ML22047A094

Presentation Information for Planned Pre-Application Meeting (Public Meeting)

ML22047A094
Person / Time
Site:	Callaway
Issue date:	02/15/2022
From:	Ameren Missouri
To:	Office of Nuclear Reactor Regulation
Shared Package
ML22047A092	List: ML22047A093 ML22047A094 ML22047A095 ULNRC-06716, Presentation Information for Third Pre-Application Meeting Regarding Use of Framatome Fuel - Affidavit
References
ULNRC-06716
Download: ML22047A094 (28)

Text

Enclosure 1 to U LN RC-06716 Callaway U nit 1 Presentation Information for Planned Pre-Application Meeting (Public Meeting)

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-:E way VQRPre-Stibrniftal Meeting b -

Ameren MISSOURI Callaway Energy Center Callaway VQP Pre-Submittal Meeting Stephanie Banker Ameren Wce President Nuclear Engineering & Support Welcome Meeting Purpose to provide the NRC with information on the upcoming License Amendment Request (LAR) for the Vendor Qualification Program (VQP) of Framatome as a supplier of nuclear fuel to Callaway Energy Center

Team Members Amer en MISSOURI Callaway Energy Center Presenters in Bold Ameren Team Titles Framatome Titles Members Team Members Stephanie Banker Vice President Nuclear Engineering & Rick Williamson Contract Manager Support Tom Gardner Project Manager Steve Meyer Manager, Regulatory Affairs Christy White Technical PM Keith Mills Director, Regulatory Performance Greg Borza Thermal-Hydraulics Tom Elwood Supervising Engineer, Regulatory Affal rs Morris Byram Licensing Jim Kovar Regulatory Affairs Engineer Kevin Segard Neutronics Don Rickard Regulatory Affairs Engineer Michael Harris Thermal-Mechanics Brian Richardson Supervising Engineer, Reactor Tim Lindquist Safety Analysis Engineering I Safety Analysis I Fuels Gordo Wissinger LOCA Analysis Jim Knaup Reactor Engineer I Core Design Pam Reed Mechanical Design Justin Vinyard Reactor Engineer I Fuels Brian Painter Mechanical Analysis Jim Mclnvale Consultant Reactor Engineer Russell Consultant Project Manager Larry

Agenda WAmeren Callaway MISSOURI Energy Center

. Purpose of Meeting I Desired Outcomes Callaway

. Background Callaway

. GAlA Fuel Assembly Design Description Framatome

. Summary of NRC Approved Methods Framatome

. Analyses Framatome

. Technical Specification Changes Callaway

. Schedule Callaway 4

Background Ameren MISSOURI Callaway Eiierg Center

. Callaway LFA I VQP Program for Framatome Fuel Lead Fuel Assemblies (LFA) 4 Fuel Assemblies

. 3 cycles (Cycles 25, 27, 28)

. Non-Limiting Operation (Cycle 25 only)

Vendor Qualification Program (VQP)

Fuel Transition Licensing Submittal VQP Lead Fuel Assemblies 4 Additional Fuel Assemblies

. 3 cycles (Cycles 27, 28, 29)

. Fully Licensed Operation GAlA Fuel Design Based on currently approved methods (with some changes)

Technical Specification changes to add Framatome methods

Fuel Assembly Design Description Ameren Callaway MISSOURI Energy Center (ANP-10342P-A Revision 0, GAlA Fuel Assembly Mechanical Design)

. Standard Reconstitutable Top Nozzle

. M5 Fuel Rods

. M5 GAlA Mixing Grid (6x)

. M5 Intermediate GAlA Mixer (1GM) Grids (3x)

. Alloy 718 HMP Top (Relaxed) and Bottom Spacer Grids Q12 MONOBLOC Guide Tubes (24x)

Q12 Instrument Tube

. GRIP Bottom Nozzle

Summary of Methods (1 of 2) Ameren MISSOURI Callaway Energy Center Functional Area Topical Report ARCADIA (ANP-10297P-A and Neutron ics ANP-1 0297P-A Supp. I P-A, Revision I)

XCOBRA-IIIC (XN-NF-82-21 P-A and XN-NF ThermalHydraulic 75-21 P-A Revision 2),

COBRA-FLX (ANP-10311P-A Revision 1)

Non-LOCA S-RELAP5 (EMF-231 OP-A Revision I)

DNBR Correlation GAlA (ANP-1 0341 P-A)

AREA (ANP-1 O338P-A)

Control Rod Ejection GALILEO (ANP-1O323P-A)

SB LOCA S-RELAP5 (EMF-2328P-A and SI P-A)

LB LOCA S-RELAP5 (EMF-2103P-A Revision 3)

These NRC Approved Methods will be added to the Callaway Tech Specs I COLR

Summary of Methods (2 of2) WAmeren Callaway MISSOURI Energy Center Functional Area Topical Report COPERNIC (BAW-1 0231 P-A),

Fuel Performance Code CROV (BAW-10084PA Revision 3)

External Loads ANP-10337P-A GAlA Mechanical Design ANP-10342P-A BAW-1 0240PA, Cladding BAW-10227P-A Revision I Statistical Setpoints EMF-92-081 P-A Fuel Rod Bow XN-75-32P-A DNB Propagation XN-NF-82-06P-A These NRC Approved Methods will be added to the Callaway Tech Specs I COLR

Recently Approved LARs for Framatome Fuel IOR

. Palo Verde Fuel TransWon ML200310947

. St. Lucie 2 Fuel Transftion ML16063A121

. Calvert Cliffs Fuel Transition ML110390263

. Calvert Cliffs Accident Tolerant Fuel LTAs ML20363A242

. St. Lucie I Extended Power Uprate ML12181A019

. Shearon Harris GAlA Implementation - ML2I 047A470

VQP Analys J es WAmeren Callaway MISSOURI Energy Center

. Analyses were completed in the foIIowng disciplines, using methods d iscussed on the su bseq uent pages:

Fuel rod thermal-mechanical Fuel assembly mechanical Neutronics Thermal-hydraulics Non-LOCA

. Rod Ejection Analysis Method meets new RG I .236 (analysis underway)

LOCA (Large and Small Break)

VQP Analysis Details AmeIBn MISSOURI I CaNaway Energy Center

. Fuel Rod Thermal-Mechanical Analysis I Basis Method Results I Comments Fuel Rod Analyses* ANP-1 0342P-A Acceptable, accounts for BAW-10231P-A lCD BAW-10084P-A, Rev. 3 Cladding Performance I Properties BAW-1 0240P-A Acceptable, M5 cladding BAW-10227P-A, Rev. I Modifications to Approved Methods described on Methods Changes slides

VQP Analysis Details WAmoren Callaway MISSOURI Energy Center

. Fuel Assembly Mechanical AnalysislBasis Method Results Mechanical Compatibility N/A Acceptable, compatible with reactor and resident fuel/components Structural Design Evaluations ANP-10342P-A Acceptable Seismic / LOCA Mechanical Faulted ANP-1 0337P-A and Acceptable, coolable Analysis geometry and RCCA insertion requirements met

VQP Analysis Details WAmeron I Callaway MISSOURI Energy Center

. Neutronics Analysis I Basis Method Results Core Design (ARTEMIS) ANP-10297P-A, Revision 0 Acceptable, Modeled cycles I 3-24 ANP-J 0297P-A, Revision - Created representative 07 Supplement I P-A transition cycles Revision I ) -

Generated power histories, axial shapes and other safety inputs Power Distribution Control* Defined in LAR Acceptable Rod Ejection AREA (ANP-1 0338P-A) Expected to be acceptable, meets requirements from RG (ANP-1 0323P-A) .

236 GALILEO Modifications to Approved Methods described on Methods Changes slides

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VQP Analysis Details Ameren MISSOURI I Callaway Energy Center

. Thermal Hydraulic Analysis I Basis Method Results XCOBRA-IIIC XN-75-21(P)(A) Rev 2 XCOBRA-IIIC is used for setpoint verification and Ch. 15 DNB analysis COBRA-FLX ANP-1 031 1 P-A, Rev I COBRA-FLX is used for thermal-hydraulic compatibility analysis and Ch.

15 DNB analysis.

Mixed Core XN-NF-82-21 (P)(A), Rev I Penalty applied to MDNBR for mixed Departure from cores.

Nucleate (DNB)

Penalty Thermal-Hydraulic N/A Verified that GAlA is thermal-hydraulically Compatibility compatible with the co-resident fuel

VQP Analysis Details Ameren MtSSOURI Callaway Thermal Hydraulic (Cont.)

Analysis I Basis Method Results Fuel Rod Bow XN-NF-75-32P-A No rod bow penalties for fresh fuel Supplements 14*

Gap closure model updated with Defined in LAR BAW-10227 Revision 2, Q3P Revision 0 DNB Propagation XN-NF-82-06P-A Rev I No fuel failure predicted for VQP Will be used to quantify fuel failures if necessary Critical Heat Flux ANP-I 0341 P-A Rev 0* Re-validated i n XCO B RA-IIIC and re Correlation validated with PV-Solver in COBRA-FLX Fuel Centerline EMF-92-081 P-A Rev I

• Cycle specific FCM limit calculated Melt Limit (FCM) BAW-I 0231 P-A Rev I RODEX2 replaced with COPERNIC Modifications to Approved Methods described on Methods Changes slides

VQPAnaIysis Details Ameren MISSOURI Callaway Energy Center

. Thermal Hydraulic (Cont.)

Analysis I Basis Method Results Statistical Setpoints EMF-92-081 P-A Rev I Verified that the existing setpoints for (OTDT/OPDT/CSLL) OTDT, OPDT, and the CSLLs are applicable for GAlA at Callaway Non-LOCA Chapter EMF-92-081 P-A Rev I Acceptance criteria met I 5 Events EMF-231 O(P)(A) Rev I *

(DNB/FCM)

• Modifications to Approved Methods described on Methods Changes slides

VQP Analysis Details Amerefl MISSOURI Callaway Energy Center Non-LOCA Analysis I Basis Method Results Chapter 1 5 Non-LOCA Events EMF-2310P-A Revision 1* Acceptable analyzed:

Decrease in FW Temp Increase in FW Flow Increase in Steam Flow Pre-ScramSLB Post-Scram SLB LossofRCP Flow RCP Shaft Seizure Uncontrolled Bank Withdrawal Dropped Rod Boron Dilution lnadv. Opening of PORV Modifications to Approved Methods described on Methods Changes slides

VQPAnalysis Details Ameren MISSOURI Callaway Energy Center Non-LOCA Cont.)

Analysis I Basis Method Results Chapter 15 Non-LOCA Events EMF-2310P-A Revision 1 Acceptable dispositioned:

Inadvertent opening of a SG relief valve Turbine Trip Loss of non-emergency AC power Partiallossofforcedreactor coolantflow  :

Reactorcoolantpumpshaft break Steam generator tube rupture Modifications to Approved Methods described on Methods Changes slides

VQPAnaIysis Details Am8f8fl MISSOURI Callaway Etierjy Center

. Loss of Coolant Accident LOCA -

Analysis I Basis Method Results Realistic Large Break LOCA EMF-2103P-A Revision 3* Acceptable Small Break LOCA EMF-2328P-A and SI PA* Acceptable RLBLOCA:

Best-estimate uncertainty analysis Included LOOP and no-LOOP cases PCT and Oxidation confirmed to meet limits SBLOCA:

Break spectrum and SI line break analyses SI Line break not limiting Modifications to Approved Methods described on Methods Changes slides

VQP Analysis J Details Ameren MISSOURI Callaway Energy Center

. OtherAnalyses Impacted Mass & Energy Release Fuel Assembly Handling Radiological Consequence GSI-191 (Debris Generation and Transport)

Spent Fuel Pool Criticality

Technical Specification Change Implications AmOrOR

. Cycle 26 starts late May 2022 No Framatome fuel n core

. Cycle 27 starts late October 2023 8 Framatome GAlAAssemblies (4 LFAs and 4 VQP) unrestricted placement Balance of core continues to be Westinghouse-supplied fuel assemblies Presence of Framatome fuel assemblies dictates changes to:

. TS2.1.1 -ReactorCoreSafety Limits

. IS 4.2.1 - Fuel Assemblies

. IS 5.6.5 - Core Operating Limits Report (COLR)

Westinghouse methods continue to govern COLR development

. Framatome evaluations ensure compliance with limits

. New fuel supplier contract to be established late in Cycle 26 or early in Cycle 27

Tech Spec Implications (continued) F&Jcefl

. Cycle 28 Batch load quantities of fresh fuel from selected supplier If Westinghouse is chosen:

. Westinghouse methods continue to govern CQLR development Framatome evaluations ensure compliance with limits

. No additional IS changes are needed (current Power Distribution Specs apply)

. Follow-up LAR after completion of Cycle 29 to remove changes needed for the Framatome assemblies (present in cycles 27, 28 and 29)

If Framatome is chosen:

. Framatome methods will govern CQLR development Westinghouse evaluations ensure compliance with limits

. New Power Distribution Limits Specs (TS 3.2.1 3.2.3 ) need to be in place reflecting Framatome methods

. Follow-up LAR to remove obsolete Westinghouse specifications

Tech Spec Implications (continued) Ameren MISSOURI Callaway Energy Center

. Ameren Missouri will provide a commitment to have only one fuel vendor in order to eliminate concern regarding mixed fresh fuel batches.

. The requested License Amendment ensures the revised TS are fully in place to allow use of Framatome fuel at the time that the contracts are established

. Therefore, this LicenseAmendment Request (LAR) will:

Revise TS 2.1 .1 Reactor Core Safety Limits; TS 4.2.1 Fuel Assemblies; TS 5.6.5 COLR as discussed earlier to accommodate Framatome fuel (needed by 9/30/2023)

Retain the current Westinghouse TS 3.2.x Power Distribution Limits TS and COLR methods

. Required for cycle 27 regardless of vendor; and thereafter, if Westinghouse is selected Add the Framatome TS 3.2.x Power Distribution Limits TS and COLR methods

. Required for cycle 28 if Framatome is selected LCO Applicability will be mutually exclusive to ensure only one vendors methods govern COLR development

. Both vendors may perform evaluations to ensure compliance with limits

Technical Specification (TS) Changes Ameren

. TS 2.1 .1 Reactor Core Safety Limits Revise to add Framatome DNBR and fuel centerline temperature limits Designate Westinghouse Methods-Based as A Designate Framatome Methods-Based as B (Retains Westinghouse-based COLR Methods) (Adopts Framatome-based COLR Methods)

. TS 3.2.IA Heat Flux Hot Channel Factor (FQ(Z))

• TS 3.2.IB Heat Flux Hot Channel Factor (FQ(Z))

. TS 3.2.2A Nuclear Enthalpy Rise Hot Channel

. TS 3.22B Nuclear Enthalpy Rise Hot Channel Factor (FN IIH) Factor (EN IXH)

. TS 3.2.3A Axial Flux Difference (AFD) (RAQC) . TS 3.2.3B Axial Flux Difference (AFD)

. Is 3.2.4 Quadrant Power Tilt Ratio (QPTR)

Revise Required Actions to refer to Surveillance Requirements with A and B designations

. Is 4.2.1- Fuel Assemblies Reviseto referto zirconium clad in lieu ofZircalloy orZlRLO

. TS 5.6.5 Core Operating Limits Report (COLR)

Revise to add Eramatome methods to list of methods used to support COLR

ExemnIW tion Renue, st Ameren MISSOURI Callaway Energy Center

. M5 Cladding I 0 CFR 50.46 and I 0 CFR 50 Appendix K Exemption Request

. SmiIar to M5 cladding exemption requests for other plants Separate TS License Amendment Request

. Currently updating the spent fuel pool criticality analyses for GAlA fuel

. May require change to TS 4.3, Fuel Storage

. May require change to TS 3.7.16, Fuel Storage Pool Boron Concentration, and TS 3.7. 1 7, Spent Fuel Assembly Storage

Schedule Ameren MISSOURI Callaway Energy Center

. LARsubmittal March 30, 2022 Pre-submittal Meeting February 28, 2022 Ameren/Framatome can support NRC Audit, if requested

. Requested NRC approval of LAR September 30, 2023 Supports Fuel Cycle 27, REQ begins October 2, 2023 Questions

I-LU