acrs meeting with the u.s. nuclear regulatory commission
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8/3/2019 ACRS MEETING WITH THE U.S. NUCLEAR REGULATORY COMMISSION
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SU.S.NRCUnited States Nuclear Regulatory CommissionProtectingPeopleand theEnvironment
ACRS MEETING WITHTHE U.S. NUCLEARREGULATORYCOMMISSIONNovember 29, 2011
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U.S.NRCUnited States Nuclear Regulatory CommissionProtectingPeopleand theEnvironment
Overview
Said Abdel-Khalik
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Accomplishments Since our last meeting with the
Commission on June 6, 2011, weissued 16 Reports.
* Topics:InitialACRS Review of: (1) the NRCNear-Term Task Force Report onFukushima and (2) Staff'sRecommended Actions to be TakenWithout Delay
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* Topics (cont.):- ACRS Review of Staff's
Prioritizationof RecommendedActions to be Taken in Response toFukushima Lessons Learned (SECY-11-0137)
- ProposedRulemaking to Introducea Site-Specific PerformanceAssessment and Human IntrusionAnalysis Requirement to 10 CFRPart614
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* Topics (cont.):- Draft SECY Paper, Options forProceedingwith Future Level 3ProbabilisticRisk AssessmentActivities"- Selected Chaptersof the Safety
Evaluation Report (SER) with OpenItems for Certificationof the U.S.APWR Design- Nine Mile Point Nuclear Station,
Unit 2, Extended Power UprateApplication5
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* Topics (cont.):- FinalSER Associated with theLicense Renewal Application for
Hope Creek GeneratingStation- GeneralElectric Topical ReportNEDC-33173P, Supplement 2, Parts1, 2, and 3, "Analysis of Gamma
Scan Data and Removal of SafetyLimit Minimum CriticalPower Ratio(SLMCPR) Margin"
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* Topics (cont.):- Assessment of the Quality of
Selected NRC Research Projects- Draft FinalRevision 6 of Standard
Review Plan Branch TechnicalPosition 7-19, "Guidance forEvaluation of Diversity andDefense-in-Depth in DigitalComputer-BasedInstrumentationand Control Systems"
- Enhancing the Fuel Cycle OversightProcess
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* Topics (cont.):Draft Regulatory Guides in Supportof Proposed10 CFR 50.46(c) Rule,"Requirements for Emergency CoreCooling Systems for LWRs":m DG 1261, Conducting Periodic:Testing
for Breakaway Oxidation Behaviorm DG 1262, Testing for Postquench
Ductilityw]DG 1263, EstablishingAnalyticalLimits for Zirconium-BasedAlloyCladding
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* Topics (cont.):
Revision 19 to the AP1000 DesignControlDocument (DCD) and theAP1000 FinalSafety Evaluation* In December 2010, we concluded
that the API000 DCA maintainsthe robustness of the previouslycertified design
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- Rev. 19 to APIO00 DCD (cont.)* Conclusion relied in part oncommitments provided by WEC
during our meetings which were notyet included in the DCA application
* Revision 19 of the DCD wassubmitted in June 2011 and staffFSER issued in August 2011
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-Rev. 19 to APIO00 DCD (cont.)DCD Revision 19 Changes/Additional finite element analyses
of Passive Cooling System Tankvl Additional analyses of seismic and
thermal load combinationsof theEnhanced Shield Building (ESB)VAdditional Tier 2* information
describingsteel modules of theESB wall
/Updated containment accidentpressure analysis
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- Rev. 19 to APIO00 DCD (cont.)* The changes proposed n theAPI00 DCD amendment, including
those made in Revision 19,maintain the robustness of theprevious certified design.
* There is reasonableassurancethat the revised design can bebuilt and operated without unduerisk to the health and safety of thepublic.
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New PlantActivities* Reviewing:DC applicationsand SERs associatedwith the U.S. EPR and US-APWR
designs-Adequacy of Long-Term Core CoolingApproach for the ABWR and US-APWR-Reference COLAs for ABWR, ESBWR,US-APWR, and U.S. EPR
Subsequent COLAs for API00* Continuing to complete reviews ofavailablematerialpromptly'14
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License Renewal* Interim and final reviews to be
performed for Columbia,Davis Besse, Seabrook, andSouth Texas
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Power Uprates* Will review the GrandGulf, Turkey
Point,St. Lucie, Monticello, FortCalhoun, Peach Bottom, and PrairieIsland Extended Power UprateApplications
* Will review GE Topical Report NEDC-33436P,"BWR Vessel Internals Project,Methodology for DemonstratingSteamDryer Integrity for Power Uprate"
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Other OngoingiFutureActivities Fukushima Longer-Term Reviews SOARCA4 Watts Bar 2 DigitalI&C0 10 CFR 50.46(c)0 Emergency Planning or Small ModularReactors* Revision to the ConstructionReactor
Oversight ProcessAssessment Program Blending of Low-Level Radioactive Waste Safety Culture Emerging Technical Issues Extended Dry Cask Storage 17
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KU.S.NRCUnited States Nuclear Regulatory CommissionProtectingPeopleand theEnvironment
ACRS Review ofFUKUSHIMA
Said Abdel-Khalik18
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ACRS Briefings on Fukushima" April 7- NRC Staff on InitialResponse" May 26- DOE and NEI* June 23 - NRC Staff on Task Force
Actions* July 12-INPO" August 16 & September 8- Near Term
Task Force October 7- Fukushima Steering
Committee
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ACRS Reports on FukushimaResponses to Commission Tasking viaSRM-SECY-11-0093, "Near-Term Reportand Recommendations for AgencyActions Following the Events in Japan"- ACRS Letter Report dated October 13, 2011- ACRS Letter Report dated November 8, 2011
* Additional Letter Reports will be issuedas we engage with the staff on actionplans related to specificrecommendations
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ACRS Letter - October 13, 2011" Staff's recommended actions are
appropriately ocused on lessonslearned from what is currentlyknown
" Near-term recommendationsunlikely to be negated, or renderedinappropriate, y the acquisitionofnew information
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ACRS Letter - October 13, 2011" ACRS review focused on
completeness and appropriatenessof recommended staff actions
* Two categoriesof recommendations- Additional immediate actions (2.1-Day
Report)- Additional actions beyond those
specified in the NTTF Report22
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ACRS Letter - October 13, 2011Additional Immediate Actions (21-Day Report)
Actions related to NTTF Recommendation2.1 (seismic and flood re-evaluations)should be expanded to include anexpedited update of the applicableregulatoryguidance,methods, and datafor external flooding
* Actions related to NTTF Recommendation2.3 (seismic and flood walkdowns) shouldbe expanded to address the integratedeffects of severe storms
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ACRS Letter - October 13, 2011Additional Immediate Actions (21-Day Report)
Actions related to NTTF Recommendation4.1 (SBO regulatoryactions)should beexpanded to include issuance of anadvanced notice of proposed rulemakingand require licensees to provide anassessment of capabilities o cope withan extended SBO
* Actions related to NTTF Recommendation5.1 (reliablehardenedvents for Mark Icontainments)should also be applied toBWRs with Mark II containments
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ACRS Letter - October 13, 2011Additional Immediate Actions (21-Day Report)" Discussionswith stakeholdersshould be
initiatedregardingnear-term actions foradditionalhydrogen controland mitigationmeasures in reactorbuildings for plantswith Mark I and Mark II containments.
* Information should be requested fromlicensees regardingcurrentplant-specificspent fuel pool instrumentation,powersupplies, and sources of makeup andcooling water.
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ACRS Letter - October 13, 2011Additional Immediate Actions (21-Day Report)* Actions related to NTTF Recommendation8 (integrationof EOPsISAMGsIEDMGs)should be expanded to include fireresponse procedures.
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ACRS Letter - October 13, 2011Additional Recommendations to
NTTF Report* Performance-based riteria o
mitigate and manage an extendedSBO should be consideredas analternative to the specific copingtimes proposed n Recommendation4.1z
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ACRS Letter - October 13, 2011Additional Recommendations to
NTTF ReportRecommendation 6 should beexpanded to include:- a requirement for BWR plants with MarkI and Mark !I containments toimplement combustible gas controlmeasures in reactorbuildings as a near-term defense-in-depth measure.
- an assessment of the vulnerabilitiesintroducedby shared ventilationsystems or sharedstacks in multi-unitsites.
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ACRS Letter - October 13, 2011Additional Recomm endations to
NTTF Report
* Selected reactorand containmentinstrumentationshould be enhancedto withstand beyond-design-basisaccident conditions.
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ACRS Letter - October 13, 2011Additional Recommendations to
NTTF ReportThe NRC should proactively engagein efforts to define and participate nprograms to capture and analyzedata from the Fukushima event toenhance understandingof severeaccidentphenomena, including BWRmelt progression,seawateradditioneffects, hydrogen transportandcombustion, and safety systemsoperability.
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ACRS Letter - October 13, 2011ContainmentAccident Pressure
Licensing actions requiringthegrantingof containment accidentpressure (CAP) credit should besuspended until the implicationsofpost-Fukushima containmentpressure control measures areunderstood.
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ACRS Letter - November 8, 2011Staff's three-tierapproachandcriteria or prioritizationof NTTFrecommendations are appropriatesubject to the following additionalrecommendations:
Rulemaking activities related tostrengthening of SBO mitigationcapabilityshould be expedited
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ACRS Letter - November 8, 2011(additional ecommendations)Tier 1 recommendationsshould beexpanded to include additionalactions identified in our O ctober 13,2011, report:" guidance for flooding hazardsevaluations" integratedwalkdowns" station blackout" BWR hardenedvents" shared ventilations systems" hydrogen control and mitigation" spent fuel pools" integrationof onsite emergencyactions 33
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ACRS Letter - November 8, 2011(additional ecommendations)NTTF recommendation 10.2regardingevaluation of the commandand control structure andqualificationsof decision makersshould be initiated n parallelwithTier 1 activities related to integrationof onsite emergency actions
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ACRS Letter - November 8, 2011(additional ecommendations)Tier 2 recommendationsshould beexpanded to include the additionalrecommendationsregardingenhancement of selected reactorand containment instrumentation,and the need to proactively engage inefforts to capture and analyze datafrom the Fukushima event
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ACRS Letter - November 8, 2011(additional ecommendations)Tier 1 recommendation 7.1-2,"Develop and issue order to licenseesto provide reliableSFPinstrumentation,"should bereconsidered. Schedules for SFPinstrumentation mprovements andother modifications to the SFP shouldbe informed by quantificationof thecontributionmade by SFPs to overallplant risk.
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Summary Staff's recommended actions areappropriately ocused on lessonslearned from what is currently known* Near-term recommendationsunlikely tobe negated, or rendered inappropriate,by the acquisitionof new information* Looking forward to future engagementswith staff to review specific actionsrelated to prioritizationefforts.
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SU.S.NRCUnited States Nuclear Regulatory CommissionProtectingPeopleand theEnvironment
ProposedRulemakingto addSite-Specific Analysis toPart61
Michael T. Ryan.38
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SRM-SECY-08-0147Directed the staff to:
e Proceedwith rulemaking to add site-specific analysis for disposalof largequantitiesof depleted Uranium (DU)
SRM-SECY-10-00Directed the staff
Incorporate argelevel waste (LLW)
Ntonscale blending of low-in the rulemaking
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CurrentPart61 PerformanceObjectivese 61.41 - Principal equirementsfor protection of members of thepublic9 61.42 - Protectionof theinadvertentintruder9 61.43 - Protectionof individualsduring operations
. 61.44 - Stability of the disposa lsite after closure40
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ProposedMajor Rule ChangesS61.41*Adds Site-Specific Performance
Assessment*Adds Period-of-Performance POP)of
20,000 years
S61.42*Adds Site-Specific IntruderAnalysis"Adds 500 mrem annualdose for anIntruder"Includes POP of 20,000 years
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ProposedMajor Rule Changes461w13Adds Site-Specific Long-Term Analysis:
-Consider the potential long-termradiological mpacts-Calculate peak dose that would occur20,000 years or more after site closure
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ACRS Recommendations* Part61 should not be amendedas recommended by staff* Assessment methodology should
be risk informed andperformance based* POP should not be specified inrule; It should be site-specificand risk informed with respect todisposaltechnology and sitecharacteristics
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Risk-InformedApproach" Radionuclide Characteristics" Waste Form" Waste Package" DisposalTechnology* Cover Technology" GeohydrologicalEnvironment
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POP* 20,000 years is excessive.
- IAEA Safety Standard (SSR-5)recommends "severalhundredyears" for short-lived and"severalthousandyears" forintermediate and high-levelwaste
- DOE (Order435.1) uses 1000years for LLW
- NRC HLW (Part63) uses 10,000years
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POP (cont.)ACNW previously (1997 and 2000)recommended two-part approach:* (1) Site-specific time to address
more mobile radionuclides-peak dose for compliance* (2) Qualitativeassessment ,
without compliance measure, toidentify possible deficiencies inlong term perform ance offacility
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POP (Cont.)" Assessments longer than a few
hundred to a thousandyearsshould focus on major failures ofa disposal system , rather han afew intruders" Only one commenter out of 15 ondraft proposed languagespecifically supported 20,000 yearPOP
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Disposal of DU" DU can be acceptable waste for
disposal n a Part61 LLW facility,under certain circumstances" DU can be evaluated in a risk
informed performance assessmentfor a LLW facility* For example - a range of depth
of burials could be evaluated tominimize intrudercontact withDU waste
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Inadverten in truders OriginalPart61 - intruderanalysis was
a simplified bounding calculation toestablish concentrations or certainradionuclides
More realistic nadvertent intruderscenarios that consider site-specificfactors should be used within a risk-informed approach
Most LLW is decayed away with only asmall number of radionuclidespresentafter 300 years
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In Conclusion" Greateremphasis on a risk
informed approach for LLWmanagement" Focus on radionuclidequantity
rather han waste origins orconcentrations* Realistic treatment of intruder
protection, including probabilityand consequences of intrusion,andotherparameters(depth of burial,performance of intruderbarriers)
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SU.S.NRCUnited States Nuclear Regulatory CommissionProtectingPeopleand the Environment
Options for Proceedingwith Future Level 3ProbabilisticRisk
Assessm ent ActivitiesJohn W. Stetkar
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SEC Y-11-0089" "Options for Proceedingwith Future
Level 3 ProbabilisticRisk AssessmentActivities"
" Option 1: Status Quo - Evolutionarydevelopment of PRA technology
Option 2: Focused Research -Address identified technology gapsbefore conducting full-scope PRA
* Option 3: Full-scope Level 3 PRA foroperatingnuclearpower plant52
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ACRS Reviews" Subcommittee meetings in November
2010 andMay 2011" Full Committee meeting in June 2011" ACRS recommended modified version
of Option 3" SRM for SECY-11-0089 in September2011 approved modified version ofOption 3
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Analytical Advances SinceNUREG.1150
* PRA methods (human reliability,fires, seismic, other external events)
* Severe accidentphenomena Risk during shutdown modes* Characterizationand quantification
of uncertainty
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Industry Advances SinceNUREG.1150
" Plantoperationsand maintenance Plantmodifications" Risk-informed configurationcontrol Severe accidentmitigationguidance" Emergency planning
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Level 3 PRA" Fully integratedassessment" Identificationof important linkages
and dependencies (physical,functional,human)
" Balanced understandingof currentrisk profile and contributors
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Option 3 vs. Option 2" Additional researchwill be needed
to address specific issues" Level 3 PRA provides scenario-based
context and focus" Level 3 PRA may identify otherimportantknowledge gaps that
requirepracticalsolutions" Simplified or bounding assessments
can distort understandingof actualrisk57
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IntegratedLevel 3 PRA Results* Interim results should benefit from
integratedassessment of Level 3 riskfor specific hazard categoriesandplant operatingstates- Internal events and hazards at full power- External events at full power- Multi-unit site risk at full power- Internal events and hazards at shutdown-External events at shutdown- Multi-unit site risk, mixed unit modes- Other contributors(e.g., fuel pools, ISFSI)
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Available Technical Information Active industry participationand
collaborative nput" Selection of participatingplant site" Benefit from existing SPAR models
and plant-specific analyses" Benefit from other NRC initiatives(e.g., SOARCA)
" May be prudent to select PWR site,pending understandingof FukushimaDaiichiaccidentprogression
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Expected Level 3 PRA Benefits" Staff knowledge and experience
from performance of a modern full-scope Level 3 PRA
* Integratedrisk perspective" Input to emergency planning" Input to resolution of generic issues" Quantitative framework to address
new reactordesign and siting issues
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Abbreviations
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ABWR Advanced Boiling Water ReactorACNW Advisory Committee on NuclearWasteACRS Advisory Committee on ReactorSafeguards
APWR Advanced PressurizedWater ReactorAPIO00 Advanced Passive 1000BWR Boiling Water ReactorCAP ContainmentAccident PressureCFR Code of FederalRegulationsCOLA Combined License ApplicationDC Design CertificationDCA Design CertificationAmendmentDCD Design Control DocumentDG Draft Regulatory GuideDOE U.S. Departmentof EnergyDU Depleted UraniumEDMG Extreme D amage Mitigation GuidelineEDO Executive Director or OperationsEOP Emergency OperatingProcedureEPR Evolutionary Power ReactorESB Enhanced Shield BuildingESBWR Economic Simplified Boiling Water
ReactorFSER FinalSafety EvaluationReportGE GeneralElectricHLW High Level Waste
IAEAINPOISFSII&CLLWLWRmremNEINRCNTTFPRAPOPPWRRGSAMGSBOSECYSERSF PSOARCASPARSRMWEC
InternationalAtomic Energy AgencyInstitute of Nuclear Power OperationsIndependent Spent Fuel StorageInstallationInstrumentation& ControlLow Level WasteLight Water ReactormilliremNuclearEnergy InstituteNuclearRegulatory CommissionNear-Term Task ForceProbabilisticRisk AssessmentPeriodof PerformancePressurizedWater ReactorRegulatory GuideSevere Accident Management GuidelineStation BlackoutSecretary of CommissionSafety Evaluation ReportSpent Fuel PoolState-of-the-Art Reactor ConsequenceAnalyses.StandardizedPlantAnalysis RiskStaff Requirements MemorandumiMemorandaWestinghouse Electric Company
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