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

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-submittalMeeting WCNOC NRC Pre submittal MeetingCore Design and Safety Analysis Methodology TransitionLicenseAmendmentRequest Transition License Amendment RequestJuly302013 July 30 , 2013Wolf Creek Nuclear O p eratin g Cor p orationpgp 1 Meeting AgendaMtiP/Objti

• M ee ti ng P urpose / Obj ec ti ves*IntroductionsLicenseAmendmentRequest(LAR)Content

• License Amendment Request (LAR) Content*Transition to Westinghouse Analysis Methodologies Methodologies*RTS/ESFAS/LOP DG Start Instrumentation Setpoint Uncertaint y Anal y sis yy*Alternative Source Term (AST)*LAR Schedule 2*Summary 2 Introductions*NRC*WCNOC Team *Westinghouse Support

• Teleconference Attendees 3 3 WCNOC Ownership of Safety AnalysisWCNOCOhifthSftAliidttd

• WCNOC O wners hi p o f th e S a f e t y A na l ys i s i s d emons t ra t e d 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*T ransm itt a l o f D es i gn I n f orma ti on -re f erence d t o th e 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 analysis OnsiteWECstaffmaintainsqualificationsinboththeWCNOCand 4 4-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 safetyanalysismethodologies safety analysis methodologies-Transition to Westinghouse Setpoint Methodology

-FullScopeImplementationofAlternativeSource Full Scope Implementation of Alternative Source Term (AST) 5 5 License Amendment Request Content*LAR is consistent with NEI 06-02, "License Amendment Request (LAR) Guidelines" template Attachments:

Attachments:I-EvaluationII-Pro posed TS Chan g es (Mark-u p) 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-TransitionLicensingReport I WCAP 17658 NP Transition Licensing ReportII-WCAP-17746-P -Setpoint Methodology for WCGSIII -WCAP-17746-NPIV-WCAP-17602-P

-Setpoint Calculations for WCGSV-WCAP-17602-NP VIFullScopeImplementationofAlternativeSourceTerm VI-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-P 7 7 TransitiontoWestinghouseAnalysis Transition to Westinghouse Analysis MethodologiesCDidSftAliMthdl

• C ore D es i gn an d S a f e t y A na l ys i s M e th o d o l ogy-The Non-LOCA safety analyses were analyzed with Westin g house , NRC a pp roved 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 c y cle 8 8 y 8 TransitiontoWestinghouseAnalysis Transition to Westinghouse Analysis MethodologiesOifAliMthdlS

• O verv i ew o f A na l ys i s M e th o d o l ogy S cope-Non-LOCA Safety Analyses*RETRAN-02 for Westin g house 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 dfthStGtTbRtMi 9 9 were use d f or th e St eam G enera t or T u b e R up t ure M arg i n to Overfill and Input to the Dose analyses 9

TransitiontoWestinghouseAnalysis Transition to Westinghouse Analysis MethodologiesOifAliMthdlS(t)

• O verv i ew o f A na l ys i s M e th o d o l ogy S cope (con t.)-DNB Correlations used in the VIPRE-01 DNBR calculations calculations*The WRB-2 DNB correlation will continue to be used as the primary DNB correlation for the T&H analyses of fuel regions abovethefirstmixingvanegrid above 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 10 10 10 TransitiontoWestinghouseAnalysis Transition to Westinghouse Analysis Methodologies f OC*Implementation o f the Westinghouse Non-L OC A Safety Analysis Methodology resulted in five changes tothecurrentWCGSTSs to 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 Limits Limits*The Minimum Measured Flow (MMF) was relocated to the COLR and revised from 371,000 gpm to 376,000 gpm 11 11*The Thermal Design Flow

-361,200 gpm, replaces the MMF 11 TransitiontoWestinghouseAnalysis Transition to Westinghouse Analysis MethodologiesIlttifthWtihNLOCASft*I mp l emen t a tion o f th e W es ti ng h ouse N on-LOCA S a f e t y 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, and2OPERABLEMSSVswasrevised and 2 OPERABLE MSSVs was revised-TS 5.6.5, COLR*Added WCAP-9272-P-A, the Westinghouse Reload MthdltSifiti565b M e th o d o l ogy t o S pec ifi ca ti on 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 parameter 12 12 TransitiontoWestinghouseAnalysis Transition to Westinghouse Analysis MethodologiesFllfth9/20/12PSbittlMti*F o ll owup f rom th e 9/20/12 P re-S u b m itt a l M ee ti ng-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) 13 13 13 InstrumentationSetpointUncertainty Instrumentation Setpoint Uncertainty AnalysisUtitAli*U ncer t a i n t y A na l ys i s-Transition from the existing WCNOC Setpoint Methodolo gy to the current Westin g house Set p oint 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 replacedwithaNominalTripSetpoint replaced with a Nominal Trip Setpoint*TS Table 3.3.1-1, Overtemperature T, Note 1 and Overpower T, Note 2 14 14 14 InstrumentationSetpointUncertaintyUtitAli(t)

Instrumentation Setpoint Uncertainty Analysis*U ncer t a i n t y A na l ys i s (con t.)-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 existingWCGSTripSetpoints existing WCGS Trip Setpoints*TS 3.3.1, RTS Function 10, Reactor Coolant Flow-Low*TS 3.3.5, Degraded Voltage Function 15 15 InstrumentationSetpointUncertainty Instrumentation Setpoint Uncertainty Analysis TSTF 493ARii4OtiAThil*TSTF-493-A , R ev i s i on 4 , O p ti on A -T ec h n i ca l Specification Changes

-VariationfromOptionA

-NominalTripSetpoint Variation from Option A Nominal Trip Setpoint specified in the single column format based on the Westinghouse Setpoint MethodologyTShildthdditifidiidl

-TS c h anges i nc l u d e th e a ddition o f i n di v id ua l Surveillance Requirement footnotes to the applicable instrumentation Functions in accordance with O p tion pA of TSTF-493, Revision 4 16 16 InstrumentationSetpointUncertainty Instrumentation 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 Can y on Power Plant (DCPP) y()submittal of March 7, 2013 (DCL-13-016)-WCNOC specific setpoint calculations are providedinWCAP

-17602-P(EnclosureIVofLAR) provided in WCAP 17602 P (Enclosure IV of LAR)17 A lternative Source TermFllSIlttifthAST

• F u ll S cope I mp l emen t a ti on o f th e AST-Radiological dose consequences analyses were performed for the accidents s p ecified in Re g ulator y ppgy Guide (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) 18 18 18 A lternative Source Term*Full Scope Implementation of the AST (cont.)-Radiological dose consequences analyses performedforadditionalaccidentsnotspecifiedin performed 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)

• Liq u id Waste Tank Fail u re (USAR Section 15.7.2)-Dose consequences analyses were performed using version 3.03 of the RADTRAD computer d co d e 19 19 A lternative Source Term*Full Scope Implementation of AST (cont.)-No changes to the licensing basis EQ dose analysesmaintainingtheTID14844accident analyses -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)20 20 20 A lternative 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 theARCON96codeconsistentwithRG1194 the 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 1.23 21 21 21 A lternative 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

throu g h 2010 g-Revises the CRHE unfiltered inleakage from 20 scfm to 50 scfm-Revises the Control Building unfiltered inleakage from 300 scfm to 400scfm 400 scfm-TS changes to address the update of the accident source term and associated DBAsTSchangestoaddresstheadoptionofTSTF 51ARevision2 22 22-TS changes to address the adoption of TSTF-51-A , Revision 2 22 A lternative Source TermThilSifitiCh

• T ec h n i ca l S pec ifi ca ti on Ch anges-Definition of DOSE EQUIVALENT I-131

• Revisedtoonlyallowtheuseofthedoseconversionfactors Revised to only allow the use of the dose conversion factors from EPA Federal Guidance Report No. 11 -Definition of DOSE EQUIVALENT XE-133

• Revisedtoonlyallowtheuseofthedoseconversionfactors Revised 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 bod y ex p osure limit to 0.1 rem (current limit is 0.5 23 23 yp (rem) 23 A lternative Source TermThilSifitiCh(t)

• T ec h n i ca l S pec ifi ca ti on Ch anges (con t.)-Adoption of TSTF-51-A, Revision 2, "Revise Containment Re q uirements durin g Handlin g qggIrradiated Fuel and Core Alterations"*Allows the elimination of the TS requirements for certain En g ineered Safet y Feature (ESF) s y stems to be gy()yOPERABLE, after a sufficient radioactive decay has occurred*Changes were not applied to the TS Section 3.8 Electrical TSs (conservative) 24 24 24 A lternative Source TermElVIfLARSti*E nc l osure VI o f LAR -S ec ti ons1 -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 PAGES 11-PROPOSEDBASESMARKUPS(informationonly) 25 25 11 PROPOSED BASES MARKUPS (information only)12 -PROPOSED TRM and BASES MARKUP (information only)13 -PROPOSED USAR CHANGES (information only) 25 A lternative 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 A lternative Source Term*Followupfrom the 9/20/12 Pre-Submittal Meeting (cont)27 Schedule*Submit LAR to NRC August 13, 2013*NRC Acceptance Review (30 days per LIC-109)*Requested Approval DateDecember 15, 2014*Start of Refueling Outage 20 January 5, 2015*Cycle 21 StartupFebruary 9, 2015 28 28 SummaryWCNOCitdtbitLAR8/13/13ti

• WCNOC i n t en d s t o su b m it a LAR on 8/13/13 t o rev i se the WCGS TSs based on:

-TransitiontotheWestinghousecoredesignand Transition 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/Comments 29