L-MT-24-006, Subsequent License Renewal Application Annual Update 1 and Supplement 9

Subsequent License Renewal Application Annual Update 1 and Supplement 9

ML24060A269
Person / Time
Site:	Monticello
Issue date:	02/29/2024
From:	Hafen S Northern States Power Co, Xcel Energy
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
L-MT-24-006
Download: ML24060A269 (1)

Text

2807 West County Road 75 fl Xcel Energy Montice l lo, MN 55362

February 29, 2024 L-MT-24-006 10 CFR 54.17

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22

Subsequent License Renewal Application Annual Update 1 and Supplement 9

References:

1) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, "Monticello Nuclear Generating Plant Docket No. 50-263, Renewal License Number DPR-22 Application for Subsequent Renewal Operating License" dated January 9, 2023, ML23009A353

2) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, "Monticello Nuclear Generating Plant, Subsequent License Renewal Application Supplement l" dated April 3, 2023, ML23094A136

3) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, "Monticello Nuclear Generating Plant, Subsequent License Renewal Application Supplement 2" dated June 26, 2023, ML23177A218

4) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, "Monticello Nuclear Generating Plant, Subsequent License Renewal Application Supplement 3" dated July 11, 2023, ML23193B026

5) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, "Monticello Nuclear Generating Plant, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1" dated July 18, 2023, ML23199A154

6) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, "Monticello Nuclear Power Plant, Subsequent License Renewal Application Response to Request for Additional Information Set 1" dated August 15, 2023, ML23227A175 Document Control Desk L-MT-24-006 Page 2

7) Letter from Northern States Power Company, a Minnesota corporation 11 Monticello (NSPM), d/b/a Xcel Energy to Document Control Desk, Nuclear Generating Plant, Subsequent License Renewal Application

11 dated August 28, 2023, ML23240A695 Supplement 5

8) Letter from Northern States Power Company, a Minnesota corporation

11 Monticello (NSPM), d/b/a Xcel Energy to Document Control Desk, Nuclear Generating Plant, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement

11 dated September 5, 2023, ML23248A474 6

9) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, "Monticello Nuclear Generating Plant, Subsequent License Renewal Application 11 dated Response to Request for Additional Information Set 3 September 22, 2023, ML23265A158

10) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, "Monticello Nuclear Generating Plant, Subsequent License Renewal Application Response to Request for Confirmation of Information Set

11 dated October 3, 2023, ML232768433 2

11) Letter from Northern States Power Company, a Minnesota corporation

11 Monticello (NSPM), d/b/a Xcel Energy to Document Control Desk, Nuclear Generating Plant, Subsequent License Renewal Application 11 dated Response to Request for Additional Information Round 2 -Set 1 November 9, 2023, ML23313A158

12) Letter from Northern States Power Company, a Minnesota corporation

11 Monticello (NSPM), d/b/a Xcel Energy to Document Control Desk, Nuclear Generating Plant, Subsequent License Renewal Application Supplement T' dated November 30, 2023, ML23334A147

13) Letter from Northern States Power Company, a Minnesota corporation

11 Monticello (NSPM), d/b/a Xcel Energy to Document Control Desk, Nuclear Generating Plant, Subsequent License Renewal Application 11 dated January 11, 2024, ML24012A051 Supplement 8 Document Control Desk L-MT-24-006 Page 3

In Reference 1, as supplemented by References 2 through 13, Northern States Powe r Company, a Minnesota co r po r atio n, doing business as Xcel Energy hereafte r " NSPM", subm itted a sub seq u en t l i cense r enewal applicatio n (S LRA) for t he Renewed Facility Ope r ati ng Lice n se fo r Mon t icello Nuclea r Genera t ing Plant (MNGP).

The License Re n ewal Rule, 10 CFR 54.21(b), r equires NSPM to r eport changes t o the Cur ren t Licensing Basis (CLB) t h at mate r ially aff ec t the contents of the SLRA, includi ng the Updated Safety Analysis Report (USAR) Supplement. These changes ar e req u ired to be su bmit t ed each year fo l low in g subm ittal of t h e l icense re n ewa l applica t ion an d at l east 3 mon t hs befo r e scheduled com pl et ion of t he NRC r eview.

In accordance with the License Renewal Rule, NSPM has performed t he annual review of MNGPs CLB changes since SLRA submittal to determine whether any sections of the SLRA were ma t erially affected by these changes. As a result of this review, NSPM has identified no material changes to the SLRA due to CLB changes.

NSPM has identified four plant modifications that have minor impacts for aging management review of several systems due to component additions or changes in component material.

Resulting updates to the MNGP SLRA are described in the Enclosure to this letter.

In the enclosures, changes are described along with the affected section(s) and page number(s) of the docketed SLRA (Reference 1) where the changes are to apply. For clarity, revisions to the SLRA are provided with deleted text by strikethrough and inserted text by bold red underline.

Summary of Commitments

This letter makes no new commitments and no revisions to existing commitments.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on February i).,~ ~, 2024.

Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company-Minnesota

Enclosure (1)

cc: Administrator, Region Ill, USNRC Projec t Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce Enclosure 01

Component Material Clari"cations Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 1 of 15

ComponentMaterialClarifications

ProvideClarificationstoVariousComponentsReplacedDuringAnnualReportReview Period.

AffectedSLRASections: Tables 2.3.3-11 and 2.3.4-6, Section 3.3.2.1.11, Tables 3.3.2-5, 3.3.2-11, 3.3.2-13, and 3.4.2-6

SLRAPageNumbers: 2.3-50, 2.3-81, 3.3-13, 3.3-14, 3.3-122, 3.3-123, 3.3-215, 3.3-216, 3.3-217, 3.3-233, 3.3-255, 3.3-256, 3.3-257, 3.4-104, and 3.4-105

DescriptionofChange:

During a review of plant modifications, changes to in-scope and addition of new components were identified:

New components were installed in the Demineralized Water System. The new instrument valves, calibration taps, and associated fittings for the pressure indicators are brass (copper alloy with greater than 15% zinc), galvanized and stainless steel in a raw water environment.

SLRA Table 3.3.2-5 is being updated to address the changes.

New components were installed in the Heating and Ventilation System. The Reactor Building Chillers were replaced. The original chiller tube side components consisted of copper alloy with greater than 15% zinc. The replacement chiller condenser is a shell and tube heat exchanger with a carbon steel shell and epoxy coated heads and tube sheets. The replacement chiller evaporator is a stainless steel brazed plate heat exchanger. Both the evaporator and condenser inlet headers are stainless steel. The material used to braze the plates together is copper alloy with 15% zinc or less. SLRA Section 3.3.2.1.11, Tables 2.3.3-11 and 3.3.2-11 are being revised to reflect the changes in components, intended function, and material.

It was identified that the Condensate Pump Area Sump Pumps casing material was changed from gray cast iron to stainless steel. The replaced pump casing provides a leakage boundary function and is being added to SLRA Table 3.3.2-13.

The modification review identified that the Heat Exchanger (Isophase Bus Cooler) Tube Side Components originally consisted of copper alloy with 15% zinc or less. A modification replaced the E-17A heat exchanger tube side components with stainless steel. These changes are being added to SLRA Tables 2.3.4-6 and 3.4.2-6. Additionally, it was identified that the Heat Exchanger (Isophase Bus Cooler) is a cooling coil within the isophase bus ducting. The leakage boundary function is thus at the cooling coil tubes and the shell side components do not exist.

The component type Heat Exchanger (Isophase Bus Cooler) Shell Side Components are replaced with Heat Exchanger (Isophase Bus Cooler) Tubes with a leakage boundary intended function and material of copper alloy with 15% zinc or less.

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 2 of 15 SLRA Table 2.3.3-11 on page 2.3-50 is revised as follows:

Table2.3.3-11 HeatingandVentilationSystemComponentsSubjecttoAgingManagementReview

ComponentType ComponentIntendedFunction(s)

Chillers(ReactorBuildingChiller LeakageBoundary Condenser)ShellSideComponents Chillers (Reactor Building Chiller Leakage Boundary Condenser) Tube Side Components Chillers (Reactor Building Chiller Leakage Boundary Evaporator) Shell Side Components BrazedPlateHeatExchanger,Plates MdarrcuP z2cNgeou y-ar5ai3 Mdarrcu scN(N3c yo-i5Nup

)kNtouNeouW yuN%c5 DrNec wcNe

)RgdNi3cuf yuN%ai3

SLRA Table 2.3.4-6 on page 2.3-81 is revised as follows:

Table2.3.4-6 TurbineGeneratorSystemComponentsSubjecttoAgingManagementReview

ComponentType ComponentIntendedFunction(s)

Heat Exchanger (Isophase Bus Cooler) ShellLeakage Boundary Side Components wcNe )RgdNi3cu zhPotdNPc y-P MoorcuW scN(N3c yo-i5Nup

,-.cP Heat Exchanger (Isophase Bus CoolerE-17A)Leakage Boundary Tube Side Components wcNe )RgdNi3cu zhPotdNPc y-P Moorcu )7 scN(N3c yo-i5Nup vByW,-.c Ea5c MontoicieP Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 3 of 15 SLRA Section 3.3.2.1.11 on page 3.3-13 and 3.3-14 is revised as follows:

Materials

The materials of construction for the HTV System components are:

Carbon and Low Alloy SteelBolting CarbonSteel CarbonSteel(withInternalCoating)

Copper Alloy with 15% Zinc orLess Copper Alloy with Greater Than 15%Zinc Glass Gray CastIron StainlessSteel Stainless SteelBolting

AgingEffectsRequiringManagement

The following aging effects associated with the HTV System require management:

Cracking FlowBlockage Long-Term Loss of Material LossofCoatingorLinerIntegrity Loss ofMaterial Loss ofPreload Reduction of HeatTransfer

AgingManagementPrograms

The following AMPs manage the aging effects for the HTV System components:

Bolting Integrity(B.2.3.10)

Closed Treated Water Systems(B.2.3.12)

External Surfaces Monitoring of Mechanical Components(B.2.3.23)

Inspection of Internal Surfaces in Miscellaneous Piping andDucting Components(B.2.3.24)

InternalCoatings/LiningsforIn-ScopePiping,PipingComponents, HeatExchangers,andTanks(B.2.3.28)

One-Time Inspection(B.2.3.20)

Open-Cycle Cooling Water System(B.2.3.11)

Selective Leaching(B.2.3.21)

Water Chemistry(B.2.3.2)

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 4 of 15 SLRA Table 3.3.2-5 on page 3.3-122 is revised as follows:

Table3.3.2-5:DemineralizedWater-SummaryofAgingManagementEvaluation Intended AgingEffect AgingManagement NUREG-2191 Table1 ComponentType Function Material Environment Requiring Program Item Item Notes Management Piping, Leakage Copper Air - Indoor Cracking External Surfaces VIII.H.S-454 3.4.1-106 A Piping Boundary Alloy with Uncontrolled Monitoring of Components Greater (External) Mechanical Than 15% Components Zinc (B.2.3.23 )

Piping,Piping Leakage CopperAlloy RawWater LossofMaterial Inspectionof VII.C1.A-727 3.3.1-134 A Components Boundary withGreater (Internal) InternalSurfacesin Than15% Miscellaneous Zinc PipingandDucting Components (B.2.3.24)

Piping,Piping Leakage CopperAlloy RawWater LossofMaterial SelectiveLeaching VII.C1.A-47 3.3.1-072 A Components Boundary withGreater (Internal) (B.2.3.21)

Than15%

Zinc Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 5 of 15 SLRA Table 3.3.2-5 on page 3.3-123 is revised as follows:

Table3.3.2-5:DemineralizedWater-SummaryofAgingManagementEvaluation Intended AgingEffect AgingManagement NUREG-2191 Table1 ComponentType Function Material Environment Requiring Program Item Item Notes Management Piping, Leakage Elastomer Treated Loss of Material Inspection of InternalVII.G.AP-76 3.3.1-096 A Piping Boundary Water Surfaces in Components (Internal) Miscellaneous Piping and Ducting Components (B.2.3.24 )

Piping, Leakage Galvanized Air - Indoor None None VII.J.AP-13 3.3.1-116 A Piping Boundary Steel Uncontrolled Components (External)

Piping,Piping Leakage Galvanized RawWater LossofMaterial Inspectionof VII.C1.A-727 3.3.1-134 A Components Boundary Steel (Internal) InternalSurfacesin Miscellaneous PipingandDucting Components (B.2.3.24)

Piping,Piping Leakage Galvanized RawWater FlowBlockage Inspectionof VII.C1.A-727 3.3.1-134 A Components Boundary Steel (Internal) InternalSurfacesin Miscellaneous PipingandDucting Components (B.2.3.24)

Piping,Piping Leakage Galvanized RawWater Long-TermLoss One-TimeInspection VII.G.A-532 3.3.1-193 A Components Boundary Steel (Internal) ofMaterial (B.2.3.20)

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 6 of 15 SLRA Table 3.3.2-11 on page 3.3-215 is revised as follows:

Table3.3.2-11:HeatingandVentilation-SummaryofAgingManagementEvaluation Intended AgingEffect AgingManagement NUREG-2191 ComponentType Function Material Environment Requiring Program Item Table1 Notes Management Item Chillers-(Reactor Leakage Carbon RawWater Lossof Internal VII.C1.A-416 3.3.1-138 A BuildingChiller Boundary Steel(with (Internal) Coating Coating/Linings Condenser)ShellSide Internal orLiner forIn-Scope Components Coating) Integrity Piping,Piping Components, HeatExchangers, andTanks (B.2.3.28)

Chillers - (Reactor Leakage Carbon Air - Indoor Loss of External Surfaces VII.I.A-77 3.3.1-078 AC Building Chiller Boundary Steel Uncontrolled Material Monitoring of VII.J.AP-6 121 Condenser) Tube Side (External) None Mechanical Components Components Gas (B.2.3.23 )None (Internal)

Chillers - (Reactor BuildingLeakage Carbon Raw Long-Term One-Time Inspection VII.C1.A-532 3.3.1-193 AC Chiller Condenser)Shell Boundary Steel Water Loss of (B.2.3.20 )None VII.J.AP-6 121 Tube Side Components (Internal) MaterialNone Gas (Internal)

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 7 of 15 SLRA Table 3.3.2-11 on page 3.3-216 is revised as follows:

Table3.3.2-11:HeatingandVentilation-SummaryofAgingManagementEvaluation Intended AgingEffect AgingManagement NUREG-2191 ComponentType Function Material Environment Requiring Program Item Table1 Notes Management Item Chillers - (Reactor BuildingLeakage Copper Gas None None VII.J.AP-9 3.3.1-114 C Chiller Condenser) Tube Boundary Alloy (External)

Side Components with Greater Than 15%

Zinc

Chillers - (Reactor BuildingLeakage Copper Raw Water Cracking Inspection of Internal VII.C1.A-473b 3.3.1-160 E, 2 Chiller Condenser) Tube Boundary Alloy (Internal) Surfaces in Side Components with Miscellaneous Piping Greater and Ducting Than Components (B.2.3.24) 15%

Zinc

Chillers - (Reactor BuildingLeakage Copper Raw Water Loss of Inspection of Internal VII.C1.A-727 3.3.1-134 A Chiller Condenser) Tube Boundary Alloy (Internal) Material Surfaces in Side Components with Miscellaneous Piping Greater and Ducting Than Components (B.2.3.24) 15%

Zinc Chillers - (Reactor BuildingLeakage Copper Raw Water Loss of Selective Leaching VII.C1.A-66 3.3.1-072 A Chiller Condenser) Tube Boundary Alloy (Internal) Material (B.2.3.21 )

Side Components with Greater Than 15%

Zinc Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 8 of 15 Chillers - (Reactor BuildingLeakage Carbon Air - Indoor Loss of External Surfaces VII.I.A-77761b 3.3.1-078 AC Chiller Evaporator) Shell Boundary Stainless Uncontrolled Material Monitoring of 232 Side ComponentsBrazed Steel Condensation Mechanical PlateHeatExchanger, (External) Components (B.2.3.23)

Plates One-TimeInspection (B.2.3.20)

Chillers-(Reactor Leakage Copper Condensation None None VII.J.AP-144 3.3.1-114 C Building Boundary Alloywith (External)

ChillerEvaporator)Brazed 15%Zinc PlateHeatExchanger, orLess Brazing Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 9 of 15 SLRA Table 3.3.2-11 on page 3.3-217 is revised as follows:

Table3.3.2-11:HeatingandVentilation-SummaryofAgingManagementEvaluation Intended AgingEffect AgingManagement NUREG-2191 ComponentType Function Material Environment Requiring Program Item Table1 Notes Management Item Chillers - (Reactor Leakage Carbon Closed Cycle Loss of Closed Treated Water VII.F2.AP-189 3.3.1-046 AC Building Chiller Boundary Stainless Cooling Material Systems (B.2.3.12) VII.C2.A-52 049 Evaporator) Shell Side Steel Water ComponentsBrazedPlate (Internal)

HeatExchanger,Plates Chillers - (Reactor Leakage Copper Closed Cycle Cracking Closed Treated Water VII.C2.A-473a 3.3.1-160 AC Building Chiller Boundary Alloy Cooling Water Systems (B.2.3.12) VII.I.A-734b 205 Evaporator) Shell Side with Condensation One-TimeInspection ComponentsBrazed Greater (External) (B.2.3.20)

PlateHeatExchanger, Than Plates 15%

Zinc Stainless Steel Chillers - (Reactor Leakage Copper Closed Loss of Closed Treated Water VII.F2.AP-199 3.3.1-046 C Building Chiller Boundary Alloy Cycle Material Systems (B.2.3.12) VII.J.AP-22 120 Evaporator) Shell Side with Cooling None None ComponentsBrazed Greater Water PlateHeatExchanger, Than (External)

Plates 15% Gas Zinc (Internal)

Stainless Steel Chillers - (Reactor Leakage Copper Closed Cycle Loss of Selective Leaching VII.F2.AP-43 3.3.1-072 C Building Chiller Boundary Alloy Cooling Water Material (B.2.3.21 )Closed VII.C2.AP-199 3.3.1-046 Evaporator) Shell Side with (ExInternal) TreatedWater ComponentsBrazed Greater Systems(B.2.3.12)

PlateHeatExchanger, Than Brazing 15%

Zincor Less Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 10 of 15 Chillers - (Reactor Leakage Copper Gas (Internal)None None VII.J.AP-9 3.3.1-114 C Building Chiller Boundary Alloy Evaporator) Shell Side with ComponentsBrazed Greater PlateHeatExchanger, Than Brazing 15%

Zincor Less

SLRA Table 3.3.2-11 on page 3.3-233 is revised as follows:

Table3.3.2-11:HeatingandVentilation-SummaryofAgingManagementEvaluation Intended AgingEffect AgingManagement NUREG-2191 ComponentType Function Material Environment Requiring Program Item Table1 Notes Management Item Insulated Piping, Leakage Carbon Condensation Loss of External Surfaces VII.I.A-405a 3.3.1-132 A Piping Components Boundary Steel (External) Material Monitoring of Mechanical Components (B.2.3.23)

InsulatedPiping, Leakage Stainless RawWater Lossof InspectionofInternal VII.C1.A-727 3.3.1-134 A PipingComponents Boundary Steel (Internal) Material Surfacesin MiscellaneousPiping andDucting Components (B.2.3.24)

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 11 of 15 SLRA Table 3.3.2-13 on pages 3.3-255, 3.3-256, and 3.3-257 is revised as follows:

Table3.3.2-13:RadwasteSolidandLiquid-SummaryofAgingManagementEvaluation Intended AgingEffect AgingManagement NUREG-2191 Table1 ComponentType Function Material Environment Requiring Program Item Item Notes Management Piping, Structural Carbon Air - Indoor Loss of External Surfaces VII.I.A-77 3.3.1-078 A Piping Integrity Steel Uncontrolled Material Monitoring of Components (Attached) (External) Mechanical Components (B.2.3.23 )

Piping, Structural Carbon Waste Water Long-Term One-Time Inspection VII.E5.A-785 3.3.1-193 A Piping Integrity Steel (Internal) Loss of (B.2.3.20 )

Components (Attached) Material Piping, Structural Carbon Waste Water Loss of Inspection of Internal VII.E5.AP-281 3.3.1-091 A Piping Integrity Steel (Internal) Material Surfaces in Components (Attached) Miscellaneous Piping andDucting Components (B.2.3.24 )

Pump Casing (DW Leakage Gray Air - Indoor Loss of External Surfaces VII.I.A-77 3.3.1-078 A Equipment Drain Boundary Cast Uncontrolled Material Monitoring of Sump/RB Iron (External) Mechanical Equipment Drain Components Sump/ TB (B.2.3.23 )

Equipment Drain Sump/Condensate Drip Tank/DW Floor Drain Sump/Condensate Pump Area Sump/Condensate Backwash/RB Equipment Drain Tank)

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 12 of 15 Table3.3.2-13:RadwasteSolidandLiquid-SummaryofAgingManagementEvaluation Component Intended AgingEffect AgingManagement NUREG-2191 Table1 Type Function Material Environment Requiring Program Item Item Notes Management Pump Casing (DW Leakage Gray Cast Waste Water Long-Term One-Time Inspection VII.E5.A-785 3.3.1-193 A Equipment Drain Boundary Iron (Internal) Loss (B.2.3.20 )

Sump/RB of Material Equipment Drain Sump/ TB Equipment Drain Sump/Condensate Drip Tank/DW Floor Drain Sump/Condensate Pump Area Sump/Condensate Backwash/RB Equipment Drain Tank)

Pump Casing (DW Leakage Gray Cast Waste Water Loss of Material Inspection of InternalVII.E5.AP-281 3.3.1-091 A Equipment Drain Boundary Iron (Internal) Surfaces in Sump/RB Miscellaneous Equipment Drain Piping and Ducting Sump/ TB Components Equipment Drain (B.2.3.24 )

Sump/Condensate Drip Tank/DW Floor Drain Sump/Condensate Pump Area Sump/Condensate Backwash/RB Equipment Drain Tank)

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 13 of 15 Table3.3.2-13:RadwasteSolidandLiquid-SummaryofAgingManagementEvaluation Component Intended AgingEffect Aging NUREG-2191 Table1 Type Function Material Environment Requiring Management Item Item Notes Management Program Pump Casing (DW Leakage Gray Cast Waste Water Loss of MaterialSelective Leaching VII.E5.A-547 3.3.1-072 A Equipment Drain Boundary Iron (Internal) (B.2.3.21 )

Sump/RB Equipment Drain Sump/ TB Equipment Drain Sump/Condensate Drip Tank/DW Floor Drain Sump/Condensate Pump Area Sump/Condensate Backwash/RB Equipment Drain Tank)

PumpCasing Leakage Stainless Air-Indoor Cracking OneTime VII.E4.AP-209a 3.3.1-004 A (Condensate Boundary Steel Uncontrolled Inspection PumpArea (External) (B.2.3.20)

Sump)

PumpCasing Leakage Stainless Air-Indoor Lossof OneTime VII.E4.AP221a 3.3.1006 A (Condensate Boundary Steel Uncontrolled Material Inspection PumpArea (External) (B.2.3.20)

Sump)

PumpCasing Leakage Stainless WasteWater Lossof Inspectionof VII.E5.AP278 3.3.1095 A (Condensate Boundary Steel (Internal) Material InternalSurfacesin PumpArea Miscellaneous Sump) PipingandDucting Components (B.2.3.24)

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 14 of 15 SLRA Table 3.4.2-6 on pages 3.4-104 and 3.4-105 is revised as follows:

Table3.4.2-6:TurbineGenerator-SummaryofAgingManagementEvaluation Component Intended AgingEffect Aging NUREG-2191 Table1 Type Function Material Environment Requiring Management Item Item Notes Management Program Heat Exchanger Leakage Carbon Air - Indoor Loss of Material External VIII.H.S-29 3.4.1-034 A (Isophase Bus Boundary Steel Uncontrolled Surfaces Cooler) Shell Side (External) Monitoring of Components Mechanical Components (B.2.3.23 )

Heat Exchanger Leakage Carbon Air - Indoor Loss of Material Inspection of V.D2.E-29 3.2.1-044 C (Isophase Bus Boundary Steel Uncontrolled Internal Surfaces Cooler) Shell (Internal) in Miscellaneous Side Piping and Components Ducting Components (B.2.3.24 )

HeatExchanger Leakage Copper AirIndoor None None VIII.I.SP-6 3.4.1-054 C (IsophaseBus Boundary Alloywith Uncontrolled Cooler)Tubes 15%Zinc (External) orLess HeatExchanger Leakage Copper RawWater Lossof Inspectionof VIII.E.S-438 3.4.1-091 A (IsophaseBus Boundary Alloywith (Internal) Material Internal Cooler)Tubes 15%Zinc Surfacesin orLess Miscellaneous Pipingand Ducting Components (B.2.3.24)

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 15 of 15 Table3.4.2-6:TurbineGenerator-SummaryofAgingManagementEvaluation Component Intended AgingEffect Aging NUREG-2191 Table1 Type Function Material Environment Requiring Management Item Item Notes Management Program HeatExchanger Leakage CopperAlloy AirIndoor None None VIII.I.SP-6 3.4.1-054 C (IsophaseBus Boundary with15% Uncontrolled CoolerE-17B) ZincorLess (External)

TubeSide Components HeatExchanger Leakage CopperAlloy RawWater Lossof Inspectionof VIII.E.S-438 3.4.1-091 A (IsophaseBus Boundary with15% (Internal) Material InternalSurfacesin CoolerE-17B) ZincorLess Miscellaneous TubeSide PipingandDucting Components Components (B.2.3.24)

Heat Exchanger Leakage Carbon Steel Air - Indoor Loss of Material External Surfaces VIII.H.S-29 3.4.1-034 AC (Isophase Bus Boundary Stainless Uncontrolled Cracking Monitoring of VIII.A.SP118a 3.4.1-002 CoolerE-17A) Steel (External) Mechanical Tube Side Components Components (B.2.3.23 )OneTime Inspection (B.2.3.20)

Heat Exchanger Leakage Carbon Steel Raw Water Long-Term One-Time Inspection VIII.A.S-432 3.4.1-081 AC (Isophase Bus Boundary Stainless (Internal)Air Loss of (B.2.3.20 ) VIII.A.SP-127a 3.4.1-003 CoolerE-17A) Steel Indoor Material Tube Side Uncontrolled Components (External)

Heat Exchanger Leakage Carbon Steel Raw Loss of Material Inspection of VIII.E.S-438 3.4.1-091 A (Isophase Bus Boundary Stainless Water Internal Surfaces in CoolerE-17A) Steel (Internal) Miscellaneous Tube Side Piping and Ducting Components Components (B.2.3.24 )