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| number = ML13205A214
| number = ML13205A214
| issue date = 07/30/2013
| issue date = 07/30/2013
| title = 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)
| title = 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
| author name =  
| author name =  
| author affiliation = Wolf Creek Nuclear Operating Corp
| author affiliation = Wolf Creek Nuclear Operating Corp
Line 9: Line 9:
| docket = 05000482
| docket = 05000482
| license number = NPF-042
| license number = NPF-042
| contact person = Lyon C F
| contact person = Lyon C
| case reference number = TAC MF2309
| case reference number = TAC MF2309
| document type = Slides and Viewgraphs, Meeting Briefing Package/Handouts
| document type = Slides and Viewgraphs, Meeting Briefing Package/Handouts
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=Text=
=Text=
{{#Wiki_filter:WCNOC-NRCPre-submittalMeeting WCNOCNRC Presubmittal MeetingCore Design and Safety Analysis Methodology TransitionLicenseAmendmentRequest Transition License Amendment RequestJuly302013 July 30, 2013Wolf Creek Nuclear O perating Corporationpgp1 Meeting AgendaMtiP/Objti
{{#Wiki_filter:WCNOC-NRC WCNOC      NRC Pre-submittal Pre submittal Meeting Core Design and Safety Analysis Methodology Transition License Amendment Request July 30 30, 2013 Wolf Creek Nuclear Operating p      g Corporation p
*Meeting Purpose / Objectives*IntroductionsLicenseAmendmentRequest(LAR)Content
1
*License Amendment Request (LAR) Content*Transition to Westinghouse Analysis Methodologies Methodologies*RTS/ESFAS/LOP DG Start Instrumentation Setpoint Uncertaint y Analysisyy*Alternative Source Term (AST)*LAR Schedule 2*Summary2 Introductions*NRC*WCNOC Team *Westinghouse Support
*Teleconference Attendees 33 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.
Meeting Agenda
Configuration Management updates, regulatory reviews, etc.*WCNOC/Westinghouse (WEC) Interface-On-site WEC staff responsible for core design and safety analysis OnsiteWECstaffmaintainsqualificationsinboththeWCNOCand 44-On-site WEC staff maintains qualifications in both the WCNOC and WEC QA programs. Proper independence is always maintained between the QA programs.
* Meeting M    ti PPurpose / Objectives Obj ti
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
* Introductions
-FullScopeImplementationofAlternativeSource Full 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:
* License Amendment Request (LAR) Content
Attachments:I-EvaluationII-Proposed TS Chan ges (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
* Transition to Westinghouse Analysis Methodologies
*LARcontent(cont)
* RTS/ESFAS/LOP DG Start Instrumentation Setpoint Uncertaintyy Analysis y
*LAR content (cont.)
* Alternative Source Term (AST)
* LAR Schedule
* Summary 2
 
===Introductions===
* NRC
* WCNOC Team
* Westinghouse Support
* Teleconference Attendees 3
 
WCNOC Ownership of Safety Analysis
* WCNOC O    Ownership    hi off ththe S Safety f t AAnalysis l i iis d  demonstrated t t 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 QA
* T Transmittal itt l off Design D i Information I f    ti - referenced f      d tto the th source calculation, design basis document, or identified as a direct input
* Owners Acceptance Review
* Configuration Management updates, regulatory reviews, etc.
* WCNOC/Westinghouse (WEC) Interface
  - On-site WEC staff responsible for core design and safety analysis
  - On-site 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 safety analysis methodologies
  - Transition to Westinghouse Setpoint Methodology
  - Full Scope Implementation of Alternative Source Term (AST) 5
 
License Amendment Request Content
* LAR is consistent with NEI 06-02, License Amendment Request (LAR) Guidelines template Attachments:
I - Evaluation II - Proposed p    TS Changes g ((Mark-up) p)
III - Revised TS pages IV - Proposed TS Bases Changes (info only)
V - Proposed COLR Changes (info only) 6
 
License Amendment Request Content
* LAR content (cont.)
(cont )


==Enclosures:==
==Enclosures:==


I-WCAP-17658-NP-TransitionLicensingReport IWCAP17658NP Transition Licensing ReportII-WCAP-17746-P -Setpoint Methodology for WCGSIII  -WCAP-17746-NPIV-WCAP-17602-P  
I -   WCAP 17658 NP - Transition Licensing Report WCAP-17658-NP II -  WCAP-17746-P - Setpoint Methodology for WCGS III - WCAP-17746-NP IV -   WCAP-17602-P - Setpoint Calculations for WCGS V -   WCAP-17602-NP VI -   Full Scope Implementation of Alternative Source Term VII - CD-ROM containing Meteorological Data VIII - Proprietary Information Affidavit for WCAP-17746-P IX -   Proprietary Information Affidavit for WCAP-17602-P 7
-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 77 TransitiontoWestinghouseAnalysis Transition 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
Transition to Westinghouse Analysis Methodologies
-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 ycle88y8 TransitiontoWestinghouseAnalysis Transition to Westinghouse Analysis MethodologiesOifAliMthdlS
* Core C      D Designi and dS Safety f t Analysis A l i Methodology M th d l
*Overview of Analysis Methodology Scope-Non-LOCA Safety Analyses*RETRAN-02 for Westin ghouse PWRs (WCAP-14882-P-A
  - The Non-LOCA safety analyses were analyzed with g
) g()was used for majority of the analyses*LOFTRAN (WCAP-7907-P-A) was used for some analyses
Westinghouse,  , NRC approved pp     methods
*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 99were used for the Steam Generator Tube Rupture Margin to Overfill and Input to the Dose analyses 9
  - All of the Westinghouse Non-LOCA methods are applicable to the WCGS
TransitiontoWestinghouseAnalysis Transition to Westinghouse Analysis MethodologiesOifAliMthdlS(t)
  - The Containment response analyses of record are not impacted
*Overview of Analysis Methodology Scope (cont.)-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 SBLOCA and LBLOCA analyses of record are not impacted
*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 TransitiontoWestinghouseAnalysis Transition to Westinghouse Analysis Methodologies fOC*Implementation o f the Westinghouse Non-L OCA 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 LimitsLimits*The Minimum Measured Flow (MMF) was relocated to the COLR and revised from 371,000 gpm to 376,000 gpm 1111*The Thermal Design Flow  
  - The Core Design and Fuel Rod Design will be y
-361,200 gpm, replaces the MMF 11 TransitiontoWestinghouseAnalysis Transition 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, and2OPERABLEMSSVswasrevised and 2 OPERABLE MSSVs was revised-TS 5.6.5, COLR*Added WCAP-9272-P-A, the Westinghouse Reload MthdltSifiti565b Methodology 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 parameter 1212 TransitiontoWestinghouseAnalysis Transition to Westinghouse Analysis MethodologiesFllfth9/20/12PSbittlMti
evaluated for each reload cycle 8
*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 InstrumentationSetpointUncertainty Instrumentation Setpoint Uncertainty AnalysisUtitAli*Uncertainty Analysis-Transition from the existing WCNOC Setpoint Methodolo gy to the current Westin ghouse Set point gygpMethodology as applied to WCGS for RTS, ESFAS and LOP DG Start Instrumentation (WCAP-17746-
Transition to Westinghouse Analysis Methodologies
* Overview O      i    off Analysis A l i M    Methodology th d l      S Scope
  - Non-LOCA Safety Analyses
* RETRAN-02 for Westinghouse g        PWRs ((WCAP-14882-P-A))
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 were used d ffor th the Steam St      Generator G      t Tube T b Rupture R t    Margin M i to Overfill and Input to the Dose analyses               9
 
Transition to Westinghouse Analysis Methodologies
* Overview O      i    off Analysis A l i M    Methodology th d l          S Scope ((cont.)
t)
  - DNB Correlations used in the VIPRE-01 DNBR calculations
* The WRB-2 DNB correlation will continue to be used as the primary DNB correlation for the T&H analyses of fuel regions 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 grid
* 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
 
Transition to Westinghouse Analysis Methodologies
* Implementation off the Westinghouse Non-LOCA        OC Safety Analysis Methodology resulted in five changes 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
* The Minimum Measured Flow (MMF) was relocated to the COLR and revised from 371,000 gpm to 376,000 gpm
* The Thermal Design Flow - 361,200 gpm, replaces the MMF 11
 
Transition to Westinghouse Analysis Methodologies
* IImplementation l      t ti off theth Westinghouse W ti h              Non-LOCA N LOCA Safety S f t 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, and 2 OPERABLE MSSVs was revised
    - TS 5.6.5, COLR
* Added WCAP-9272-P-A, the Westinghouse Reload M th d l Methodology tto S Specification ifi ti 5  5.6.5 65b 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
 
Transition to Westinghouse Analysis Methodologies
* Followup F ll          ffrom th the 9/20/12 P      Pre-Submittal S b itt l M    Meeting ti
  - 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
 
Instrumentation Setpoint Uncertainty Analysis
* Uncertainty U      t i t Analysis A l i
  - Transition from the existing WCNOC Setpoint Methodology  gy to the current Westinghouse g      Setpoint p
Methodology 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 replaced with a Nominal Trip Setpoint
* TS Table 3.3.1-1, Overtemperature T, Note 1 and Overpower T, Note 2 14
 
Instrumentation Setpoint Uncertainty Analysis
* Uncertainty U    t i t Analysis A l i ((cont.)  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 existing WCGS Trip Setpoints
* TS 3.3.1, RTS Function 10, Reactor Coolant Flow- Low
* TS 3.3.5, Degraded Voltage Function 15
 
Instrumentation Setpoint Uncertainty Analysis
* TSTF TSTF-493-A, 493 A Revision R i i 4,  4 Option O ti A - Technical T h i l Specification Changes
  - Variation from Option A - Nominal Trip Setpoint specified in the single column format based on the Westinghouse Setpoint Methodology
  - TS changes h        include i l d the th addition dditi off individual i di id l Surveillance Requirement footnotes to the applicable instrumentation Functions in accordance with Option p
A of TSTF-493, Revision 4 16
 
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 Canyon y Power Plant ((DCPP))
submittal of March 7, 2013 (DCL-13-016)
  - WCNOC specific setpoint calculations are provided in WCAP WCAP-17602-P 17602 P (Enclosure IV of LAR) 17
 
Alternative Source Term
* Full F ll S Scope IImplementation l      t ti off the th AST
  - Radiological dose consequences analyses were performed for the accidents specified p                                p        in Regulatory g    y Guide (RG) 1.183 include:
* Main Steamline Break (USAR Section 15.1.5.3)
* Locked Rotor (USAR Section 15.3.3.3) 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
 
Alternative Source Term
* Full Scope Implementation of the AST (cont.)
  - Radiological dose consequences analyses performed for additional accidents not specified in RG 1.183 include:
* Loss of Non-Emergency AC Power (USAR Section 15 2 6 3) 15.2.6.3)
* Letdown Line Break (USAR Section 15.6.2.1)
* Waste Gas Decay Tank Failure (USAR Section 15.7.1)
* Liquid Liq id Waste Tank Fail Failure re (USAR Section 15.7.2) 15 7 2)
  - Dose consequences analyses were performed using version 3.03 of the RADTRAD computer code d
19
 
Alternative Source Term
* Full Scope Implementation of AST (cont.)
  - No changes to the licensing basis EQ dose analyses - maintaining the TID TID-14844 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 Support Center doses (III (III.A.1.2)
A 1 2) 20
 
Alternative Source Term
* Atmospheric Dispersion Factors (X/Q)
  - New X/Q values were calculated
* 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 the ARCON96 code consistent with RG 1  1.194 194
  - 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
 
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 throughg 2010
  - Revises the CRHE unfiltered inleakage from 20 scfm to 50 scfm
  - Revises the Control Building unfiltered inleakage from 300 scfm to 400 scfm
  - TS changes to address the update of the accident source term and associated DBAs
  - TS changes to address the adoption of TSTF TSTF-51-A, 51 A Revision 2 22
 
Alternative Source Term
* Technical T h i lS    Specification ifi ti Ch  Changes
  - Definition of DOSE EQUIVALENT I-131
* Revised to only allow the use of the dose conversion factors from EPA Federal Guidance Report No. 11
  - Definition of DOSE EQUIVALENT XE-133
* 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 Tank Radioactivity Monitoring ProgramProgram
* Revises the quantity of radioactivity contained in each gas storage tank to be less than the amount that would result in a whole bodyy exposure p      limit to  0.1 rem ((current limit is  0.5 rem) 23
 
Alternative Source Term
* Technical T h i lS      Specification ifi ti Ch    Changes ((cont.)  t)
  - Adoption of TSTF-51-A, Revision 2, Revise q
Containment Requirements          during g Handling g Irradiated Fuel and Core Alterations
* Allows the elimination of the TS requirements for certain g
Engineered  Safetyy Feature ((ESF)) systems y      to be OPERABLE, after a sufficient radioactive decay has occurred
* Changes were not applied to the TS Section 3.8 Electrical TSs (conservative) 24
 
Alternative Source Term
* E l Enclosure    VI off LAR - Sections S ti 1 -  DESCRIPTION 2 -  PROPOSED CHANGES 3 -  BACKGROUND 4 -  TECHNICAL ANALYSIS 5 -  RG 1.183 CONFORMANCE TABLE 6 -  RG 1.145 CONFORMANCE TABLE 7 -  RG 1.194 CONFORMANCE TABLE 8 -  RIS 2006-04 TABLE 9 -  PROPOSED TS MARKUPS 10 - RETYPED TS PAGES 11 - PROPOSED BASES MARKUPS (information only) 12 - PROPOSED TRM and BASES MARKUP (information only) 25 13 - PROPOSED USAR CHANGES (information only)
 
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 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


P, Enclosure II of LAR
Alternative Source Term
),)-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 1414 InstrumentationSetpointUncertaintyUtitAli(t)
* Followup from the 9/20/12 Pre-Submittal Meeting (cont) 27
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 existingWCGSTripSetpoints existing WCGS Trip Setpoints*TS 3.3.1, RTS Function 10,  Reactor Coolant Flow-Low*TS 3.3.5, Degraded Voltage Function 1515 InstrumentationSetpointUncertainty Instrumentation Setpoint Uncertainty AnalysisTSTF493ARii4OtiAThil*TSTF-493-A, Revision 4, Option A -Technical Specification Changes
Schedule
-VariationfromOptionA
* Submit LAR to NRC            August 13, 2013
-NominalTripSetpoint Variation from Option A Nominal Trip Setpoint specified in the single column format based on the Westinghouse Setpoint MethodologyTShildthdditifidiidl
* NRC Acceptance Review        (30 days per LIC-109)
-TS changes include the addition of individual Surveillance Requirement footnotes to the applicable instrumentation Functions in accordance with O ption pA of TSTF-493, Revision 4 1616 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 yon Power Plant (DCPP) y()submittal of March 7, 2013 (DCL-13-016)-WCNOC specific setpoint calculations are providedinWCAP
* Requested Approval Date      December 15, 2014
-17602-P(EnclosureIVofLAR) provided in WCAP17602P (Enclosure IV of LAR)17 Alternative Source TermFllSIlttifthAST
* Start of Refueling Outage 20 January 5, 2015
*Full Scope Implementation of the AST-Radiological dose consequences analyses were performed for the accidents s pecified in Re gulatory ppgyGuide (RG) 1.183 include:*Main Steamline Break (USAR Section 15.1.5.3)
* Cycle 21 Startup            February 9, 2015 28
*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 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)
*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 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)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 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 212121 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 DBAsTSchangestoaddresstheadoptionofTSTF 51ARevision2 2222-TS changes to address the adoption of TSTF-51-A, Revision 222 Alternative Source TermThilSifitiCh
Summary
*Technical Specification Changes-Definition of DOSE EQUIVALENT I-131
* WCNOC iintends t d tto submit b it a LAR on 8/13/13 tto revise i
*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
the WCGS TSs based on:
*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 exposure limit to 0.1 rem (current limit is 0.5 23 23yp(rem) 23 Alternative Source TermThilSifitiCh(t)
  - Transition to the Westinghouse core design and safety analysis methodologies
*Technical Specification Changes (cont.)-Adoption of TSTF-51-A, Revision 2, "Revise Containment Re quirements durin g Handling qggIrradiated Fuel and Core Alterations"*Allows the elimination of the TS requirements for certain Engineered Safet y 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 PAGES 11-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 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 2828 SummaryWCNOCitdtbitLAR8/13/13ti
  - Transition to the Westinghouse Setpoint Methodology
*WCNOC intends to submit a LAR on 8/13/13 to revise the WCGS TSs based on:
  - Full Scope Implementation of the Alternative Source Term (AST)
-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)
* Request NRC approval by 12/15/14 to support Cycle 21 operation (Feb. 2015)
Source Term (AST)*Request NRC approval by 12/15/14 to support Cycle 21 operation (Feb. 2015) 29*Questions/Comments 29}}
* Questions/Comments 29}}

Latest revision as of 16:38, 4 November 2019

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 Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 07/30/2013
From:
Wolf Creek
To:
Office of New Reactors
Lyon C
References
TAC MF2309
Download: ML13205A214 (29)
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Text

WCNOC-NRC WCNOC NRC Pre-submittal Pre submittal Meeting Core Design and Safety Analysis Methodology Transition License Amendment Request July 30 30, 2013 Wolf Creek Nuclear Operating p g Corporation p

1

Meeting Agenda

  • Meeting M ti PPurpose / Objectives Obj ti
  • Introductions
  • License Amendment Request (LAR) Content
  • Transition to Westinghouse Analysis Methodologies
  • RTS/ESFAS/LOP DG Start Instrumentation Setpoint Uncertaintyy Analysis y
  • Summary 2

Introductions

  • NRC
  • Westinghouse Support
  • Teleconference Attendees 3

WCNOC Ownership of Safety Analysis

  • WCNOC O Ownership hi off ththe S Safety f t AAnalysis l i iis d demonstrated t t 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 QA

  • T Transmittal itt l off Design D i Information I f ti - referenced f d tto the th source calculation, design basis document, or identified as a direct input
  • Configuration Management updates, regulatory reviews, etc.
  • WCNOC/Westinghouse (WEC) Interface

- On-site WEC staff responsible for core design and safety analysis

- On-site 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 safety analysis methodologies

- Transition to Westinghouse Setpoint Methodology

- Full Scope Implementation of Alternative Source Term (AST) 5

License Amendment Request Content

  • LAR is consistent with NEI 06-02, License Amendment Request (LAR) Guidelines template Attachments:

I - Evaluation II - Proposed p TS Changes g ((Mark-up) p)

III - Revised TS pages IV - Proposed TS Bases Changes (info only)

V - Proposed COLR Changes (info only) 6

License Amendment Request Content

  • LAR content (cont.)

(cont )

Enclosures:

I - WCAP 17658 NP - Transition Licensing Report WCAP-17658-NP II - WCAP-17746-P - Setpoint Methodology for WCGS III - WCAP-17746-NP IV - WCAP-17602-P - Setpoint Calculations for WCGS V - WCAP-17602-NP VI - Full Scope Implementation of Alternative Source Term VII - CD-ROM containing Meteorological Data VIII - Proprietary Information Affidavit for WCAP-17746-P IX - Proprietary Information Affidavit for WCAP-17602-P 7

Transition to Westinghouse Analysis Methodologies

  • Core C D Designi and dS Safety f t Analysis A l i Methodology M th d l

- The Non-LOCA safety analyses were analyzed with g

Westinghouse, , NRC approved pp methods

- All of the Westinghouse Non-LOCA methods are applicable to the WCGS

- 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 y

evaluated for each reload cycle 8

Transition to Westinghouse Analysis Methodologies

  • Overview O i off Analysis A l i M Methodology th d l S Scope

- Non-LOCA Safety Analyses

was used for majority of the analyses

  • Other Codes that were used:

- TWINKLE (WCAP-7979-P-A)

- FACTRAN (WCAP-7908-A)

- Non-LOCA Thermal-Hydraulics (T&H) Safety Analyses

- RETRAN-02 (WCAP-14882-P-A) and WCAP-10698-P-A were used d ffor th the Steam St Generator G t Tube T b Rupture R t Margin M i to Overfill and Input to the Dose analyses 9

Transition to Westinghouse Analysis Methodologies

  • Overview O i off Analysis A l i M Methodology th d l S Scope ((cont.)

t)

- DNB Correlations used in the VIPRE-01 DNBR calculations

  • The WRB-2 DNB correlation will continue to be used as the primary DNB correlation for the T&H analyses of fuel regions 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 grid
  • 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

Transition to Westinghouse Analysis Methodologies

  • Implementation off the Westinghouse Non-LOCA OC Safety Analysis Methodology resulted in five changes 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

  • The Minimum Measured Flow (MMF) was relocated to the COLR and revised from 371,000 gpm to 376,000 gpm
  • The Thermal Design Flow - 361,200 gpm, replaces the MMF 11

Transition to Westinghouse Analysis Methodologies

  • IImplementation l t ti off theth Westinghouse W ti h Non-LOCA N LOCA Safety S f t 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, and 2 OPERABLE MSSVs was revised

- TS 5.6.5, COLR

  • Added WCAP-9272-P-A, the Westinghouse Reload M th d l Methodology tto S Specification ifi ti 5 5.6.5 65b b.
  • Deleted the WCNOC methodologies from Specification 5.6.5 b.

Transition to Westinghouse Analysis Methodologies

  • Followup F ll ffrom th the 9/20/12 P Pre-Submittal S b itt l M Meeting ti

- 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

Instrumentation Setpoint Uncertainty Analysis

  • Uncertainty U t i t Analysis A l i

- Transition from the existing WCNOC Setpoint Methodology gy to the current Westinghouse g Setpoint p

Methodology 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 replaced with a Nominal Trip Setpoint
  • TS Table 3.3.1-1, Overtemperature T, Note 1 and Overpower T, Note 2 14

Instrumentation Setpoint Uncertainty Analysis

  • Uncertainty U t i t Analysis A l i ((cont.) 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 existing WCGS Trip Setpoints

Instrumentation Setpoint Uncertainty Analysis

  • TSTF TSTF-493-A, 493 A Revision R i i 4, 4 Option O ti A - Technical T h i l Specification Changes

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

- TS changes h include i l d the th addition dditi off individual i di id l Surveillance Requirement footnotes to the applicable instrumentation Functions in accordance with Option p

A of TSTF-493, Revision 4 16

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 Canyon y Power Plant ((DCPP))

submittal of March 7, 2013 (DCL-13-016)

- WCNOC specific setpoint calculations are provided in WCAP WCAP-17602-P 17602 P (Enclosure IV of LAR) 17

Alternative Source Term

  • Full F ll S Scope IImplementation l t ti off the th AST

- Radiological dose consequences analyses were performed for the accidents specified p p in Regulatory g y Guide (RG) 1.183 include:

  • Main Steamline Break (USAR Section 15.1.5.3)
  • Locked Rotor (USAR Section 15.3.3.3) 15 3 3 3)
  • Rod Ejection (USAR Section 15.4.8.3)
  • Loss of Coolant Accident (USAR Section 15.6.5.4)
  • Fuel Handling Accident (USAR Section 15.7.4) 18

Alternative Source Term

  • Full Scope Implementation of the AST (cont.)

- Radiological dose consequences analyses performed for additional accidents not specified in RG 1.183 include:

  • Loss of Non-Emergency AC Power (USAR Section 15 2 6 3) 15.2.6.3)
  • Letdown Line Break (USAR Section 15.6.2.1)
  • Waste Gas Decay Tank Failure (USAR Section 15.7.1)
  • Liquid Liq id Waste Tank Fail Failure re (USAR Section 15.7.2) 15 7 2)

- Dose consequences analyses were performed using version 3.03 of the RADTRAD computer code d

19

Alternative Source Term

  • Full Scope Implementation of AST (cont.)

- No changes to the licensing basis EQ dose analyses - maintaining the TID TID-14844 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 Support Center doses (III (III.A.1.2)

A 1 2) 20

Alternative Source Term

  • Atmospheric Dispersion Factors (X/Q)

- New X/Q values were calculated

  • 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 the ARCON96 code consistent with RG 1 1.194 194

- 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

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 throughg 2010

- Revises the CRHE unfiltered inleakage from 20 scfm to 50 scfm

- Revises the Control Building unfiltered inleakage from 300 scfm to 400 scfm

- TS changes to address the update of the accident source term and associated DBAs

- TS changes to address the adoption of TSTF TSTF-51-A, 51 A Revision 2 22

Alternative Source Term

  • Technical T h i lS Specification ifi ti Ch Changes

- Definition of DOSE EQUIVALENT I-131

  • Revised to only allow the use of the dose conversion factors from EPA Federal Guidance Report No. 11

- Definition of DOSE EQUIVALENT XE-133

  • 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 Tank Radioactivity Monitoring ProgramProgram

  • Revises the quantity of radioactivity contained in each gas storage tank to be less than the amount that would result in a whole bodyy exposure p limit to 0.1 rem ((current limit is 0.5 rem) 23

Alternative Source Term

  • Technical T h i lS Specification ifi ti Ch Changes ((cont.) t)

- Adoption of TSTF-51-A, Revision 2, Revise q

Containment Requirements during g Handling g Irradiated Fuel and Core Alterations

  • Allows the elimination of the TS requirements for certain g

Engineered Safetyy Feature ((ESF)) systems y to be OPERABLE, after a sufficient radioactive decay has occurred

  • Changes were not applied to the TS Section 3.8 Electrical TSs (conservative) 24

Alternative Source Term

  • E l Enclosure VI off LAR - Sections S ti 1 - DESCRIPTION 2 - PROPOSED CHANGES 3 - BACKGROUND 4 - TECHNICAL ANALYSIS 5 - RG 1.183 CONFORMANCE TABLE 6 - RG 1.145 CONFORMANCE TABLE 7 - RG 1.194 CONFORMANCE TABLE 8 - RIS 2006-04 TABLE 9 - PROPOSED TS MARKUPS 10 - RETYPED TS PAGES 11 - PROPOSED BASES MARKUPS (information only) 12 - PROPOSED TRM and BASES MARKUP (information only) 25 13 - PROPOSED USAR CHANGES (information only)

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 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

  • Followup from the 9/20/12 Pre-Submittal Meeting (cont) 27

Schedule

  • Submit LAR to NRC August 13, 2013
  • Requested Approval Date December 15, 2014
  • Start of Refueling Outage 20 January 5, 2015
  • Cycle 21 Startup February 9, 2015 28

Summary

  • WCNOC iintends t d tto submit b it a LAR on 8/13/13 tto revise i

the WCGS TSs based on:

- Transition to the Westinghouse core design and safety analysis methodologies

- Transition to the Westinghouse Setpoint Methodology

- Full Scope Implementation of the Alternative Source Term (AST)

  • Request NRC approval by 12/15/14 to support Cycle 21 operation (Feb. 2015)
  • Questions/Comments 29
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