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

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Subsequent License Renewal Application Annual Update 1 and Supplement 9
ML24060A269
Person / Time
Site: Monticello Xcel Energy icon.png
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)
v • d • e


Text

fl Xcel Energy 2807 West County Road 75 Monticello, 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 (NSPM), d/b/a Xcel Energy to Document Control Desk, 11Monticello Nuclear Generating Plant, Subsequent License Renewal Application Supplement 5 11 dated August 28, 2023, ML23240A695
8) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, 11 Monticello Nuclear Generating Plant, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6

11 dated September 5, 2023, ML23248A474

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 Response to Request for Additional Information Set 3 11 dated 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 2

11 dated October 3, 2023, ML232768433

11) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, 11 Monticello Nuclear Generating Plant, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 11 dated November 9, 2023, ML23313A158
12) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, 11 Monticello Nuclear Generating Plant, Subsequent License Renewal Application Supplement T' dated November 30, 2023, ML23334A147
13) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, 11 Monticello Nuclear Generating Plant, Subsequent License Renewal Application Supplement 8 11 dated January 11, 2024, ML24012A051

Document Control Desk L-MT-24-006 Page 3 In Reference 1, as supplemented by References 2 through 13, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy hereafter "NSPM", submitted a subsequent license renewal application (SLRA) for the Renewed Facility Operating License for Monticello Nuclear Generating Plant (MNGP).

The License Renewal Rule, 10 CFR 54.21(b), requires NSPM to report changes to the Current Licensing Basis (CLB) t hat materially affect the contents of the SLRA, including the Updated Safety Analysis Report (USAR) Supplement. These changes are required to be submitt ed each year following submittal of t he license renewal applicat ion and at least 3 mont hs before scheduled complet ion of the NRC review.

In accordance with the License Renewal Rule, NSPM has performed the annual review of MNGPs CLB changes since SLRA submittal to determine whether any sections of the SLRA were materially 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 Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce 1

Component Material Clari"cations

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 1 of 15 Component Material Clarifications Provide Clarifications to Various Components Replaced During Annual Report Review Period.

Affected SLRA Sections: 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 SLRA Page Numbers: 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 Description of Change:

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 Heating and Ventilation System Components Subject to Aging Management Review Component Type Component Intended Function(s)

Chillers (Reactor Building Chiller Condenser) Shell Side Components Leakage Boundary Chillers (Reactor Building Chiller Condenser) Tube Side Components Leakage Boundary Chillers (Reactor Building Chiller Evaporator) Shell Side Components Brazed Plate Heat Exchanger, Plates Leakage Boundary Chillers (Reactor Building Chiller Evaporator) Brazed Plate Heat Exchanger, Brazing Leakage Boundary SLRA Table 2.3.4-6 on page 2.3-81 is revised as follows:

Table2.3.4-6 Turbine Generator System Components Subject to Aging Management Review Component Type Component Intended Function(s)

Heat Exchanger (Isophase Bus Cooler) Shell Side Components Leakage Boundary Heat Exchanger (Isophase Bus Cooler)

Tubes Leakage Boundary Heat Exchanger (Isophase Bus Cooler E-17A)

Tube Side Components Leakage Boundary Heat Exchanger (Isophase Bus Cooler E-17B) Tube Side Components Leakage Boundary

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 Steel Bolting

Carbon Steel

Carbon Steel (with Internal Coating)

Copper Alloy with 15% Zinc or Less

Copper Alloy with Greater Than 15% Zinc

Glass

Gray Cast Iron

Stainless Steel

Stainless Steel Bolting Aging Effects Requiring Management The following aging effects associated with the HTV System require management:

Cracking

Flow Blockage

Long-Term Loss of Material

Loss of Coating or Liner Integrity

Loss of Material

Loss of Preload

Reduction of Heat Transfer Aging Management Programs 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 and Ducting Components (B.2.3.24)

Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (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:

Table 3.3.2-5: Demineralized Water - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-2191 Item Table 1 Item Notes

Piping, Piping Components Leakage Boundary Copper Alloy with Greater Than 15%

Zinc Air - Indoor Uncontrolled (External)

Cracking External Surfaces Monitoring of Mechanical Components (B.2.3.23)

VIII.H.S-454 3.4.1-106 A

Piping, Piping Components Leakage Boundary Copper Alloy with Greater Than 15%

Zinc Raw Water (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VII.C1.A-727 3.3.1-134 A

Piping, Piping Components Leakage Boundary Copper Alloy with Greater Than 15%

Zinc Raw Water (Internal)

Loss of Material Selective Leaching (B.2.3.21)

VII.C1.A-47 3.3.1-072 A

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:

Table 3.3.2-5: Demineralized Water - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-2191 Item Table 1 Item Notes

Piping, Piping Components Leakage Boundary Elastomer Treated Water (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VII.G.AP-76 3.3.1-096 A

Piping, Piping Components Leakage Boundary Galvanized Steel Air - Indoor Uncontrolled (External)

None None VII.J.AP-13 3.3.1-116 A

Piping, Piping Components Leakage Boundary Galvanized Steel Raw Water (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VII.C1.A-727 3.3.1-134 A

Piping, Piping Components Leakage Boundary Galvanized Steel Raw Water (Internal)

Flow Blockage Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VII.C1.A-727 3.3.1-134 A

Piping, Piping Components Leakage Boundary Galvanized Steel Raw Water (Internal)

Long-Term Loss of Material One-Time Inspection (B.2.3.20)

VII.G.A-532 3.3.1-193 A

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:

Table 3.3.2-11: Heating and Ventilation - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-2191 Item Table 1 Item Notes Chillers - (Reactor Building Chiller Condenser) Shell Side Components Leakage Boundary Carbon Steel (with Internal Coating)

Raw Water (Internal)

Loss of Coating or Liner Integrity Internal Coating/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B.2.3.28)

VII.C1.A-416 3.3.1-138 A

Chillers - (Reactor Building Chiller Condenser) Tube Side Components Leakage Boundary Carbon Steel Air - Indoor Uncontrolled (External)

Gas (Internal)

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

Gas (Internal)

Long-Term Loss of Material None One-Time Inspection (B.2.3.20) None VII.C1.A-532 VII.J.AP-6 3.3.1-193 121 A C

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:

Table 3.3.2-11: Heating and Ventilation - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-2191 Item Table 1 Item Notes Chillers - (Reactor Building Chiller Condenser) Tube Side Components Leakage Boundary Copper Alloy with Greater Than 15%

Zinc Gas (External)

None None VII.J.AP-9 3.3.1-114 C

Chillers - (Reactor Building Chiller Condenser) Tube Side Components Leakage Boundary Copper Alloy with Greater Than 15%

Zinc Raw Water (Internal)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VII.C1.A-473b 3.3.1-160 E, 2 Chillers - (Reactor Building Chiller Condenser) Tube Side Components Leakage Boundary Copper Alloy with Greater Than 15%

Zinc Raw Water (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VII.C1.A-727 3.3.1-134 A

Chillers - (Reactor Building Chiller Condenser) Tube Side Components Leakage Boundary Copper Alloy with Greater Than 15%

Zinc Raw Water (Internal)

Loss of Material Selective Leaching (B.2.3.21)

VII.C1.A-66 3.3.1-072 A

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 8 of 15 Chillers - (Reactor Building Chiller Evaporator) Shell Side Components Brazed Plate Heat Exchanger, Plates Leakage Boundary Carbon Stainless Steel Air - Indoor Uncontrolled Condensation (External)

Loss of Material External Surfaces Monitoring of Mechanical Components (B.2.3.23)

One-Time Inspection (B.2.3.20)

VII.I.A-77 761b 3.3.1-078 232 A C Chillers - (Reactor Building Chiller Evaporator) Brazed Plate Heat Exchanger, Brazing Leakage Boundary Copper Alloy with 15% Zinc or Less Condensation (External)

None None VII.J.AP-144 3.3.1-114 C

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:

Table 3.3.2-11: Heating and Ventilation - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-2191 Item Table 1 Item Notes Chillers - (Reactor Building Chiller Evaporator) Shell Side ComponentsBrazed Plate Heat Exchanger, Plates Leakage Boundary Carbon Stainless Steel Closed Cycle Cooling Water (Internal)

Loss of Material Closed Treated Water Systems (B.2.3.12)

VII.F2.AP-189 VII.C2.A-52 3.3.1-046 049 A C Chillers - (Reactor Building Chiller Evaporator) Shell Side Components Brazed Plate Heat Exchanger, Plates Leakage Boundary Copper Alloy with Greater Than 15%

Zinc Stainless Steel Closed Cycle Cooling Water Condensation (External)

Cracking Closed Treated Water Systems (B.2.3.12)

One-Time Inspection (B.2.3.20)

VII.C2.A-473a VII.I.A-734b 3.3.1-160 205 A C Chillers - (Reactor Building Chiller Evaporator) Shell Side Components Brazed Plate Heat Exchanger, Plates Leakage Boundary Copper Alloy with Greater Than 15%

Zinc Stainless Steel Closed Cycle Cooling Water (External)

Gas (Internal)

Loss of Material None Closed Treated Water Systems (B.2.3.12)

None VII.F2.AP-199 VII.J.AP-22 3.3.1-046 120 C

Chillers - (Reactor Building Chiller Evaporator) Shell Side Components Brazed Plate Heat Exchanger, Brazing Leakage Boundary Copper Alloy with Greater Than 15%

Zinc or Less Closed Cycle Cooling Water (ExInternal)

Loss of Material Selective Leaching (B.2.3.21) Closed Treated Water Systems (B.2.3.12)

VII.F2.AP-43 VII.C2.AP-199 3.3.1-072 3.3.1-046 C

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 10 of 15 Chillers - (Reactor Building Chiller Evaporator) Shell Side Components Brazed Plate Heat Exchanger, Brazing Leakage Boundary Copper Alloy with Greater Than 15%

Zinc or Less Gas (Internal)

None None VII.J.AP-9 3.3.1-114 C

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

Table 3.3.2-11: Heating and Ventilation - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-2191 Item Table 1 Item Notes Insulated Piping, Piping Components Leakage Boundary Carbon Steel Condensation (External)

Loss of Material External Surfaces Monitoring of Mechanical Components (B.2.3.23)

VII.I.A-405a 3.3.1-132 A

Insulated Piping, Piping Components Leakage Boundary Stainless Steel Raw Water (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VII.C1.A-727 3.3.1-134 A

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:

Table 3.3.2-13: Radwaste Solid and Liquid - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-2191 Item Table 1 Item Notes

Piping, Piping Components Structural Integrity (Attached)

Carbon Steel Air - Indoor Uncontrolled (External)

Loss of Material External Surfaces Monitoring of Mechanical Components (B.2.3.23)

VII.I.A-77 3.3.1-078 A

Piping, Piping Components Structural Integrity (Attached)

Carbon Steel Waste Water (Internal)

Long-Term Loss of Material One-Time Inspection (B.2.3.20)

VII.E5.A-785 3.3.1-193 A

Piping, Piping Components Structural Integrity (Attached)

Carbon Steel Waste Water (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VII.E5.AP-281 3.3.1-091 A

Pump Casing (DW Equipment Drain 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)

Leakage Boundary Gray Cast Iron Air - Indoor Uncontrolled (External)

Loss of Material External Surfaces Monitoring of Mechanical Components (B.2.3.23)

VII.I.A-77 3.3.1-078 A

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 12 of 15 Table 3.3.2-13: Radwaste Solid and Liquid - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-2191 Item Table 1 Item Notes Pump Casing (DW Equipment Drain 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)

Leakage Boundary Gray Cast Iron Waste Water (Internal)

Long-Term Loss of Material One-Time Inspection (B.2.3.20)

VII.E5.A-785 3.3.1-193 A

Pump Casing (DW Equipment Drain 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)

Leakage Boundary Gray Cast Iron Waste Water (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VII.E5.AP-281 3.3.1-091 A

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 13 of 15 Table 3.3.2-13: Radwaste Solid and Liquid - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-2191 Item Table 1 Item Notes Pump Casing (DW Equipment Drain 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)

Leakage Boundary Gray Cast Iron Waste Water (Internal)

Loss of Material Selective Leaching (B.2.3.21)

VII.E5.A-547 3.3.1-072 A

Pump Casing (Condensate Pump Area Sump)

Leakage Boundary Stainless Steel Air - Indoor Uncontrolled (External)

Cracking OneTime Inspection (B.2.3.20)

VII.E4.AP-209a 3.3.1-004 A

Pump Casing (Condensate Pump Area Sump)

Leakage Boundary Stainless Steel Air - Indoor Uncontrolled (External)

Loss of Material OneTime Inspection (B.2.3.20)

VII.E4.AP221a 3.3.1006 A

Pump Casing (Condensate Pump Area Sump)

Leakage Boundary Stainless Steel Waste Water (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VII.E5.AP278 3.3.1095 A

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:

Table 3.4.2-6: Turbine Generator - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-2191 Item Table 1 Item Notes Heat Exchanger (Isophase Bus Cooler) Shell Side Components Leakage Boundary Carbon Steel Air - Indoor Uncontrolled (External)

Loss of Material External Surfaces Monitoring of Mechanical Components (B.2.3.23)

VIII.H.S-29 3.4.1-034 A

Heat Exchanger (Isophase Bus Cooler) Shell Side Components Leakage Boundary Carbon Steel Air - Indoor Uncontrolled (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

V.D2.E-29 3.2.1-044 C

Heat Exchanger (Isophase Bus Cooler) Tubes Leakage Boundary Copper Alloy with 15% Zinc or Less Air Indoor Uncontrolled (External)

None None VIII.I.SP-6 3.4.1-054 C

Heat Exchanger (Isophase Bus Cooler) Tubes Leakage Boundary Copper Alloy with 15% Zinc or Less Raw Water (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VIII.E.S-438 3.4.1-091 A

Monticello Nuclear Generating Plant Docket 50-263 L-MT-24-006 1 Page 15 of 15 Table 3.4.2-6: Turbine Generator - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-2191 Item Table 1 Item Notes Heat Exchanger (Isophase Bus Cooler E-17B)

Tube Side Components Leakage Boundary Copper Alloy with 15%

Zinc or Less Air Indoor Uncontrolled (External)

None None VIII.I.SP-6 3.4.1-054 C

Heat Exchanger (Isophase Bus Cooler E-17B)

Tube Side Components Leakage Boundary Copper Alloy with 15%

Zinc or Less Raw Water (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VIII.E.S-438 3.4.1-091 A

Heat Exchanger (Isophase Bus Cooler E-17A)

Tube Side Components Leakage Boundary Carbon Steel Stainless Steel Air - Indoor Uncontrolled (External)

Loss of Material Cracking External Surfaces Monitoring of Mechanical Components (B.2.3.23) OneTime Inspection (B.2.3.20)

VIII.H.S-29 VIII.A.SP118a 3.4.1-034 3.4.1-002 A C Heat Exchanger (Isophase Bus Cooler E-17A)

Tube Side Components Leakage Boundary Carbon Steel Stainless Steel Raw Water (Internal) Air Indoor Uncontrolled (External)

Long-Term Loss of Material One-Time Inspection (B.2.3.20)

VIII.A.S-432 VIII.A.SP-127a 3.4.1-081 3.4.1-003 A C Heat Exchanger (Isophase Bus Cooler E-17A)

Tube Side Components Leakage Boundary Carbon Steel Stainless Steel Raw Water (Internal)

Loss of Material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B.2.3.24)

VIII.E.S-438 3.4.1-091 A

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