5 1,100MWe / 3,293MWt ToshibaNo.3 1993/8/11 BWR-5 1,100MWe / 3,293MWt ToshibaNo.4 1994/8/11 BWR-5 1,100MWe / 3,293MWt HitachiNo.5 1990/4/10 BWR-5 1,100MWe / 3,293MWt HitachiNo.6 1996/11/7 ABWR 1,356MWe / 3,926MWt Toshiba/Hitachi/

GE

No.7 1997/7/2 ABWR 1,356MWe / 3,926MWt Toshiba/Hitachi/GE

Total 8,212MWe

43

ChuetsuChuetsu--Oki Earthquake on July 16,2007Oki Earthquake on July 16,2007• July 16, 2007 10:13AM JST (GMT+9) (National Holiday)• Magnitude on the Richter scale: 6.8• Distance from the Kashiwazaki-Kariwa Site

– Epicenter :16 km, Hypocenter : 23 km, (Depth: 17 km)

©Google ©ZENRIN

10km

30km

Epicenter

KK site

Sea of Japan

Pacific Ocean

Distribution of seismic intensity (JMA)44

�Road damage near K-5

Damage to the Roads Inside the SiteDamage to the Roads Inside the Site

�Road damage near Switch Yard

Operational Status of the UnitsOperational Status of the Unitson July 16,2007 on July 16,2007

Unit 1 Unit 2 Unit 3 Unit 4 Unit 5 Unit 6 Unit 7Status beforeearthquake Outage Startup

(subcritical)At FullPower

At FullPower Outage Outage At Full

Power

Automaticshutdown Yes Yes Yes Yes

Status afterearthquake

Coldshutdown

Coldshutdown

Coldshutdown

Coldshutdown

Coldshutdown

Coldshutdown

Coldshutdown

Off-sitepowerDieselgenerator

Good(Stand-by)

Good(Stand-by)

Good(Stand-by)

Good(Stand-by)

Good(Stand-by)

Good(Stand-by)

Good(Stand-by)

2 out of 4 lines were maintained during and after the quake

46

PostPost--Seismic Plant ConditionsSeismic Plant Conditions- Reactor Pressure Vessel Foundation Bolts -

Pedestal

Reactor pressure vessel

Skirt

Foundation bolt

� No damage was observed by visual check of the RPV foundation bolts

47

PostPost--Seismic Plant ConditionsSeismic Plant Conditions-- MSIV and PLR Pump MSIV and PLR Pump --

Main steam isolation valves (in primary containment vessel)

Recirculation pump (in primary containment vessel) 48

IAEA Expert MissionIAEA Expert Missionon August 6on August 6--10, 200710, 2007

• Review Team– JAMET, Philippe: IAEA/NSNI/Director, Team Leader – GODOY, Antonio R.: IAEA/NSNI/ESS, Deputy Team Leader– GUNSELL, Lars: SKI, Sweden– JOHNSON, James J.: James J. Johnson & Associates, USA– KOSTOV, Marin: Risk Engineering Ltd., Bulgaria

49

IAEA Mission Report IAEA Mission Report –– (1)(1)1. The trip of all the reactors which were at full power or increasing power was performed without problem and the installation behaved in a satisfactory manner during and after the earthquake.The three fundamental safety functions (reactivity control, removal of residual heat and confinement) were insured.

2. Although an extremely small amount of radioactive material was released, the resulting individual dose was estimated well below the authorized limits.

3. Although the safety related structures, systems and components of the plant suffered from the large earthquake, they seem to be in a much better general condition than expected. This is probablydue to the conservatisms taken into account at different stages of the design process.

4. In the re-evaluation complying with the September 2006 guidelines issued by NSC, the investigations are also to address the issue of the potential existence of active faults under the site.

5. The possibility should be considered that the systems and components remain functionally available under normal operating conditions but sustain hidden damage.

50

IAEA Mission Report IAEA Mission Report –– (2)(2)Specific issues indicated in the Report• Exceeding of the Design Basis Ground Motion by the Observed Earthquake

• Re-evaluation of the Seismic Hazard• Off-Site Power• Common-Cause Failure• Fire Safety• Seismic System Interaction• Soil Failures• Anchorage Failures• Operational Safety Management• Releases• Ageing

51

A New Advisory Committee in NISAA New Advisory Committee in NISA

(1) Operation and Management of the Plant Systems– Evaluation of measures for operation management

conducted by the licensee immediately after the earthquake disaster; extraction of problems; and demanding the licensee to reflect the problems in their manuals when needed.

(2) Examination of Integrity of SSCs– Examination of necessary inspection, and evaluation of

inspection plans and results by TEPCO– Examination of evaluation methodology for equipment

integrity, and criteria for necessary repair or replacement actions

– Examination of a method for maintenance and repair, based on the results of inspection and evaluation

– Extraction of items to be reflected in guidelines and criteria in the courses of individual examinations

- A Working Group for Reactor Management and Systems Integrity -

52

Summary (1)Summary (1)•• Current status of ageing management of Japanese Current status of ageing management of Japanese light water reactors is briefly stated.light water reactors is briefly stated.

•• Regulatory systems and documents for technical Regulatory systems and documents for technical evaluation procedures of safe long term operation evaluation procedures of safe long term operation have been continuously improved and uphave been continuously improved and up--dated.dated.

•• New regulatory inspection system will start next year, New regulatory inspection system will start next year, which can improve and strengthen maintenance and which can improve and strengthen maintenance and ageing management of Japanese light water reactors.ageing management of Japanese light water reactors.

•• Continuous revision of Strategy Maps forContinuous revision of Strategy Maps forAgeing Management and Safe Long Term Operation Ageing Management and Safe Long Term Operation by all the stakeholders has been performed under the by all the stakeholders has been performed under the Coordinating Committee of Ageing Management.Coordinating Committee of Ageing Management.

53

Summary (2)Summary (2)•• IIntensive safety research collaborations have been ntensive safety research collaborations have been performed accompanying the following activities;performed accompanying the following activities;– Systematic Development of Information Basis for Database

and Knowledge-base– Development of Codes and Standards by Academic Societies– International Contribution and Collaboration– Effective Sharing and Collaboration between Industries,

Government and Academia

•• Regulatory activities for ChuetsuRegulatory activities for Chuetsu--okioki earthquake earthquake which caused temporary shutdown of the which caused temporary shutdown of the KashiwazakiKashiwazaki--KariwaKariwa plants were briefly explained.plants were briefly explained.

54

Thank you very much.Thank you very much.

IIISSSaaaGGG 222000000888

Preliminary AnnouncementISaG2008

2nd International Symposium on the Ageing Management & Maintenance of Nuclear Power Plants

Tokyo, Japan, July or August 2008Organizer: Research Strategy Committee of NISA Project on Enhancement of Ageing Management and Maintenance of Nuclear Power PlantsFirst announcement: November 2007Call for Paper: January 2008 Registration: April 2008Topics: Building intelligence infrastructure on ageing and maintenance management, R&D activities, Standardization of technical information, Advancement and optimization of maintenance management in the industries and regulatory body, etc.Information: http://nisaplm.jp/ISaG2007/index.html

mailto: [email protected]

IIISSSaaaGGG

222000000888

Preliminary AnnouncementISaG2008

2nd International Symposium on the Ageing Management & Maintenance of Nuclear Power Plants

Tokyo, Japan, July or August 2008Organizer: Research Strategy Committee of NISA Project on Enhancement of Ageing Management and Maintenance of Nuclear Power PlantsFirst announcement: November 2007Call for Paper: January 2008 Registration: April 2008Topics: Building intelligence infrastructure on ageing and maintenance management, R&D activities, Standardization of technical information, Advancement and optimization of maintenance management in the industries and regulatory body, etc.Information: http://nisaplm.jp/ISaG2007/index.html

mailto: [email protected]