ageing management and safe long term operation of ... management and safe long term operation of...
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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
Nuclear Power Plants
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
Age-related Technical Evaluation Review Manual
• 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
Age-related Technical Evaluation Review Manual
• 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
Original in Japanese
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)
Neutron Irradiation Embrittlement of Reactor Pressure Vessel
Ageing Technical Evaluation Review Manual
Technical Document for Ageing Management of Nuclear Power Plants
December 2005 December 2005
December 2005 December 2005
Revised, October 2006
Neutron Irradiation Embrittlement of Reactor Pressure Vessel
Age-related Technical Evaluation Review Manual
Technical Document for Ageing Management Implementation of
Nuclear Power Plants
JNES - SS - 0570 - 01
Original in Japanese
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
December 2005 December 2005
December 2005 December 2005
Japan Nuclear Energy Safety Organization(JNES)
Neutron Irradiation Embrittlement of Reactor Pressure Vessel
Technical Evaluation Review Manual for Ageing Management
Technical Document for Ageing Management Implementation of Nuclear
Power Plants
JNES - SS - 0570 - 01
Original in Japanese
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)
Revised, 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
Japan Nuclear Energy Safety Organization(JNES)
Fatigue
Age-related Technical Assessment Review Manual
Technical Document for Ageing Management Implementation of Nuclear
Power Plants
JNES - SS - 0570 - 00
Original in Japanese
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
Japan Nuclear Energy Safety Organization(JNES)
Seismic Safety EvaluationAge-related Technical Assessment Review Manual
Technical Document for Ageing Management Implementation of Nuclear
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
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O2K2TM11F42F41F3T4OG12F21F1Tsu11F61F4①①①①
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O2④④④④④④④④
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GN3
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SM1
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③③③③
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SM2
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③③③③
T3
K1
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GN2M1
③③③③
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M21F1M1 I1H1SM11
③③③③③③③③
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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
Establishment of code and standards, and regulatory criteria
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
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-serviceIASCC integrity evaluation guide
Establishment of CS for fitness-for-service
Coding of IASCC initiation and growth simulationSCC long term integrity evaluation guide
Establishment of code and standards, and regulatory criteria
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
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
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]
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]