meeting between the u.s. nuclear rlt c iistffdthregulatory ...rlt c iistffdthregulatory commission...
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Meeting Between the U.S. Nuclear R l t C i i St ff d thRegulatory Commission Staff and the Nuclear Energy Institute to Discuss
Current License Renewal Topics
December 4, 2014
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Action Items
A NRC d NEI ill ti th i di iA. NRC and NEI will continue their discussion on industry’s two draft guideline documents on operating experience and AMP effectiveness self-assessment. p
B. NEI and EPRI will work with the NRC on a case by case basis to review requests for certaincase-by-case basis to review requests for certain portions of EPRI documents to be made publically available to support the SLR expert panels. Also as an ongoing effort EPRI will be revising documents to address operations from 60 to 80 years.
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Action Items cont.
C. NRC to provide schedule updates to GALL-SLR and SRP-SLR.
D. NRC and NEI will consider having a separate meeting on the draft Selective Leaching AMP after the NEI Mechanical Working Group Review releases the document to the NRC.
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NRC’s CABLE AGING RESEARCH ACTIVITIES
Darrell Murdock Division of EngineeringDivision of Engineering
Office of Nuclear Regulatory Research
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NRC’s CABLE AGING RESEARCH ACTIVITIES
OUTLINE
EVALUATION OF CABLE DEGRADATION IN A EVALUATION OF CABLE DEGRADATION IN A SUBMERGED ENVIRONMENT
ASSESSMENT OF CONDITION MONITORING METHODS OF ELECTRICAL CABLES
INTERNATIONAL RESEARCH COOPERATION
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NRC’s CABLE AGING RESEARCH ACTIVITIES
BACKGROUND Generic Letter 2007-01
o 269 Records Of Cable Failureo 269 Records Of Cable Failure NRC Starts a Research Project Called “Essential Elements
Of An Electric Cable Condition Monitoring Program”Commonly Used Condition Monitoring Techniqueso Commonly Used Condition Monitoring Techniques
o Elements That Constitute A Good CM Program In 2011 The NRC Issued
o NUREG 7000 “Essential Elements Of An Electric Cable Condition Monitoring Program”
o RG 1.218 “Condition Monitoring Techniques For Electric Cables Used In Nuclear Power Plants”
Condition Monitoring Techniques In RG 1.218 and NUREG 7000 Do Not Possess A Quantitative Predictive Capability Of Remaining Useful Life.
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EVALUATION OF CABLE DEGRADATION IN A SUBMERGED ENVIRONMENT
RESEARCH OVERVIEW
In 2013 RES Began The Project Called “Evaluation of Cable In 2013 RES Began The Project Called Evaluation of Cable Degradation In A Submerged Environment”.
Objective:o Develop A Predictive Model For Cables In A Submergedo Develop A Predictive Model For Cables In A Submerged
Environment The Project Was Divided Into Two Phases:
Fi t Pho First Phase:a)Perform A Literature Review Of Past Projects In The Realm
Of Submerged Cables.b)Provide Recommendations For Accelerating Aging Test
o Second Phase:a)Develop Test Plan) pb)Implement Accelerating Testing And Condition Monitoring
Techniques 7
EVALUATION OF CABLE DEGRADATION IN A SUBMERGED ENVIRONMENTENVIRONMENT
PHASE 1: LITERATURE SEARCH PRELIMINARY CONCLUSIONS
Fundamental Studies Are Needed To Systematically Understand Variables/Stressors.
Id tifi ti Of A C i t t E d f Lif (EOL) C it i I N d d Identification Of A Consistent End-of-Life (EOL) Criteria Is Needed Advances In Accelerated Aging Needed To:
o Understand Synergism Of The Stressors Advances In Condition Monitoring Required
o Track/Measure Proper Cable Parameter o Develop A Condition Monitoring Technique To Track Parametero Develop A Condition Monitoring Technique To Track Parameter
As The Cable Ages.
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EVALUATION OF CABLE DEGRADATION IN A SUBMERGED ENVIRONMENT
PHASE II: INTERIM RESEARCH
Perform Fundamental Studies To Systematically Understand StressorsU d t d S i Of Th Sto Understand Synergism Of The Stressors
Determine A Consistent End-of-Life (EOL) Criteria
Condition Monitoringo Track/Measure Proper Cable Parameter o Develop A Condition Monitoring Technique To Track Parameter Aso Develop A Condition Monitoring Technique To Track Parameter As
The Cable Ages.
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EVALUATION OF CABLE DEGRADATION IN A SUBMERGED ENVIRONMENT
PHASE III – ACCELERATED AGING PROTOCOL IMPLEMENTATION
Implement Developed Accelerated Aging Protocolp p g g
Develop Life Predictive Model
Validate Model With Field Samples
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ASSESSMENT OF CONDITION MONITORING METHODS OF ELECTRICAL CABLES
PURPOSE:
Determine The Most Applicable Condition Monitoring Techniques For Specific Insulation Materials
Establish Reproducible And Consistent Condition Establish Reproducible And Consistent Condition Monitoring Techniques Under Nuclear Plant Conditions
Inform Service Life Predictions Models At Lower Temperatures.Temperatures.
CONTRACTOR & COLLABORATORS National Institute of Standards and Technology National Institute of Standards and Technology
o University of Maryland EPRI
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ASSESSMENT OF CONDITION MONITORING METHODS OF ELECTRICAL CABLES
COMMONLY USED CONDITION MONITORING TECHNIQUES TO BE EVALUATED
Mechanical Condition Indicators: Elongation, Indenter Methods, Recovery Time
Dielectric Condition Indicators : Dielectric Condition Indicators :Insulation Resistance, Dielectric Loss, Time Domain Reflectometry, LIRA, Partial Discharge
Chemical Indicators :Oxidation Time/Temperature, Fourier Transform I f d S tInfrared Spectroscopy
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ASSESSMENT OF CONDITION MONITORING METHODS OF ELECTRICAL CABLES
PHASE 1: ASSESSING CM TECHNIQUES DURING OPERATIONAL AGING
Cables Subject To Normal Operating Conditions (temperature, radiation, humidity)
Samples Will Be Subject To Accelerated Aging To Simulate Samples Will Be Subject To Accelerated Aging To Simulate 40, 60 Years
Selection Of Exposure Environments Is Based On Normal Plant ConditionsPlant Conditions
Temperature (C ) Relative Humidity (%)
30 2042 50
Radiation Exposure Will Be Done At A Rate Of 40 G/hr For A T t l O ti l A i R di ti D Of 50 MR d
42 5055 70
A Total Operational Aging Radiation Dose Of 50 MRad(500 kGy).
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ASSESSMENT OF CONDITION MONITORING METHODS OF ELECTRICAL CABLES
PHASE 2: ASSESSING CM TECHNIQUES FOR CABLES SUBJECT TO ACCIDENT CONDITIONS
Cables Will Be Exposed To Accident Conditions Cables Will Be Exposed To Accident Conditions (temperature, pressure, humidity, radiation, chemical/steam spray)
Condition Monitoring Techniques Will Be Evaluated During And After The Accident Conditions.
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ASSESSMENT OF CONDITION MONITORING METHODS OF ELECTRICAL CABLES
PROJECT CURRENT STATUS
Naturally Aged Cableso Hope To Get Additional Naturally Aged Cables From
Zion In The Springo Possibility Of Getting Cable Samples From Crystal
River
Construction Of Ageing Chamberso Aging Chambers Will Be Completed 01/15 By Theo Aging Chambers Will Be Completed 01/15 By The
University Of Marylando Aging Should Begin 02/15 For 18 Months
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INTERNATIONAL RESEARCH COLLABORATIONS
IAEA Coordinated Research ProjectAssemble A Group Of Experts From Around The Worldo Assemble A Group Of Experts From Around The World To Provide Input On Condition Monitoring, Aging ManagementEstablish A Benchmarking Program Whereby Cableo Establish A Benchmarking Program Whereby Cable Samples Are Tested By Various Methods And Results Compared To Identify The Best Testing Methods
OECD/NEA Cable Aging Data And Knowledge (CADAK)o Follow Up To The SCAP Projecto Final Report Expected Early 2015
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AGING MANAGEMENT OF LOSS OF COATING OR LINING INTEGRITY FORCOATING OR LINING INTEGRITY FOR
INTERNAL COATINGS/LININGS ON IN-SCOPE PIPING PIPING COMPONENTSIN-SCOPE PIPING, PIPING COMPONENTS,
HEAT EXCHANGERS AND TANKSLR-ISG-2013-01LR ISG 2013 01
William C HolstonDi i i f Li R lDivision of License Renewal
Aging Management of Reactor Systems Branch Staff
Scope & Parameters
• AMP XI M42 or alternative AMPsAMP XI.M42 or alternative AMPs
• Physical damage
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Detection of Aging Effects
• Periodic visual inspections
• Extent of inspections• Extent of inspections
• Alternatives to managing loss of coating integrity
• Training and qualifications
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Acceptance Criteria
• Peeling and delaminationPeeling and delamination
• Blisters
• Cracking, flaking, and rusting
• Cementitious coatings
• Wall thickness measurementsWall thickness measurements
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Corrective Actions
• Alternative for peeling and delaminationp g
• Base material examinations
• Blister testing
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GALL Report-SLRAMP XI M33 S l ti L hiAMP XI.M33 Selective Leaching
Staff Questions Related to Industry Proposed AMP XI.M33 Changes
William C HolstonDivision of License Renewal
Aging Management of Reactor Systems Branch Staff
Staff Questions
Scope of Programp g
• Treated & closed-cycle cooling water
Detection of Aging Effects
• Population – material versus material & environmentPopulation material versus material & environment
• Number of inspections at multi-unit sites
• Detecting selective leaching of gray cast iron
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Staff Questions, cont.
Acceptance Criteriap
• Next inspection period, or
• End of subsequent period of extended operation
Corrective ActionsCorrective Actions
• Additional inspections
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GALL Report-SLRAMP XI 17 Fl A l t dAMP XI.17 Flow-Accelerated
Corrosion Program
Jim GavulaDivision of License RenewalDivision of License Renewal
Aging Management of Reactor Systems Branch Staff
Background / Issue
• Susceptibility guidelines allow system exclusions
– Operation less than 2 percent of plantOperation less than 2 percent of plant operating time
• Guidance does not limit duration of exclusion
• Cumulative effect for 60 year operation notCumulative effect for 60 year operation not addressed
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Proposed Resolution
• Detection of Aging Effects revisionDetection of Aging Effects revision
– Re-assessment for any system previously excluded due to limited operating time
R b d ll hi k– Re-assessment based on wall thickness measurements to confirm exclusion validity
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GALL Report-SLRAMP XI 20 O C l C li W tAMP XI.20 Open-Cycle Cooling Water
System Program
Jim GavulaDivision of License RenewalDivision of License Renewal
Aging Management of Reactor Systems Branch Staff
Background / Issue
V if I t d d f ti f i t t• Verify Intended function of service water system– Flow tests for portions where system configuration
allowsallows– Portions without testable configuration rely on design
parameter verification
• Design parameters affect flow– inside diameter of pipeinside diameter of pipe– friction factor or roughness factor
I t l t b l ti d l ff t b th t
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• Internal tuberculation adversely affects both parameters
Fouling from Tubercles
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Service Water Tubercles
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Proposed Resolution
• Parameters Monitored or Inspected revision
– Intended functions of non-tested portions verified using changes to design parameters
– Tested portions of system provide basis for changes to design parametersg g p
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Use of the Expanded Materials Degradation Assessment (EMDA)
Reports for SLRp
B tt B dBennett BradyDivision of License Renewal
Subsequent Renewal, Guidance, and qOperations Branch Staff
EMDA
• In 2007, NRC published the Proactive Materials pDegradation Assessment (PMDA)– Looked at potential degradation modes for core internals
and piping for operation to 40 years
• In 2010, NRR asked RES to – Expand the PMDA to also look at concrete and civil
structures the reactor pressure vessel and electricalstructures, the reactor pressure vessel, and electrical cables and insulation
– Extend to operation from 60 to 80 years
• Expert panels ranked the degradation modes as to susceptibility and current knowledge– Five volumes published in October 2014p
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Use of EMDA Results in SLR T h i l PTechnical Process
• Goal:
– Prioritize the technical work of the expert panels developing the GALL-SLR and SRP-SLRp g
– Define new aging management review “line-items”1
that were not in GALL 2that were not in GALL 2
– Provide comments to RES and to better understand the experts’ rankingsthe experts rankings
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1 i.e., a component, material, environment, aging effect/mechanism, and aging program combination
Determining Top Priority AMPs for SLRAMPs for SLR
• Looked at EMDA t i l/ i t/d d ti dmaterial/environment/degradation modes
ranked as– High susceptibility low knowledgeHigh susceptibility, low knowledge– High susceptibility, high knowledge– Moderate susceptibility, low knowledge
• Mapped these line items to GALL 2 line items (except for electrical items)
• Tabulated the AMPs managing these degradation modesg
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Setting Priority of AMPs
• Used– AMP rankings from EMDA results– EPRI’s AMP Gap Analysis– Technical judgment of NRC staff– Technically challenging AMPs for GALL 2
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Most Significant AMPs for SLRXI.M9 BWR Vessel Internals
XI.M16A PWR Vessel Internals
XI.S6 Structures Monitoring
XI.S2 ASME Section XI, Subsection IWLXI.S2 ASME Section XI, Subsection IWL
XI.M31 Reactor Vessel Surveillance
XI.M32 One-Time InspectionXI.M32 One Time Inspection
XI.E1 Insulation Material for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements
XI.E2 Insulation Material for Electrical Cables and Connections Not S bj t t 10 CFR 50 49 E i t l Q lifi tiSubject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits
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Most Significant AMPs for SLRMost Significant AMPs for SLRXI.M1 ASME Section XI, Inservice Inspection, Subsections IWB,
IWC and IWDIWC, and IWDXI.M35 One-time Inspection of ASME Code Class 1 Small bore piping
TLAA Concrete Containment Tendon PrestressX.S1XI.M33 Selective Leaching
XI M2 W t Ch i tXI.M2 Water Chemistry
XI.M11B Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor CoolantDue to Boric Acid Induced Corrosion in Reactor Coolant Pressure Boundary Components (PWR only)
XI.M4 BWR Vessel ID Attachment WeldsXI M6 BWR Control Rod Drive Return Line NozzleXI.M6 BWR Control Rod Drive Return Line Nozzle
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Example Line Items and Aging M h i Add d t GALLMechanisms Added to GALL
• Added loss of material due to pitting and crevice corrosion to steel components exposed to air-
t ll duncontrolled
• Added microbiologically influenced corrosionAdded microbiologically influenced corrosion (MIC) and new line items for MIC
Add d BWR i k l ll CRD t li l• Added BWR nickel alloy CRD return line nozzle caps and welds, cracking due to stress corrosion cracking intergranular stress corrosion crackingcracking, intergranular stress corrosion cracking.
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Generic Aging Lessons Learned (GALL) Reportg g ( ) pand Standard Review Plan (SRP) Schedule
for Subsequent License Renewal (SLR)
B tt B dBennett BradyDivision of License Renewal
Subsequent Renewal, Guidance, and Operations Branch StaffBranch Staff
SLR Timeline
Draft GALL & SRP Public Meeting &
Develop GALL & SRP
Comments Disposition
First Application Submitted?
First SLR License Issued?
2014 2015 20182016 2017 2019 20212020
Final GALL &Draft GALLFirst Application
Review?Final GALL & SRP
Draft GALL & SRP for comments
Review?
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Schedule Milestones
Milestone DateCompletion of draft GALL & SRP August 2015Advisory Committee on Reactor Safeguards (ACRS) Subcommittee Meeting
October 2015Subcommittee MeetingIssue draft GALL & SRP for SLR December 2015Public Meeting – Draft GALL & SRP January 2016End of draft GALL & SRP Comment Period February 2016Public Comments Disposition May 2016Completion of final GALL & SRP December 2016Completion of final GALL & SRP December 2016ACRS Full-Committee February 2017Issue Final GALL, SRP and Technical Basis for SLR June 2017
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