New Reactor ActivitiesJoseph Colaccino, Senior Project Manager Division of New Reactor LicensingOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory Commission

January 2006

*AgendaDiscuss goals for licensing under 10 CFR Part 52Provide overview of Part 52 licensing process components and current NRC activities associated with these componentsDesign certificationEarly site permit (ESP)Combined license (COL)Inspections, tests, analyses, and acceptance criteria (ITAAC)Discuss the review and implementation of operational programs for new plant licensing and constructionDiscuss guidance documents being developed by NRCNRC COL application guide NRC standard review plan updateIntroduce construction inspection program (CIP)New reactor forecastIndustry timeline for COL activitiesSummary

*Goals for Licensing Under Part 52More predictable licensing processResolve safety and environmental issues before authorizing constructionReduce financial risk to licensees (COL)Encourage standardization of nuclear plants

*Reference: November 21, 2005 Commission Meeting on New Reactor Activities

*Design CertificationsCertified design is appendix to 10 CFR Part 52Allows an applicant to obtain pre-approval of an essentially complete plant designReduces licensing uncertainty by resolving all design issues Facilitates standardizationHigher degree of regulatory finality15 year duration

*Design Certification ReviewSite safety (seismology, etc.)Environmental impactOperational programsSite-specific design featuresSelected design areas (design acceptance criteria)

Final design information w/ITAACPostulated site parametersInterface requirementsResolution of severe accident issuesAdvanced reactor testing requirements

What is reviewed:What is not reviewed:

*Westinghouse AP1000Certification expected January 2006

*General Electric ESBWR(Currently in NRC review)

*Framatome EPR(currently in pre-application review)

*ESPAllows an applicant to bank a siteReduces licensing uncertainty by resolving site-related issues early in the licensing process10 20 year durationApplications under reviewDominion (North Anna)Exelon (Clinton)Entergy (Grand Gulf)Pre-applicationSouthern (Vogtle)

*Early Site Permit ReviewSite Safety ReviewSeismologyGeologyHydrologyMeteorologyGeographyDemography (population distribution)Site Hazards EvaluationEmergency Preparedness ReviewEvaluate proposed emergency plan, or emergency preparedness informationEvaluate physical impediments, population distribution, & transportation routesFederal Emergency Management Agency (FEMA)

*Early Site Permit ReviewEnvironmental Protection ReviewSurface water quality, hydrology, & useAquatic ecologyGround-water use & qualityThreatened or endangered speciesAir qualityLand useUranium fuel cycle & waste managementHuman healthSocioeconomicsPostulated accidentsDecommissioningEnvironmental justiceAlternative sites

*COLCombined construction permit and conditional operating license for a nuclear power plantMay reference an ESP, a standard design certification, both, or neitherObjective is to resolve all safety & environmental issues before authorizing constructionPrior to fuel load, must verify the facility has been constructed in accordance with COLCOL is the fundamental licensing process in Part 52 for reducing regulatory risk for companies building nuclear power plants

*ITAACFirst mentioned in an Atomic Industrial Forum (AIF) Report on Standardization of Nuclear Power Plants in US (1986)Nuclear industry representatives proposed ITAAC so that licensees would know in advance the specific inspections and acceptance criteria for those inspectionsITAAC codified in Part 52 in 1989 Included in the Atomic Energy Act (Energy Policy Act of 1992)Provide reasonable assurance that the facility has been constructed and will be operated in conformity with the license, the provisions of the Atomic Energy Act, and the Commission's rules and regulations (10 CFR 52.97(b)(1))ITAAC are required to be submitted as part of the design certification and combined license applicationsITAAC reviewed by NRC staff in conjunction with applicationITAAC are conditions placed on the COLOpportunity for optional hearing regarding satisfaction of ITAAC acceptance criteria

*Examples of Types of ITAACs Included in Design Control Documents(reference: AP1000 DCD Tier 1, Section 2.1.2, Reactor Coolant System)

DesignCommitmentInspections,Tests, AnalysesAcceptanceCriteriaASME Code piping retains pressure boundary integrity at design pressureReport demonstrating piping meets ASME CodeA report exists and concludes piping meets requirements of ASME CodeRCP Flywheel can withstand design overspeed conditionOffsite testEach flywheel passes overspeed condition of 125% of operating speedRCS provides automatic depressurization during design basis eventsOnsite inspectionMinimum elevation of ADS outlet valves is greater than plant elevation of 110'RCS provides circulation of coolant to remove heat from coreTest with analysisCalculated post fuel load RCS flowrate is 301,670 gpmSafety related displays identified in table can be retrieved in MCRSimple InspectionSafety related displays identified in table can be retrieved in MCR

*Optional Hearing (10 CFR 52.103)Commission publishes notice of intended operation in Federal Register 180 days before scheduled fuel loadAny person whose interest may be affected by operation of the plant can request a hearing Hearing granted if prima facie evidence supports: One or more ITAAC acceptance criteria have not been or will not be met, andThe specific operational consequences of nonconformance that would be contrary to providing reasonable assurance of adequate protection of the public health and safety

*Operational ProgramsContainment Leak Rate TestingEmergency Preparedness (EP)*Fire ProtectionMaintenance RuleOperator TrainingOperator RequalificationPlant Staff TrainingPhysical SecurityWeapons Training and Weapons Qualification and ReqalificationAccess AuthorizationFitness for Duty

RadiationReactor Vessel Material SurveillanceProcess and Effluent Monitoring and Sampling Quality Assurance OperationPreservice InspectionInservice InspectionPreservice TestingInservice TestingEquipment QualificationMotor-Operated Valve TestingSafeguards Contingency PlanSECY-05-0197, Review of Operational Programs in a Combined License Application and Generic Emergency Planning Inspections, Tests, Analyses, and Acceptance Criteria, identified the following as operational programs:*EP has ITAAC

*Development of Standard Format and Content Guide for a Combined License Application

Starting point: Regulatory Guide (RG) 1.70Complete set of information to be included in COL application Applicable to applications referencing a certified design, an early site permit, both, or neitherWork-in-progress chapters will be placed on NRC website to facilitate stakeholder interaction (public meetings)Scheduled issuance for draft RG for public comment in June 2006Workshop tentatively scheduled for July 2006 to discuss draft RG

*Update to NRC Standard Review Plan (SRP) (NUREG-0800)Approximately 290 SRP Sections (including Branch Technical Positions)Certain SRP sections to be updated by 2007 to support COL applicationsHigh priority SRP sections new or existing sections providing guidance related to new reactor licensing (e.g., Section 14.3 on ITAAC);sections addressing operational programs (including industry identified sections);sections with inconsistent technical guidance; and site-specific sections addressed in RS-002, Processing Applications for Early Site Permits.Medium priority SRP sections design-related sections used in previous design certification reviews

*Construction Inspection ProgramCollect data to support licensing decisionsMonitor and evaluate construction activities supporting ITAAC completionMonitor and evaluate the development and implementation of operational programsEvaluate operational readinessNUREG-1789: 10 CFR Part 52 Construction Inspection Program Framework Document

*CIP Manual ChaptersIMC 2501 - ESP InspectionsIMC 2502 - Pre-COL InspectionsIMC 2503 - ITAAC InspectionsIMC 2504 - Non-ITAAC Inspections

*Reference: November 21, 2005 Commission Meeting on New Reactor Activities(South Carolina)

*Figure 3-1* Overview and Timeline of COLA-Related ActivitiesCOLA PreparationImplement QA, Part 21 and DRAP ProgramsLong-lead procurement NRC Review & HearingPlant ConstructionAntitrust Submittal9 mos18-24 monthsProject DecisionCOLA SubmittalCOLIssuanceITAAC Finding Fuel LoadS/U Tests22-30 months24-48 months9 mos Annual P-S DCD updates Qtrly reports on departures ITAAC completion, NRC verification and Section 52.99 notices Operation

Annual P-S DCD update and report on departures DAC Completion LWA-1, LWA-2; implement Construction FFD ProgramSchedule coordination with NRC construction inspection program Site-specific & detailed design and NRC Engineering Design VerificationFull PowerOperations QA Meeting w/NRC Early ITAAC-related activitiesThis figure provides an overview of the COL process from project decision to plant operation. The figure depicts key milestones, concepts, processes and relationships discussed in NEI 04-01*Reference: NEI 04-01, Revision D, submitted to NRC on December 21, 2004 (ML050110295)NRC: Operational Program Inspections 27(NRC Note: assumes COL references a certified design and an ESP)X

*SummaryNRC currently reviewing design certifications and ESPsNRC preparing for a large number of COL applications in 2007-2008 time frameNRC preparing regulatory framework to review the incoming COL applications and perform inspection of construction activitiesTimely review of COL applications requires both NRC preparation of regulatory framework and industry standardization of applicationsFor more information, visit our website:http://www.nrc.gov/reactors/new-reactor-licensing.html

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