ML13205A214

Wolf Creek Nuclear Operating Corporation - Slides for Pre-application Meeting on 7/30/13 - Core Design and Safety Analysis Methodology Transition License Amendment Request for Wolf Creek Generating Station (TAC No. MF2309)

ML13205A214
Person / Time
Site:	Wolf Creek
Issue date:	07/30/2013
From:	Wolf Creek
To:	Office of New Reactors
Lyon C F
References
TAC MF2309
Download: ML13205A214 (29)

Text

WCNOC-NRCPre-submittalMeetingWCNOCNRC Presubmittal MeetingCore Design and Safety Analysis Methodology TransitionLicenseAmendmentRequestTransition License Amendment RequestJuly302013July 30, 2013Wolf Creek Nuclear Operating Corporationpgp1 Meeting AgendaMtiP/Objti*Meeting Purpose / Objectives*IntroductionsLicenseAmendmentRequest(LAR)Content*License Amendment Request (LAR) Content*Transition to Westinghouse Analysis MethodologiesMethodologies*RTS/ESFAS/LOP DG Start Instrumentation Setpoint Uncertainty Analysisyy*Alternative Source Term (AST)*LAR Schedule2*Summary2 Introductions*NRC*WCNOC Team *Westinghouse Support

• Teleconference Attendees33 WCNOC Ownership of Safety AnalysisWCNOCOhifthSftAliidttd*WCNOC Ownership of the Safety Analysis is demonstrated through the strength and application of the Quality Assurance (QA) Program-WCNOC technical oversight is provided by the QA processes and participation in NUPIC-WCNOC QATittlfDiIftifdtth*Transmittal of Design Information -referenced to the source calculation, design basis document, or identified as a direct input*Owner's Acceptance Review

• ConfigurationManagementupdates,regulatoryreviews,etc.Configuration Management updates, regulatory reviews, etc.*WCNOC/Westinghouse (WEC) Interface-On-site WEC staff responsible for core design and safety analysisOnsiteWECstaffmaintainsqualificationsinboththeWCNOCand44-On-site WEC staff maintains qualifications in both the WCNOC and WEC QA programs. Proper independence is always maintained between the QA programs.4 License Amendment Request Content*License Amendment Request (LAR) to revise the WCGS Technical Specifications (TSs) based on:-Transition to Westinghouse core design and safetyanalysismethodologiessafety analysis methodologies-Transition to Westinghouse Setpoint Methodology-FullScopeImplementationofAlternativeSourceFull Scope Implementation of Alternative Source Term (AST)55 License Amendment Request Content*LAR is consistent with NEI 06-02, "License Amendment Request (LAR) Guidelines" template Attachments:Attachments:I-EvaluationII-Proposed TS Changes (Mark-up) pg(p)III -Revised TS pages IV-Proposed TS Bases Changes (info only)V-Proposed COLR Changes (info only)6 License Amendment Request Content*LARcontent(cont)*LAR content (cont.)Enclosures:I-WCAP-17658-NP-TransitionLicensingReportIWCAP17658NP Transition Licensing ReportII-WCAP-17746-P -Setpoint Methodology for WCGSIII -WCAP-17746-NPIV-WCAP-17602-P -Setpoint Calculations for WCGSV-WCAP-17602-NPVIFullScopeImplementationofAlternativeSourceTermVI-Full Scope Implementation of Alternative Source TermVII -CD-ROM containing Meteorological Data VIII -Proprietary Information Affidavit for WCAP-17746-PIX -Proprietary Information Affidavit for WCAP-17602-P77 TransitiontoWestinghouseAnalysisTransition to Westinghouse Analysis MethodologiesCDidSftAliMthdl*Core Design and Safety Analysis Methodology-The Non-LOCA safety analyses were analyzed with Westinghouse, NRC approved methodsg,pp-All of the Westinghouse Non-LOCA methods are applicable to the WCGSTheContainmentresponseanalysesofrecordarenot-The Containment response analyses of record are not impacted-The SBLOCA and LBLOCA analyses of record are not impacted-The Core Design and Fuel Rod Design will be evaluated for each reload cycle88y8 TransitiontoWestinghouseAnalysisTransition to Westinghouse Analysis MethodologiesOifAliMthdlS*Overview of Analysis Methodology Scope-Non-LOCA Safety Analyses*RETRAN-02 for Westinghouse PWRs (WCAP-14882-P-A) g()was used for majority of the analyses*LOFTRAN (WCAP-7907-P-A) was used for some analyses

• Other Codes that were used:-TWINKLE (WCAP-7979-P-A)-FACTRAN (WCAP-7908-A) -Non-LOCA Thermal-Hydraulics (T&H) Safety Analyses*VIPRE-01 (WCAP-14565-P-A) was used for the T&H analyses-RETRAN-02 (WCAP-14882-P-A) and WCAP-10698-P-A dfthStGtTbRtMi99were used for the Steam Generator Tube Rupture Margin to Overfill and Input to the Dose analyses9 TransitiontoWestinghouseAnalysisTransition to Westinghouse Analysis MethodologiesOifAliMthdlS(t)*Overview of Analysis Methodology Scope (cont.)-DNB Correlations used in the VIPRE-01 DNBR calculationscalculations*The WRB-2 DNB correlation will continue to be used as the primary DNB correlation for the T&H analyses of fuel regions abovethefirstmixingvanegridabove the first mixing vane grid*The ABB-NV DNB correlation was used for the T&H analyses of fuel regions below the first mixing vane gridTheWLOPDNBcorrelationwasusedfortheT&Hanalysesthat*The WLOP DNB correlation was used for the T&H analyses that are outside the range of applicability of the WRB-2 and ABB-NV DNB correlations 101010 TransitiontoWestinghouseAnalysisTransition to Westinghouse Analysis MethodologiesfOC*Implementation of the Westinghouse Non-LOCA Safety Analysis Methodology resulted in five changes tothecurrentWCGSTSsto the current WCGS TSs-SLs 2.1.1, Added the ABB-NV and WLOB DNB Correlations-TS 3.3.1, RTS Function 10, Reactor Coolant Flow-Low-TS 3.4.1, RCS Pressure, Temperature and Flow DNB LimitsLimits*The Minimum Measured Flow (MMF) was relocated to the COLR and revised from 371,000 gpm to 376,000 gpm1111*The Thermal Design Flow -361,200 gpm, replaces the MMF11 TransitiontoWestinghouseAnalysisTransition to Westinghouse Analysis MethodologiesIlttifthWtihNLOCASft*Implementation of the Westinghouse Non-LOCA Safety Analysis Methodology results in five changes to the current WCGS TSs (cont.)()-TS Table 3.7.1-1, OPERABLE MSSVs versus Maximum Allowable Power, the maximum allowable power for 4, 3, and2OPERABLEMSSVswasrevisedand 2 OPERABLE MSSVs was revised-TS 5.6.5, COLR*Added WCAP-9272-P-A, the Westinghouse Reload MthdltSifiti565bMethodology to Specification 5.6.5 b.*Deleted the WCNOC methodologies from Specification 5.6.5 b.*WCAP-9272-P-A is the only methodology associated with a Tech Spec COLR parameter1212 TransitiontoWestinghouseAnalysisTransition to Westinghouse Analysis MethodologiesFllfth9/20/12PSbittlMti*Followup from the 9/20/12 Pre-Submittal Meeting-Provide a roadmap of which code was used to analyze each postulated accident -Attachment I of the LAR includes a roadmap-The Limitations, Restrictions and Conditions for the Westinghouse codes used in the Non-LOCA safety analyses are addressed in detail, including justifications in the LAR (Enclosure I, Appendix A)131313 InstrumentationSetpointUncertaintyInstrumentation Setpoint Uncertainty AnalysisUtitAli*Uncertainty Analysis-Transition from the existing WCNOC Setpoint Methodology to the current Westinghouse Setpoint gygpMethodology as applied to WCGS for RTS, ESFAS and LOP DG Start Instrumentation (WCAP-17746-P, Enclosure II of LAR),)-Technical Specification Changes*TS 3.3.1,TS 3.3.2, and TS 3.3.5 Allowable Values were replacedwithaNominalTripSetpointreplaced with a Nominal Trip Setpoint*TS Table 3.3.1-1, Overtemperature T, Note 1 and Overpower T, Note 2 14 1414 InstrumentationSetpointUncertaintyUtitAli(t)Instrumentation Setpoint Uncertainty Analysis*Uncertainty Analysis (cont.)-Calculations were performed for the RTS, ESFAS, and LOP DG Start instrumentation Functions using the current Westinghouse setpoint methodology (WCAP-17602-P, Enclosure IV of LAR))-Implementation of the Westinghouse Setpoint Methodology resulted in two changes to the existingWCGSTripSetpointsexisting WCGS Trip Setpoints*TS 3.3.1, RTS Function 10, Reactor Coolant Flow-Low*TS 3.3.5, Degraded Voltage Function1515 InstrumentationSetpointUncertaintyInstrumentation Setpoint Uncertainty AnalysisTSTF493ARii4OtiAThil*TSTF-493-A, Revision 4, Option A -Technical Specification Changes-VariationfromOptionA-NominalTripSetpointVariation from Option A Nominal Trip Setpoint specified in the single column format based on the Westinghouse Setpoint MethodologyTShildthdditifidiidl-TS changes include the addition of individual Surveillance Requirement footnotes to the applicable instrumentation Functions in accordance with Option pA of TSTF-493, Revision 41616 InstrumentationSetpointUncertaintyInstrumentation Setpoint Uncertainty Analysis*Followup from the 9/20/12 Pre-Submittal Meeting-The level of detail of the setpoint methodology and setpoint calculations for WCGS is consistent with that in the Diablo Canyon Power Plant (DCPP) y()submittal of March 7, 2013 (DCL-13-016)-WCNOC specific setpoint calculations are providedinWCAP-17602-P(EnclosureIVofLAR)provided in WCAP17602P (Enclosure IV of LAR)17 Alternative Source TermFllSIlttifthAST*Full Scope Implementation of the AST-Radiological dose consequences analyses were performed for the accidents specified in Regulatory ppgyGuide (RG) 1.183 include:*Main Steamline Break (USAR Section 15.1.5.3)*LockedRotor(USARSection15333)*Locked Rotor (USAR Section 15.3.3.3)*Rod Ejection (USAR Section 15.4.8.3)*Steam Generator Tube Rupture (USAR Section 15.6.3.3)*Loss of Coolant Accident (USAR Section 15.6.5.4)*Fuel Handling Accident (USAR Section 15.7.4)181818 Alternative Source Term*Full Scope Implementation of the AST (cont.)-Radiological dose consequences analyses performedforadditionalaccidentsnotspecifiedinperformed for additional accidents not specified in RG 1.183 include:*Loss of Non-Emergency AC Power (USAR Section 15263)15.2.6.3)*Letdown Line Break (USAR Section 15.6.2.1)*Waste Gas Decay Tank Failure (USAR Section 15.7.1)LiqidWasteTankFailre(USARSection1572)*Liquid Waste Tank Failure (USAR Section 15.7.2)-Dose consequences analyses were performed using version 3.03 of the RADTRAD computer dcode1919 Alternative Source Term*Full Scope Implementation of AST (cont.)-No changes to the licensing basis EQ dose analysesmaintainingtheTID14844accidentanalyses -maintaining the TID-14844 accident source term -No changes to the licensing basis NUREG-0737 evaluations other than the Control Room Habitability Envelope (CHRE) doses (III.D.3.4) and Technical SupportCenterdoses(IIIA12)Support Center doses (III.A.1.2)202020 Alternative Source Term*Atmospheric Dispersion Factors (X/Q)-New X/Q values were calculated*Offsite(EABandLPZ)X/Qvalueswerecalculatedusing*Offsite (EAB and LPZ) X/Q values were calculated using the PAVAN code consistent with RG 1.145*Control Room and TSC X/Q values were calculated using theARCON96codeconsistentwithRG1194the ARCON96 code consistent with RG 1.194-Meteorological Data*Five years of WCGS site-specific meteorological data from 1/1/2006 through 12/31/2010 was collected*Data recovery for the 5-year period met the 90% recovery criterion of RG 1.23212121 Alternative Source Term*Current licensing basis changes-Revises USAR Chapter 15 dose analysis for 10 accidents (includes the 6 DBAs in RG 1.183)()-New Offsite, Control Room, and TSC atmospheric dispersion factors based on site-specific meteorological data from 2006 through 2010g-Revises the CRHE unfiltered inleakage from 20 scfm to 50 scfm-Revises the Control Building unfiltered inleakage from 300 scfm to 400scfm400 scfm-TS changes to address the update of the accident source term and associated DBAsTSchangestoaddresstheadoptionofTSTF51ARevision22222-TS changes to address the adoption of TSTF-51-A, Revision 222 Alternative Source TermThilSifitiCh*Technical Specification Changes-Definition of DOSE EQUIVALENT I-131*RevisedtoonlyallowtheuseofthedoseconversionfactorsRevised to only allow the use of the dose conversion factors from EPA Federal Guidance Report No. 11 -Definition of DOSE EQUIVALENT XE-133*RevisedtoonlyallowtheuseofthedoseconversionfactorsRevised to only allow the use of the dose conversion factors EPA Federal Guidance Report No. 12 -Specification 5.5.12, "Explosive Gas and Storage TankRadioactivityMonitoringProgram"Tank Radioactivity Monitoring Program*Revises the quantity of radioactivity contained in each gas storage tank to be less than the amount that would result in a whole body exposure limit to 0.1 rem (current limit is 0.5 23 23yp(rem) 23 Alternative Source TermThilSifitiCh(t)*Technical Specification Changes (cont.)-Adoption of TSTF-51-A, Revision 2, "Revise Containment Requirements during Handling qggIrradiated Fuel and Core Alterations"*Allows the elimination of the TS requirements for certain Engineered Safety Feature (ESF) systems to be gy()yOPERABLE, after a sufficient radioactive decay has occurred*Changes were not applied to the TS Section 3.8 Electrical TSs (conservative)242424 Alternative Source TermElVIfLARSti*Enclosure VI of LAR -Sections1 -DESCRIPTION2 -PROPOSED CHANGES3 -BACKGROUND 4 -TECHNICAL ANALYSIS 5 -RG 1.183 CONFORMANCE TABLE6 -RG 1.145 CONFORMANCE TABLE 7 -RG 1.194 CONFORMANCE TABLE 8 -RIS 2006-04 TABLE9 -PROPOSED TS MARKUPS 10 -RETYPED TS PAGES11-PROPOSEDBASESMARKUPS(informationonly)252511 PROPOSED BASES MARKUPS (information only)12 -PROPOSED TRM and BASES MARKUP (information only)13 -PROPOSED USAR CHANGES (information only)25 Alternative Source Term*Followup from the 9/20/12 Pre-Submittal Meeting-Meteorological Data -One gap in the recorded data was due to the data logger failure (5/30/2007 through6/7/2007)through 6/7/2007)-Provide a detailed plant drawing that shows the potential release paths -site plan provided consistent with the guidance in RIS 2006-04 (Enclosure VI of the LAR)26 Alternative Source Term*Followupfrom the 9/20/12 Pre-Submittal Meeting(cont)27 Schedule*Submit LAR to NRCAugust 13, 2013*NRC Acceptance Review (30 days per LIC-109)*Requested Approval DateDecember 15, 2014*Start of Refueling Outage 20January 5, 2015*Cycle 21 StartupFebruary 9, 20152828 SummaryWCNOCitdtbitLAR8/13/13ti*WCNOC intends to submit a LAR on 8/13/13 to revise the WCGS TSs based on:-TransitiontotheWestinghousecoredesignandTransition to the Westinghouse core design and safety analysis methodologies-Transition to the Westinghouse Setpoint Methodology-Full Scope Implementation of the Alternative SourceTerm(AST)Source Term (AST)*Request NRC approval by 12/15/14 to support Cycle 21 operation (Feb. 2015)29*Questions/Comments29