ML24095A207

Update to Subsequent License Renewal Application (SLRA) Supplement 1

ML24095A207
Person / Time
Site:	Summer
Issue date:	04/01/2024
From:	James Holloway Dominion Energy South Carolina
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
24-101
Download: ML24095A207 (1)

Text

Dominion Energy South Carolina, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Energy.com April 1, 2024 United States Nuclear Regulatory Commission Attention: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 DOMINION ENERGY SOUTH CAROLINA, INC.

VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 Dominion Energy~

Serial No.:

NRA/SS:

Docket No.:

License No.:

10 CFR 50 10 CFR 51 10 CFR 54 24-101 RO 50-395 NPF-12 UPDATE TO SUBSEQUENTLICENSE RENEWAL APPLICATION (SLRA)

SUPPLEMENT 1 By letter dated August 17, 2023 [Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML23233A179], Dominion Energy South Carolina, Inc. (Dominion, Dominion Energy South Carolina, or DESC) submitted an application for the subsequent license renewal of Renewed Facility Operating License No. NPF-12 for Virgil C. Summer Nuclear Station (VCSNS) Unit 1.

Beginning on November 6, 2023, the NRC staff conducted an Aging Management Audit as part of their review of the VCSNS SLRA. As a result of discussions with the NRC staff throughout the audit, additional information necessary for the NRC staff to complete their technical review is included in updates to the SLRA. provides a description of each of the topics that require the SLRA to be supplemented and identifies the affected SLRA section and/or table.

includes mark-ups of affected SLRA sections and/or tables being supplemented, as described in Enclosure 1.

To aid the staff in assessing changes, Enclosure 2 shows new text as underlined and deleted text as lined-through. Please note that change bars are shown for new text but are not shown for deleted text.

Serial No.: 24-101 Docket No.: 50-395 Page 2 of 6 If there are any questions regarding this submittal or if additional information is needed, please contact Mr. Keith Miller at (804) 273-2569.

Sincerely, r James E. Holloway Vice President - Nuclear Engineering and Fleet Support -------------,

COMMONWEAL TH OF VIRGINIA COUNTY OF HENRICO KATHRYN HILL BARRET NOTARY PUBLIC I

COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES JANUARY 31, 202fl The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by James E. Holloway, who is Vice President - Nuclear Engineering and Fleet Support of Dominion Energy South Carolina, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document on behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this__!_.§!_ day of Av"'\\

, 2024.

My Commission Expires: 'J"' GLn'-1 ct Yi

~ \\ 1 2Ji28 Commitments made in this letter:

The Licensee Commitments identified in Table A4.0-1 of Appendix A, FSAR Supplement, are proposed to support approval of the subsequent renewed operating licenses and may change during the NRC review period.

Enclosures:

Topics that Require a SLRA Supplement -

SLRA Mark-ups - Supplement 1

cc:

U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector Virgil C. Summer Nuclear Station Ms. Lauren Gibson NRC Branch Chief U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 11 E11 11555 Rockville Pike Rockville, Maryland 20852-2738 Ms. Kim Conway

• NRC Project Manager U.S. Nuclear Regulatory Commission Two White Flint North Mail Stop A 1 OM 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. Ted Smith NRC Branch Chief U.S. Nuclear Regulatory Commission Two White Flint North Mail Stop B 72M 11555 Rockville Pike Rockville, Maryland 20852-2738 Ms. Marieliz Johnson NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 7 E 1 11555 Rockville Pike Rockville, Maryland 20852-2738 Serial No.: 24-101 Docket No.: 50-395 Page 3 of 6

Mr. G. Edward Miller NRC Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop O-9E3 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. Gregory Lindamood Santee Cooper-Nuclear Coordinator Virgil C. Summer Nuclear Station P. 0. Box 88 Jenkinsville, SC 29065 Stephen R. Pelcher Santee Cooper - Deputy General Counsel One Riverwood Drive Moncks Corner, SC 29461 Elizabeth Johnson Director, Historical Services, D-SHPO South Carolina Department of Archives and History 8301 Parklane Road Columbia, SC 29233 Johnathan Leader State Archaeologist South Carolina Institute of Archaeology and Anthropology 1321 Pendleton St, 1st Floor, Suite 16 Columbia, SC 29208 Fran Marshall Director, Office of Environmental and Public Health Serial No.: 24-101 Docket No.: 50-395 Page 4 of 6 South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Myra Reese Director, Office of Environmental Affairs South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201

Serial No.: 24-101 Docket No.: 50-395 Nate Haber Director Bureau of Water - Water Quality Division South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Lorianne Riggin Director of Environmental Programs South Carolina Department of Natural Resources 1000 Assembly Street Columbia, SC 29201-3117 Duane Parrish Director, South Carolina Parks, Recreation, and Tourism 1205 Pendleton St. Ste 248 Columbia, SC 29201 Florence Belser Chair, Public Service Commission of South Carolina 101 Executive Center Drive #100 Columbia, SC 29210 Christy Hall Secretary of Transportation South Carolina Department of Transportation 955 Park Street Columbia, SC 29201 Kim Stenson Director, South Carolina Emergency Management Division 2779 Fish Hatchery Rd West Columbia, SC 29172 Rhonda Thompson Chief, Bureau of Air Quality South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Renee Shealy Chief, Bureau of Environmental Health Services South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Page 5 of 6

Serial No.: 24-101 Docket No.: 50-395 Henry Porter Chief, Bureau of Land and Waste Management South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Jennifer Hughes Chief, Bureau of Water South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Elizabeth von Kolnitz Chief, Office of Ocean & Coastal Resource Management South Carolina Department of Health and Environmental Control 1362 McMillan Avenue North Charleston, SC 29405 Page 6 of 6

Supplement 1 VCS SLRA Serial No.: 24-101 Docket No: 50-395 TOPICS THAT REQUIRE A SLRA SUPPLEMENT Dominion Energy South Carolina, Inc.

(Dominion Energy South Carolina, or DESC)

Virgil C. Summer Nuclear Station Unit 1

Supplement 1 VCS SLRA Serial No.: 24-101 Page 2 of 14 The following twenty-three topics require the SLRA to be supplemented:

1.

10 CFR 54.4(a)(3) - Regulated Events: Station Blackout Corrections

2.

Fire Service System: Piping Material Addition for Incipient Fire Detectors

3.

Diesel Generator Services and Fire Service Systems: Flame Arrestor Function and Fire Door Reference Corrections

4.

Fire Service System: Clarification - Fire Pump Engine is Active

5.

Fire Service System: Aging Management Review (AMR) Standard Note and Component Type Corrections

6.

Fire Protection: Provide Clarifying Discussion

7.

Steel Elements Component Type: Intended Function Correction

8.

Scoping and Screening Results: Electrical and Instrumentation and Control Systems

9.

Steam Generators: Updating Versions of Industry Documents

10. Correction to Editorial Error in Table 3.1.1

11. Further Evaluation 3.1.2.2.11, Cracking due to Primary Water Stress Corrosion Cracking

12. Clarification for Embedded Piping That is Not Potentially Exposed to Groundwater

13. Correction to Further Evaluation Discussion on Loss of Material in Piping Exposed to Concrete

14. Multiple Systems: Notes for Components Not Credited with Flow Delivery

15. Domestic Water System: Component and Environment Additions

16. Nuclear Sampling System: Cooling Loop Not Managed by Closed Treated Water Systems Program

17. Fatigue Management: RV Outlet Nozzle Allowable End-Of-Evaluation Flaw Size Correction

18. PWR Vessel Internals: Component Inspection Scope and Categories Enhancements

19. Pressurized Thermal Shock RTPTS Value Correction

20. Enhancement for the Flux Thimble Tube Inspection Program

21. Reactor Building Polar Crane: Clarification of Operating Experience Summary

22. Scoping and Screening Results: Electrical and Instrumentation and Control Systems

23. Fatigue Management: ASME Code,Section XI, Appendix L Weld Identification Correction

Supplement 1 VCS SLRA Serial No.: 24-101 Page 3 of 14 The following twenty-three topics require the SLRA to be supplemented:

1. 10 CFR 54.4(a)(3) - Regulated Events: Station Blackout Corrections SLRA Section 2.1.3.4, 10 CFR 54.4(a)(3) - Regulated Events, provides the components that are in scope of license renewal (LR) for recovery from a station blackout (SBO).

Figure 2.1-1, SBO Offsite Recovery Paths, shows the SBO recovery path from the offsite power system.

The third, fourth, and fifth bullets on SLRA Page 2-11 provide a discussion of the electrical components associated with recovery of these offsite power sources. A correction is being made to clarify that the Engineered Safety Features transformer XTF-4 is connected to the XSW-1DX bus, and the Emergency Auxiliary Transformer XTF-31 is connected to the XSW-1DA and XSW-1DB busses.

A typographical error is being corrected in the fourth and fifth bullets on SLRA Page 2-11, by changing XSB-1DB to XSW-1DB.

Figure 2.1-1 on Page 2-13 is being clarified with a note to state that Cubicle 17 in Bus XSW-1DB does not contain a breaker.

Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to incorporate corrections of electrical component descriptions, as shown in the following:

2. Fire Service System: Piping Material Addition for Incipient Fire Detectors The fire service system includes Piping, piping components (sample tubing) made of polymeric material for the incipient fire detectors. These components are subject to aging management but were not addressed in the SLRA.

Based on the above, the SLRA is supplemented as shown in Enclosure 2, to address the polymeric incipient fire detector Piping, piping components, as shown in the following:

SLRA Section SLRA Table 2.3.3.13 3.3.1 Item 263 3.3.2.1.13 3.3.2-13 SLRA Section SLRA Figure 2.1.3.4 (Station Blackout) 2.1-1

Supplement 1 VCS SLRA Serial No.: 24-101 Page 4 of 14

3. Diesel Generator Services and Fire Service Systems: Flame Arrestor Function and Fire Door Reference Corrections SLRA Tables 2.3.3-10 and 3.3.2-10 for the diesel generator services system, and Tables 2.3.3-13 and 3.3.2-13 for the fire service system indicate that the Flame arrestor component type has a pressure boundary (PB) intended function. These components should have a fire barrier (FB) function instead.

Additionally, SLRA Section 2.3.3.13 (Fire Service) system evaluation boundary incorrectly states that fire doors are addressed in the structural commodities section. Fire doors are addressed in the structural sections for their associated buildings.

Based on the above, the SLRA is supplemented as shown in Enclosure 2, to change the PB intended function to FB for the Flame arrestor component type, and to correct the fire door reference, as shown in the following:

SLRA Section SLRA Table 2.3.3.13 2.3.3-10 2.3.3-13 3.3.2-10 3.3.2-13

4. Fire service system: Clarification - Fire Pump Engine is Active The SLRA did not clearly state that the diesel engine associated with the engine-driven fire pump is an active component (per NUREG-2192, Table 2.1-6, item 55).

Based on the above, the SLRA is supplemented as shown in Enclosure 2, to add clarification text to the fire service system boundary description, as shown in the following:

SLRA Section 2.3.3.13

5. Fire Service System: AMR Standard Note and Component Type Corrections The SLRA assigned GALL item VII.G.A-403 (for sprinkler heads) to a row for component type Strainer element using note A. This note indicates that the component is consistent with NUREG-2191 item for component, material, environment, and aging effect.

Supplement 1 VCS SLRA Serial No.: 24-101 Page 5 of 14 However, note C should have been used since the component is different, but materials, environment, aging effect, and program are consistent with NUREG-2191.

Additionally, the water suppression within in-scope charcoal filter banks uses cone spray nozzles (which are not sprinkler heads), but the SLRA did not include component type Spray nozzle in Tables 2.3.3-13 and 3.3.2-13.

Based on the above, the SLRA is supplemented as shown in Enclosure 2, to correct the affected strainer element note and to add a new Spray nozzle component, as shown in the following:

SLRA Table 2.3.3-13 3.3.2-13

6. Fire Protection: Provide Clarifying Discussions A. Miscellaneous Structural Commodities: Section 2.4.1.14 Correction The System Evaluation Boundary discussion in SLRA Section 2.4.1.14, Miscellaneous Structural Commodities, states that fire damper assemblies are evaluated in the fire protection system. As indicated in SLRA Section 2.3.3.1, Air Handling and Local Ventilation and Cooling, the evaluation boundary for those systems includes fire damper assemblies.

The System Evaluation Boundary discussion in SLRA Section 2.4.1.14 is revised to state that fire damper assemblies are evaluated in the air handling system.

Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to correct the System Evaluation Boundary description as described above, as shown in the following:

SLRA Section 2.4.1.14 B. Fireproofing and Fire Barriers Component Type: Intended Function Correction SLRA Tables 2.4.1-14 and 3.5.2-14 for Miscellaneous Structural Commodities indicate that the Fireproofing and fire barriers component type has a fire barrier (FB), enclosure protection (EN), and flood barrier (FLB) intended functions. Only the FB intended

Supplement 1 VCS SLRA Serial No.: 24-101 Page 6 of 14 function should have been assigned to the Fireproofing and fire barriers component type.

Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to delete the enclosure protection (EN) and flood barrier (FLB) intended functions from the Fireproofing and fire barriers component type, as shown in the following:

SLRA Table 2.4.1-14 3.5.2-14 C. Fireproofing and Fire Barriers: AMR Correction - Materials to Secure Fire Barriers/Fire Wraps Fireproofing and fire barriers are addressed as part of Miscellaneous Structural Commodities. However, the materials used to secure fire barriers/fire wraps to the components were not addressed. SLRA Section 3.5.2.2.2.4, Table 3.5.1, and Table 3.5.2-14 are being updated to address the materials used to secure fire barriers/fire wraps to the components within the Fire Protection Program.

Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to address the materials used to secure fire barriers/fire wraps to the components, as shown in the following:

SLRA Section SLRA Table 3.5.2.2.2.4 3.5.1 3.5.2-14 D. Fireproofing and Fire Barriers: AMR Correction - Gypsum Boards The material gypsum, which is a credited fire barrier material, was not identified as included for aging management review. SLRA Section 3.5.2.1.14 and Table 3.5.2-14 is being updated to include the gypsum fire barrier material.

Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to address the fire barrier material gypsum, as shown in the following:

SLRA Section SLRA Table 3.5.2.1.14 3.5.2-14

Supplement 1 VCS SLRA Serial No.: 24-101 Page 7 of 14 E. Fireproofing and Fire Barriers: AMR Correction - Seismic Gap Covers Some fire barrier configurations include seismic gap covers, but seismic gap covers were not identified as included for aging management review. SLRA Section 2.4.1.14, Table 2.4.1-14, and Table 3.5.2-14 are being updated to address seismic gap covers.

Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to address the seismic gap covers, as shown in the following:

SLRA Section SLRA Table 2.4.1.14 2.4.1-14 3.5.2-14

7. Steel Elements Component Type: Intended Function Correction For several buildings, the SLRA tables indicate that the Steel elements component type has a fire barrier (FB) intended function. The FB intended function should not have been assigned to the Steel elements component type for the buildings.

Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to delete the FB intended function from the Steel elements component type for the applicable buildings, as shown in the following SLRA tables:

SLRA Table 2.4.1-1 3.5.2-1 2.4.1-2 3.5.2-2 2.4.1-6 3.5.2-6 2.4.1-7 3.5.2-7 2.4.1-12 3.5.2-12 2.4.1-13 3.5.2-13 2.4.1-20 3.5.2-20

8. Scoping and Screening Results: Electrical and Instrumentation and Control Systems SLRA Section 2.5, Identification of Electrical Components and Commodities, discusses grouping electrical and I&C component types into commodities. NUREG-2192 (Standard

Supplement 1 VCS SLRA Serial No.: 24-101 Page 8 of 14 Review Plan for SLR) Table 2.1-2, Specific Staff Guidance on Scoping, recommends that the applicant describe the basis for the commodity groupings.

To be consistent with the guidance in NEI 17-01 (Industry Guideline for Implementing the Requirements of 10 CFR Part 54 for Subsequent License Renewal) and in NUREG-2192, a statement is added to SLRA Section 2.5 that describes the basis for the commodity groupings.

SLRA Table 2.2-1, provides the list of systems and clarifies whether they are in the scope of subsequent license renewal. System electrical power (EP), which was already listed in the mechanical system section, was listed in the electrical and I&C section as not within the scope of subsequent license renewal. As stated in the mechanical section of Table 2.2-1, System EP is an inactive system in the plant asset management system (PAMS) database. To correct this inconsistency, the line for System EP on SLRA Page 2-47 is deleted.

Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to revise the electrical and I&C scoping and screening results as shown in the following:

SLRA Section SLRA Table 2.5 2.2-1

9. Steam Generators: Updating Versions of Industry Documents An exception is being added to the Steam Generators program to utilize updated versions of industry documents for the following topics listed in GALL-SLR Section XI.M19:

PWR Primary-to-Secondary Leak Guidelines (EPRI 3002018267)

Steam Generator Integrity Assessment Guidelines (EPRI 3002020909)

Steam Generator In-Situ Pressure Test Guidelines (EPRI 3002007856)

Based on the above, revisions are being made in the following areas of the SLRA, as shown in Enclosure 2, to add the exception:

SLRA Section SLRA Table B2.1.10 3.1.1 3.1.2-4 B2-1

Supplement 1 VCS SLRA Serial No.: 24-101 Page 9 of 14

10. Correction to Editorial Error in Table 3.1.1 The Discussion column for Item 3.1.1-068 in SLRA Table 3.1.1 refers to nickel alloy tube support plates in the Reactor Vessel, Internals, and Reactor Coolant System. However, the Aging Effect/Mechanism column for Item 3.1.1-068 addresses carbon steel tube support plates. The editorial error is being corrected.

Based on the above, the SLRA is supplemented as shown in Enclosure 2, to change nickel alloy tube support plates to carbon steel tube support plates, as shown in the following:

SLRA Table 3.1.1 Item 3.1.1-068

11. Further Evaluation 3.1.2.2.11, Cracking due to Primary Water Stress Corrosion Cracking SLRA Section 3.1.2.2.11 states that steam generator divider plate assemblies and associated welds are Alloy 690 materials. However, the Steam Generator aging management program implementing documents state that the weld materials are Alloy 600 material.

Based on the above, the SLRA is supplemented as shown in Enclosure 2, to revise the Further Evaluation discussion to reflect the correct materials, as shown in the following:

SLRA Section 3.1.2.2.11

12. Clarification for Embedded Piping That is Not Potentially Exposed to Groundwater SLRA Table 3.3.1, Item 107 is revised to clarify that stainless steel piping exposed to concrete that is not potentially exposed to groundwater (i.e., interior / above ground concrete) is addressed in Table 3.3.1, Item 202.

Based on the above, the SLRA is supplemented as shown in Enclosure 2, to add clarification to Table 3.3.1 Item 107, as shown in the following:

Supplement 1 VCS SLRA Serial No.: 24-101 Page 10 of 14 SLRA Table 3.3.1-107

13. Correction to Further Evaluation Discussion on Loss of Material in Piping Exposed to Concrete The Discussions for AMR Items 3.1.1-105 and 3.1.1-115 in SLRA Table 3.1.1 state that there are no in-scope steel piping, piping components exposed to concrete in the Reactor Vessel, Internals, and Reactor Coolant System, and that there are no in-scope stainless steel piping, piping components exposed to concrete in the Reactor Vessel, Internals, and Reactor Coolant System, respectively. However, the corresponding Further Evaluation discussion in SLRA Section 3.1.2.2.15 only addresses steel piping or piping components exposed to concrete. This discussion should also address stainless steel piping or piping components exposed to concrete.

Based on the above, the SLRA is supplemented as shown in Enclosure 2, to add stainless steel to the Further Evaluation discussion, as shown in the following:

SLRA Section 3.1.2.2.15

14. Multiple Systems: Notes for Components Not Credited with Flow Delivery Some aging management tables show components that include a PB function and align to Table 3.3.1, Items -091 or -095, but do not list flow blockage as an (internal) aging effect that requires management. Notes are added to these rows clarifying that the associated components are not credited with delivery of downstream flow. The following systems are affected:

Diesel generator services Gaseous waste processing Instrument air Liquid waste processing Nuclear and miscellaneous drains Nuclear sampling Radiation monitoring

Supplement 1 VCS SLRA Serial No.: 24-101 Page 11 of 14 Based on the above, the SLRA is supplemented as shown in Enclosure 2, to add plant-specific notes clarifying that the associated components are not credited with delivery of downstream flow, as shown in the following:

SLRA Table 3.3.2-10 3.3.2-15 3.3.2-19 3.3.2-22 3.3.2-25 3.3.2-26 3.3.2-27

15. Domestic Water System: Component and Environment Additions Review of domestic water piping in the Fuel Handling Building identified piping embedded within a concrete wall and a 1.5-gallon water heater tank. These components are subject to aging management review but were not addressed in the SLRA.

Based on the above, the SLRA is supplemented as shown in Enclosure 2, to address the Tank (water heater) component and external environment (concrete), as shown in the following:

SLRA Section SLRA Table 3.3.2.1.11 2.3.3-11 3.3.2.2.9 3.3.1 Item 107 3.3.2-11

16. Nuclear Sampling System: Cooling Loop Not Managed by Closed Treated Water Systems Program and Correction of Administrative Errors Within the nuclear sampling system, the auxiliary sample cooler and connected flowpaths are not managed by the Closed Treated Water Systems program as identified in SLRA Table 3.3.2-26. Fill and makeup to this small sample cooling loop is provided by treated water from the demineralized water system. The environment for these components is changed to treated water. Aging effects for the components exposed to treated water will be managed by the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting

Supplement 1 VCS SLRA Serial No.: 24-101 Page 12 of 14 Components instead of the Water Chemistry and One-Time Inspection programs that are recommended by the assigned GALL items VIII.E.SP-73 and VIII.E.SP-73.

Additionally, Tables 3.3.2-14 and 3.6.2-2 contained administrative errors that are corrected in this supplement.

Based on the above, the SLRA is supplemented as shown in Enclosure 2, to revise aging management of the sample system components, and to correct administrative errors in Tables 3.3.2-14 and 3.6.2-2, as shown in the following:

SLRA Table 3.3.2-14 3.3.2-26 3.4.1, Items -014 & -015 3.6.2-2

17. Fatigue Management: RV Outlet Nozzle Allowable End-Of-Evaluation Flaw Size Correction SLRA Section 4.3.4 indicates that the allowable end-of-evaluation flaw size for the RV Outlet Nozzle is 0.696 inches. The actual end-of-evaluation flaw size is 0.67 inches.

Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to replace the original allowable end-of-evaluation flaw size, as shown in the following:

18. PWR Vessel Internals: Component Inspection Scope and Categories Enhancements Enhancements are being made to the PWR Vessel Internals program to indicate an addition to the scope of components to be inspected, and to change inspection categories for several components. Inspection is being added for upper core plate inserts.

Inspection categories are being changed for the upper girth weld, clevis insert bolts, and Stellite wear surfaces on clevis inserts and radial supports. Clarifications are being made such that the latest NRC-approved version of MRP-227, which provides aging management to 80 years, may be implemented.

SLRA Section 4.3.4

Supplement 1 VCS SLRA Serial No.: 24-101 Page 13 of 14 Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to enhance component scope and categories, as shown in the following:

SLRA Section SLRA Table A1.7 A4.0-1 #7 B2.1.7

19. Pressurized Thermal Shock RTPTS Value Correction SLRA Section A3.2.3 (Pressurized Thermal Shock) is revised, as shown in Enclosure 2, to update the RTPTS value for base metal and longitudinal welds for consistency with Table 4.2.3-1.

Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to correct the RTPTS value, as shown in the following:

20. Enhancement for the Flux Thimble Tube Inspection Program SLRA Section B.2.1.24 discusses flux thimble tube inspections, and the use of measured wear rates in establishing future inspection frequency. However, there is no established minimum inspection periodicity for flux thimble tubes that show no wear.

Based on the above, the SLRA is supplemented as shown in Enclosure 2, to add a program Enhancement to provide minimum inspection periodicity for flux thimble tubes that show no wear, as shown in the following:

SLRA Section SLRA Table B2.1.24 A4.0-1 #24 B2-1

21. Reactor Building Polar Crane: Clarification of Operating Experience Summary The May 2017 example of operating experience provided for the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems program (B2.1.13),

as described in SLRA Section B2.1.13, is revised to clarify that the metal flakes were identified along the reactor building polar crane trolley rails.

SLRA Section A3.2.3

Supplement 1 VCS SLRA Serial No.: 24-101 Page 14 of 14 SLRA Section B2.1.13 is supplemented, as shown in Enclosure 2, to provide the clarification, as shown in the following:

22. Scoping and Screening Results: Electrical and Instrumentation and Control Systems SLRA Section B2.1.40 will be revised to add an enhancement related to the Monitoring and Trending program element for the Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements program.

The SLRA is supplemented, as shown in Enclosure 2, to provide the enhancement, as shown in the following:

SLRA Section SLRA Table B2.1.40 A4.0-1 #40

23. Fatigue Management: ASME Code,Section XI, Appendix L Weld Identification Correction SLRA Section 4.3.4 describes the results of ASME Code,Section XI, Appendix L evaluations for pressurizer surge line hot leg nozzle, charging nozzle, and alternate charging nozzle. Table 4.3.4-3 provides the weld numbers for the branch welds to the main loop piping and latest inspection dates. The locations assessed by ASME Code,Section XI, Appendix L are the field welds that attach each nozzle to the branch line piping.

Based on the above, the SLRA is supplemented, as shown in Enclosure 2, to replace the branch weld numbers with the field weld numbers and provide the inspection dates for the most recent inspection of the field welds to the pressurizer surge line hot leg nozzle, charging nozzle, and alternate charging nozzle, as shown in the following:

SLRA Section SLRA Table B2.1.1 4.3.4-3 A4.0-1 #1 SLRA Section B2.1.13

Supplement 1 VCS SLRA Serial No.: 24-101 Docket No: 50-395 SLRA MARK-UPS SUPPLEMENT 1 Dominion Energy South Carolina, Inc.

(Dominion Energy South Carolina, or DESC)

Virgil C. Summer Nuclear Station Unit 1

Page 2-11 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Scoping and Screening Methodology Plant electrical system cables, and cable bus are routed from the Engineered Safety Features transformer XTF-4 and Emergency Auxiliary Transformer XTF-31 transformers to the ES 7.2kV Buses XSW-1DA, and XSW-1DB.

Offsite power is supplied to the station by the 115 kV Parr ESF Line and 230 kV Bus #3, to the Engineered Safety Features transformer XTF-4 and Emergency Auxiliary Transformer XTF-31 transformers. Restoration of the 7.2kV ES buses XSW-1DA, XSW-1DB, XSW-1EA, and XSW-1EB through the Engineered Safety Features transformer XTF-4 or Emergency Auxiliary Transformer XTF-31 would by definition terminate an SBO event. The following electrical components are in the scope of license renewal for recovery from Station Blackout:

• 230KV Bus #3 disconnect switches, circuit breakers, associated control components (including cables), transmission conductors, switchyard bus, high voltage insulators to connect the 230KV Bus #3 Breaker XCB-8892 to Emergency Auxiliary Transformer XTF-31.

• 115KV Parr ESF Line disconnect switches, circuit breakers, associated control components (including cables), voltage regulators, transmission conductors, switchyard bus, high voltage insulators to connect the 115 kV Parr ESF Line, Circuit Switcher XES4 to the Engineered Safety Features transformer XTF-4.

• The Emergency Auxiliary Transformer, XTF-31Engineered Safety Features transformer, XTF-4, connection to the 7.2kV bus XSW-1DX includes insulated cables, cable bus, and circuit breakers.

• The XTF-31XTF-4 connection via the 7.2kV bus XSW-1DX to the 7.2kV ES buses XSW-1DA and XSBXSW-1DB includes insulated cables, cable bus, and circuit breakers.

• The Engineered Safety Features transformer, XTF-4Emergency Auxiliary Transformer, XTF-31, connection to the 7.2kV ES buses XSW-1DA and XSBXSW-1DB includes insulated cables, cable bus, and circuit breakers.

• ES bus XSW-1EA is connected to ES bus XSW-1DA with insulated cables, cable bus, and circuit breakers.

• ES bus XSW-1EB is connected to ES bus XSW-1DB with insulated cables, cable bus, and circuit breakers.

• DG/A (XEG-0001A-DG) is connected to ES bus XSW-1DA with insulated cables and circuit breakers

• DG/B (XEG-0001B-DG) is connected to ES bus XSW-1DB with insulated cables and circuit breakers The Alternate AC (AAC) source of power from the Parr Hydro Power Station via ESF Transformer XTF5052 to bus XSW-1DX described in FSAR Section 8.1 is not credited for SBO recovery.

Serial No.24-101 Page 2 of 115

Virgil C. Summer Nuclear Station Page 2-13 Application for Subsequent License Renewal Scoping and Screening Methodology, DRAFT A Supplement 1 Figure 2.1-1 SBO Offsite Recovery Paths 230KVBus#3 R

XTF31 EMERAUXTRANS 2307.2KV R

R DG/A XSW1DA

R R

XTF4 UNIT1ESFTRANS 1157.2KV R

R DG/B XSW1DB

R R

15 03 04 01 NORMAL 16 NORMAL 10 01 04 05 XSW1DX

02 XSW1EB

XSW1EA

01 XTF6 VOLTAGE REGULATOR 115KVPARRESFLINE XCB8892 EMERG 7.2KVIB463 7.2KVIB436 7.2KVTB463 7.2KVSW440 7.2KVSW425 CableBusTapBox 17 BusTie R

19 XSW1DB

XES8 TRANSFER SWITCH XES4 DISPATCH#1826 R

Note 1 Note 1: XSW-1DB Cubicle 17 does not contain a breaker.

Serial No.24-101 Page 3 of 115

Virgil C. Summer Nuclear Station Page 2-14 Application for Subsequent License Renewal Scoping and Screening Methodology, DRAFT A Supplement 1 Intentionally Blank Serial No.24-101 Page 4 of 115

Page 2-47 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Scoping and Screening Methodology AC Vital Buses (120V Distribution)

EV Yes FSAR 7.6.1, 7.2.1.1, Figure 8.3.3, Figures 8.2-3 &

8.2-4 Warehouse Electrical Equipment EW Yes N/A Main Control Board MC Yes N/A Miscellaneous Instrumentation (Pressure Flow Monitor System only)

MI Yes FSAR 9.3.4.2.5.24 Nuclear Instrumentation NI Yes FSAR 7.2.1.1, 7.7.1.3.1 Plant Surveillance PS Yes N/A Reactor Protection Control System RP Yes FSAR 7.2.2.3, 7.7.1.1 Engineered Safety Features SG Yes FSAR 7.3.1.1, 8.3.1.1 Substation (230KV and 115kV Parr ESF)

TS Yes FSAR 8.2.1 Technical Support Center TX Yes FSAR 7.7.3 Process Instrumentation and Control XI Yes FSAR 6.3.2.18, 7.2.1.1 Annunciators AA No FSAR 13.5.2.4 Computer CP No N/A Grounding & Cathodic Protection EC No FSAR 8.3.1.1.4(7)

Communications EE No FSAR 1.2.3.8.12, 9.5.2 Generator & Main Transformer EG No FSAR 8.3 Earthquake Instrumentation EI No N/A Electrical Power EP No FSAR 8.3 Inhouse Electrical Maintenance IE No N/A Integrated Control IN No N/A Low Frequency Grounding LF No N/A Table 2.2-1 Plant-Level Scoping Results System, Structure, or Commodity Group PAMS ID In Scope for License Renewal Reference1 Serial No.24-101 Page 5 of 115

Page 2-97 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Mechanical Systems System Evaluation Boundary The evaluation boundary for the fire service system components subject to aging management review includes safety-related containment penetration piping and nonsafety-related components that provide support to directly-connected safety-related components, or that retain water in buildings containing safety-related components. The electric and diesel-driven fire pumps and jockey pump are subject to aging management review. The fire pump diesel engine is an active skid-mounted unit. Components attached to the engine and within the skid boundaries are integral parts of the engine. They are tested as a unit and are parts of the active engine component, and are not subject to aging management review. The diesel fire pump engine exhaust and fuel oil supply components outside of the skid are subject to aging management review. The water supply from the fire pumps, via the yard loop to applicable hydrants, hose reels, and sprinkler systems are subject to aging management review. Water suppression piping within the Auxiliary Service Building is not credited for NFPA-805, but is subject to aging management review to maintain yard loop integrity.

The low pressure carbon dioxide tank and supply piping components are subject to aging management review.

Sample piping for the incipient fire (smoke) detectors that monitor the Relay and Upper Cable Spreading Rooms is also subject to aging management review, but does not appear on system drawings. The incipient fire detector panels (enclosures containing tubing, filters, valves, and vacuum pumps) are active components not subject to aging management review.

Portions of the water suppression system are not credited with 10 CFR 50.48 compliance and are not within-scope, as shown on the highlighted SLR boundary drawings. The Halon systems are not credited with 10 CFR 50.48 compliance and are not within-scope.

Fire doors are addressed in the structural commoditiessections for their associated buildings. Fire dampers are addressed in the air handling system. Smoke detectors are active instruments not subject to aging management review.

System Intended Functions The fire service system performs the following safety-related functions: The system provides containment isolation. Therefore, the fire service system is within the scope of license renewal in accordance with the criteria of 10 CFR 54.4(a)(1).

The fire service system contains nonsafety-related components whose failure could prevent satisfactory accomplishment of a safety-related function. Therefore, the fire service system is within the scope of license renewal in accordance with the criterion of 10 CFR 54.4(a)(2) for spatial interaction and structural integrity.

Serial No.24-101 Page 6 of 115

Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Mechanical Systems See Table 2.1-1 for definitions of intended functions.

Page 2-150 Table 2.3.3-10 Diesel Generator Services Component Type Intended Function(s)

Accumulator (air start positive shutdown)

Pressure Boundary Air dryer (separator and piping)

Leakage Boundary (Spatial)

Bolting Leakage Boundary (Spatial), Pressure Boundary, Structural Integrity (Attached)

Expansion joint Pressure Boundary Expansion joint (flange and bellows)

Pressure Boundary Expansion joint (tube)

Pressure Boundary Filter housing (fuel oil)

Pressure Boundary, Structural Integrity (Attached)

Filter housing (lube oil)

Pressure Boundary Filter silencer body Pressure Boundary Flame arrestor Pressure BoundaryFire Barrier Flexible hose Pressure Boundary Heat exchanger (intercooler - channel cover)

Pressure Boundary Heat exchanger (intercooler - channel)

Pressure Boundary Heat exchanger (intercooler - cover liner)

Pressure Boundary Heat exchanger (intercooler - shell)

Pressure Boundary Heat exchanger (intercooler - tube)

Heat Transfer, Pressure Boundary Heat exchanger (intercooler -

tubesheet)

Pressure Boundary Serial No.24-101 Page 7 of 115

Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Mechanical Systems See Table 2.1-1 for definitions of intended functions.

Page 2-154 The aging management review results for these component types are indicated in Table 3.3.2-11, Auxiliary Systems - Domestic Water - Aging Management Evaluation.

Table 2.3.3-11 Domestic Water Component Type Intended Function(s)

Bolting Leakage Boundary (Spatial)

Eyewash - safety shower (stanchion)

Leakage Boundary (Spatial)

Eyewash - safety shower (valve body)

Leakage Boundary (Spatial)

Orifice Leakage Boundary (Spatial)

Piping, piping components Leakage Boundary (Spatial)

Pump casing (hot water recirculating)

Leakage Boundary (Spatial)

Tank (hot water)

Leakage Boundary (Spatial)

Tank (water heater)

Leakage Boundary (Spatial)

Valve body Leakage Boundary (Spatial)

Waterhammer arrestor Leakage Boundary (Spatial)

Serial No.24-101 Page 8 of 115

Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Mechanical Systems See Table 2.1-1 for definitions of intended functions.

Page 2-156 Table 2.3.3-13 Fire Service Component Type Intended Function(s)

Bolting Pressure Boundary Exhaust silencer Pressure Boundary Flame arrestor Pressure BoundaryFire Barrier Flexible hose Pressure Boundary Heat exchanger coil (carbon dioxide tank)

Pressure Boundary Hose reel (fitting)

Pressure Boundary Hydrant Pressure Boundary Odorizer Pressure Boundary Orifice Pressure Boundary, Restricts Flow Piping, piping components Leakage Boundary (Spatial), Pressure Boundary Piping, piping components (spectacle flange)

Pressure Boundary Pump casing (jockey)

Pressure Boundary Pump casing (motor-and engine-driven column)

Pressure Boundary Pump casing (motor-and engine-driven)

Pressure Boundary Spray nozzle Flow Distribution Sprinkler head Pressure Boundary Strainer body Leakage Boundary (Spatial), Pressure Boundary Serial No.24-101 Page 9 of 115

Page 2-238 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Structures

- Guard pipes

- Penetration sleeves and seals

- Seismic gap filler material and covers Fireproofing and fire barriers are assemblies, which are designed and constructed to achieve specific fire resistance ratings, limit the spread of heat and fire, and restrict the movement of smoke.

Electrical enclosures include bus duct and switchgear enclosures, electrical panels and cabinets, junction, terminal, and pull boxes. The electrical panels and cabinets contain supports for electrical components located inside the enclosure. Gaskets provide a leak-tight condition from weather for the junction, terminal, and pull boxes. Electrical enclosures also include panels that are designed to contain potential internal fluid leakage.

Guard pipes are used as spray shields which protect adjacent equipment from postulated piping cracks or breaks.

Penetration sleeves are located in openings of walls, floors, roofs, or ceilings and allow components such as piping, conduits, duct banks, and tubing to be routed through the opening. Penetration seals are materials that are used to seal the penetration.

Seismic gaps are provided between adjacent structures to allow for relative motion between the structures. Although there are different configurations, in many configurations, the seismic gaps are covered by structural angles or plates, and/or filled with a compressible material.

System Evaluation Boundary The evaluation boundary for Miscellaneous Structural Commodities includes bolting; electrical enclosures; fireproofing and fire barriers associated with fire stops, fire wraps, fire barrier seals, coatings, and radiant energy shields; guard pipes; penetration seals; penetration sleeves; and seismic gap filler material; and seismic gap covers that are located in buildings and structures that are within the scope of subsequent license renewal.

Fire damper assemblies are evaluated in the air handling fire protection system. Fire barrier walls, doors, floors, and ceilings are evaluated with the associated buildings and structures that are within the scope of subsequent license renewal.

System Intended Functions Miscellaneous Structural Commodities perform the following safety-related functions:

Miscellaneous Structural Commodities provide structural support, shelter, and protection for safety-related SSCs. Therefore, Miscellaneous Structural Commodities are within the scope of license renewal in accordance with the criteria of 10 CFR 54.4(a)(1).

Serial No.24-101 Page 10 of 115

Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Structures See Table 2.1-1 for definitions of intended functions.

Page 2-250 The aging management review results for these component types are indicated in Table 3.5.2-1, Containment Structure - Aging Management Evaluation.

Table 2.4.1-1 Reactor Building Structural Member Intended Function(s)

Bolting Pressure Boundary, Structural Support Concrete elements Enclosure Protection, Fire Barrier, Flood Barrier, Jet Impingement Shield, Missile Barrier, Pressure Boundary, Structural Support Containment liner Pressure Boundary, Structural Support Equipment hatch, personnel access air lock, personnel escape air lock, and accessories (hinges, pins, closure mechanisms)

Enclosure Protection, Fire Barrier, Missile Barrier, Pressure Boundary, Structural Support Moisture barriers Enclosure Protection Penetrations (electrical)

Pressure Boundary, Structural Support Penetrations (mechanical)

Pressure Boundary, Structural Support Primary shield wall Enclosure Protection, Structural Support Refueling cavity/fuel transfer canal liner Water Barrier, Pressure Boundary, Structural Support Seals and gaskets Pressure Boundary Service Level I coatings Coating Integrity Steel elements Enclosure Protection, Fire Barrier, Flood Barrier, Jet Impingement Shield, Missile Barrier, Structural Support Sump liners Pressure Boundary, Structural Support Tendon anchorage components Structural Support Tendons Structural Support Serial No.24-101 Page 11 of 115

Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Structures See Table 2.1-1 for definitions of intended functions.

Page 2-251 The aging management review results for these component types are indicated in Table 3.5.2-2, Structures and Component Supports - Auxiliary Building - Aging Management Evaluation.

Table 2.4.1-2 Auxiliary Building Structural Member Intended Function(s)

Bellows Pressure Boundary Bolting Structural Support Caulking and sealants Enclosure Protection Concrete elements Enclosure Protection, Fire Barrier, Flood Barrier, Missile Barrier, Structural Support Containment liner Pressure Boundary Doors Enclosure Protection, Fire Barrier, Flood Barrier Masonry block walls Enclosure Protection, Flood Barrier Roofing membrane Enclosure Protection Steel elements Enclosure Protection, Fire Barrier, Flood Barrier, Missile Barrier, Structural Support Serial No.24-101 Page 12 of 115

Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Structures See Table 2.1-1 for definitions of intended functions.

Page 2-255 The aging management review results for these component types are indicated in Table 3.5.2-6, Structures and Component Supports - Control Building - Aging Management Evaluation.

Table 2.4.1-6 Control Building Structural Member Intended Function(s)

Bolting Structural Support Concrete elements Enclosure Protection, Fire Barrier, Flood Barrier, Missile Barrier, Structural Support Doors Enclosure Protection, Fire Barrier Roofing membrane Enclosure Protection Steel elements Enclosure Protection, Fire Barrier, Flood Barrier, Missile Barrier, Structural Support Serial No.24-101 Page 13 of 115

Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Structures See Table 2.1-1 for definitions of intended functions.

Page 2-256 The aging management review results for these component types are indicated in Table 3.5.2-7, Structures and Component Supports - Diesel Generator Building - Aging Management Evaluation.

Table 2.4.1-7 Diesel Generator Building Structural Member Intended Function(s)

Aluminum elements Enclosure Protection Bolting Structural Support Concrete elements Enclosure Protection, Fire Barrier, Flood Barrier, Missile Barrier, Structural Support Doors Enclosure Protection, Fire Barrier Roofing membrane Enclosure Protection Steel elements Enclosure Protection, Fire Barrier, Flood Barrier, Missile Barrier, Structural Support Serial No.24-101 Page 14 of 115

Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Structures See Table 2.1-1 for definitions of intended functions.

Page 2-261 The aging management review results for these component types are indicated in Table 3.5.2-12, Structures and Component Supports - Fuel Handling Building - Aging Management Evaluation.

Table 2.4.1-12 Fuel Handling Building Structural Member Intended Function(s)

Aluminum elements Enclosure Protection Bolting Structural Support Concrete elements Enclosure Protection, Fire Barrier, Flood Barrier, Missile Barrier, Structural Support Doors Enclosure Protection, Fire Barrier Fuel storage rack neutron-absorbing sheets Absorbs Neutrons Roofing membrane Enclosure Protection Spent fuel pool liner plates Enclosure Protection, Pressure Boundary, Structural Support Stainless steel elements Enclosure Protection, Pressure Boundary, Structural Support Steel elements Enclosure Protection, Fire Barrier, Flood Barrier, Missile Barrier, Structural Support Serial No.24-101 Page 15 of 115

Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Structures See Table 2.1-1 for definitions of intended functions.

Page 2-262 The aging management review results for these component types are indicated in Table 3.5.2-13, Structures and Component Supports - Intermediate Building - Aging Management Evaluation.

Table 2.4.1-13 Intermediate Building Structural Member Intended Function(s)

Bolting Structural Support Concrete elements Enclosure Protection, Fire Barrier, Flood Barrier, Missile Barrier, Structural Support Doors Enclosure Protection, Fire Barrier, Flood Barrier Roofing membrane Enclosure Protection Steel elements Enclosure Protection, Fire Barrier, Flood Barrier, Missile Barrier, Structural Support Serial No.24-101 Page 16 of 115

Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Structures See Table 2.1-1 for definitions of intended functions.

Page 2-263 The aging management review results for these component types are indicated in Table 3.5.2-14, Structures and Component Supports - Miscellaneous Structural Commodities - Aging Management Evaluation.

Table 2.4.1-14 Miscellaneous Structural Commodities Structural Member Intended Function(s)

Bolting Structural Support Electrical Enclosures Enclosure Protection, Leakage Boundary (Spatial), Structural Support Fireproofing and fire barriers Enclosure Protection, Fire Barrier, Flood Barrier Guard pipes Enclosure Protection Penetration seals Enclosure Protection, Fire Barrier, Flood Barrier, Pressure Boundary Penetration sleeves Structural Support Seismic gap covers Fire Barrier Seismic gap filler material Enclosure Protection, Fire Barrier Serial No.24-101 Page 17 of 115

Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Structures See Table 2.1-1 for definitions of intended functions.

Page 2-269 The aging management review results for these component types are indicated in Table 3.5.2-20, Structures and Component Supports - Turbine Building - Aging Management Evaluation.

Table 2.4.1-20 Turbine Building Structural Member Intended Function(s)

Aluminum elements Enclosure Protection Bolting Structural Support Concrete elements Enclosure Protection, Fire Barrier, Structural Support Doors Enclosure Protection, Fire Barrier Masonry block walls Enclosure Protection, Fire Barrier, Structural Support Roofing membrane Enclosure Protection Steel elements Enclosure Protection, Fire Barrier, Structural Support Serial No.24-101 Page 18 of 115

Page 2-271 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Electrical and Instrumentation and Control Systems 2.5 SCOPING AND SCREENING RESULTS: ELECTRICAL AND INSTRUMENTATION AND CONTROL SYSTEMS Scoping to determine the electrical and I&C systems that fall within subsequent license renewal was performed according to the methodology in Section 2.1.4 with results presented in Table 2.2-1.

Results of electrical system scoping presented in Section 2.2 include not only plant electrical systems, but also switchyard components credited with restoring offsite power following a Station Blackout (SBO) event. The boundary for the SBO recovery path from both onsite and offsite power is depicted in a simplified diagram in Figure 2.1-1. Screening of in-scope electrical and I&C systems, as well as electrical and I&C components within in-scope mechanical systems, was performed in accordance with the methodology discussed in Section 2.1.5.

Identification of Electrical Components and Commodities Screening of electrical and I&C components within the in-scope electrical, I&C, and mechanical systems used a bounding approach as discussed in Section 2.1.5.1. With the commodity-based approach, the electrical and I&C component types with similar design and/or functional characteristics are grouped together. This is consistent with the guidance from NEI 17-01 and Table 2.1-6 of NUREG-2192. Electrical and I&C components for the in-scope systems were assigned to commodity groups based on the listing in NUREG-2192, Table 2.1-6.

Application of Screening Criterion 10 CFR 54.21(a)(1)(i) to Electrical Components and Commodities Following identification of electrical components and commodities, the criteria of 10 CFR 54.21(a)(1)(i) were applied to identify components and commodities that perform their functions without moving parts or without a change in configuration or properties. Commodities s u b j e c t t o a n a g i n g m a n a g e m e n t r e v i e w w e r e i d e n t i f i e d b y a p p l y i n g 10 CFR 54.21(a)(1) to identify those commodities that perform their function without moving parts or a change in configuration (passive components). This method provides the most efficient means for determining the electrical commodities subject to an aging management review since many electrical and I&C components are active.

Passive commodity groups were reviewed, and any that did not perform an intended function were determined to not require an aging management review. The following electrical components and commodity groups were determined to meet the screening criteria of 10 CFR 54.21(a)(1)(i):

Cable Bus Cables and Connections Cable connections (metallic parts)

Connector contacts for electrical connections exposed to borated water leakage Serial No.24-101 Page 19 of 115

Page 3-32 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Aging Management Review

• For units with divider plate assemblies fabricated of Alloy 600 or Alloy 600 type weld materials, if the industry analyses (EPRI 3002002850) are not bounding for the applicants unit, a plant-specific AMP is necessary or a rationale is necessary for why such a program is not needed. A plant-specific AMP (one beyond the primary water chemistry and the steam generator programs) may include a one time inspection that is capable of detecting cracking to verify the effectiveness of the water chemistry and steam generator programs and the absence of PWSCC in the divider plate assemblies.

The existing programs rely on control of reactor water chemistry to mitigate cracking due to PWSCC and general visual inspections of the channel head interior surfaces (included as part of the steam generator program). The GALL-SLR Report recommends further evaluation for a plant-specific AMP to confirm the effectiveness of the primary water chemistry and steam generator programs as described in this section. Acceptance criteria for a plant-specific AMP are described in BTP RLSB-1 (Appendix A.1 of this SRP SLR). In place of a plant-specific AMP, the applicant may provide a rationale to justify why a plant-specific AMP is not necessary.

(1) [3.1.1-025] - Foreign OE in steam generators with a design similar to that of Westinghouse steam generators (particularly Model 51) has identified cracks due to primary water stress corrosion cracking (PWSCC) in steam generator (SG) divider plate assemblies fabricated of Alloy 600 and/or the associated Alloy 600 weld materials, even with proper primary water chemistry.

The steam generator divider plate assemblies and associated welds are fabricated of Alloy 690 materials. The welds are ERNiCr-3 or ENiCrFe-3 weld material. Analysis performed by the industry (EPRI 3002002850) evaluated divider plate cracking for the Westinghouse Model 51 steam generator, which was determined to be the most limiting steam generator model. EPRI provided a checklist to determine whether this analysis bounds an applicants steam generators.

This checklist was completed for VCSNS and documents that the analysis is applicable and bounding for the VCSNS steam generators. Therefore, a plant-specific AMP is not necessary.

Cracking of the steam generator channel head divider plate is managed by the Steam Generators (B2.1.10) program and the Water Chemistry (B2.1.2) program.

(2) Cracking due to PWSCC could occur in SG nickel alloy tube-to-tubesheet welds exposed to reactor coolant. The acceptance criteria for this review are:

• For units with Alloy 600 SG tubes for which an alternate repair criterion such as C*, F*, H*, or W*

has been permanently approved for both the hot-and cold-leg side of the steam generator, the weld is no longer part of the reactor coolant pressure boundary and a plant specific AMP is not necessary; Serial No.24-101 Page 20 of 115

Page 3-37 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Aging Management Review If the following conditions are met, loss of material is not considered to be an applicable aging effect for steel: (a) attributes of the concrete are consistent with American Concrete Institute (ACI) 318 or ACI 349 (low water to-cement ratio, low permeability, and adequate air entrainment) as cited in NUREG1557; (b) plant specific OE indicates no degradation of the concrete that could lead to penetration of water to the metal surface; and (c) the piping is not potentially exposed to groundwater. For SS components loss of material and cracking due to SCC are not considered to be applicable aging effects as long as the piping is not potentially exposed to groundwater. Where these conditions are not met, loss of material due to general (steel only), crevice or pitting corrosion and cracking due to SCC (SS only) are identified as applicable aging effects. GALL SLR Report AMP XI.M41, Buried and Underground Piping and Tanks, describes an acceptable program to manage these aging effects.

Not applicable. There are no in-scope steel or stainless steel piping or piping components exposed to concrete in the Reactor Vessel, Internals, and Reactor Coolant System.

3.1.2.2.16 Loss of Material Due to Pitting and Crevice Corrosion Loss of material due to pitting and crevice corrosion could occur in indoor or outdoor SS and nickel alloy piping, piping components, and tanks exposed to any air, condensation, or underground environment when the component is: (a) uninsulated; (b) insulated; (c) in the vicinity of insulated components; or (d) in the vicinity of potentially transportable halogens. Loss of material due to pitting and crevice corrosion can occur on SS and nickel alloys in environments containing sufficient halides (e.g., chlorides) in the presence of moisture.

Insulated SS and nickel alloy components exposed to air, condensation, or underground environments are susceptible to loss of material due to pitting or crevice corrosion if the insulation contains certain contaminants. Leakage of fluids through mechanical connections such as bolted flanges and valve packing can result in contaminants leaching onto the component surface or the surfaces of other components below the component. For outdoor insulated SS and nickel alloy components, rain and changing weather conditions can result in moisture intrusion into the insulation.

Plant specific OE and the condition of SS and nickel alloy components are evaluated to determine if prolonged exposure to the plant specific environments has resulted in pitting or crevice corrosion. Loss of material due to pitting and crevice corrosion is not an aging effect requiring management for SS and nickel alloy components if: (a) plant-specific OE does not reveal a history of loss of material due to pitting or crevice corrosion; and (b) a one-time inspection demonstrates that the aging effect is not occurring or is occurring so slowly that it will not affect the intended function of the components during the subsequent period of extended operation. The applicant documents the results of the plant specific OE review in the SLRA.

Serial No.24-101 Page 21 of 115

Virgil C. Summer Nuclear Station Page 3-47 Supplement 1 Application for Subsequent License Renewal 3.1.1-025 Steel (with nickel alloy cladding) or nickel alloy steam generator primary side components: divider plate and tube-to-tube sheet welds exposed to reactor coolant Cracking due to primary water SCC AMP XI.M2, Water Chemistry, and AMP XI.M19, Steam Generators. In addition, a plant-specific program is to be evaluated.

Yes (SRP-SLR Sections 3.1.2.2.11.1 and 3.1.2.2.11.2)

Consistent with NUREG-2191 with exceptions.

Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation.

A plant-specific program is not needed for the divider plate or for the tube-to-tubesheet weld. See further evaluation in Section 3.1.2.2.11.1 and 3.1.2.2.11.2.

3.1.1-028 Westinghouse-specific Existing Programs components: Stainless steel, nickel alloy, and X-750 control rod guide tube support pins (split pins) exposed to reactor coolant and neutron flux Loss of material due to wear; cracking due to SCC, IASCC, fatigue AMP XI.M16A, PWR Vessel Internals, and AMP XI.M2, Water Chemistry (for SCC mechanisms only)

Yes (SRP-SLR Section 3.1.2.2.9)

Not applicable. The stainless steel control rod guide tube support pins (split pins) are No additional measures components and are addressed by row 3.1.1-055c. The associated NUREG-2191 items are not used.

3.1.1-029 Nickel alloy core shroud and core plate access hole cover (welded covers) exposed to reactor coolant Cracking due to SCC, IGSCC, IASCC AMP XI.M9, BWR Vessel Internals, and AMP XI.M2, Water Chemistry Yes (SRP-SLR Section 3.1.2.2.12)

Not applicable - BWR only.

3.1.1-030 Stainless steel, nickel alloy penetration: drain line exposed to reactor coolant Cracking due to SCC, IGSCC, cyclic loading AMP XI.M1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, and AMP XI.M2, Water Chemistry (SCC, IGSCC mechanisms only)

No Not applicable - BWR only.

3.1.1-031 Steel and stainless steel isolation condenser components exposed to reactor coolant Loss of material due to general (steel only),

pitting, crevice corrosion, wear AMP XI.M1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, and AMP XI.M2, Water Chemistry No Not applicable - BWR only.

Table 3.1.1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 22 of 115

Virgil C. Summer Nuclear Station Page 3-48 Supplement 1 Application for Subsequent License Renewal 3.1.1-033 Stainless steel, steel with stainless steel cladding Class 1 reactor coolant pressure boundary components exposed to reactor coolant Cracking due to SCC AMP XI.M1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, and AMP XI.M2, Water Chemistry No Consistent with NUREG-2191, with exceptions, and a different aging management program is credited for some components. The Steam Generators (B2.1.10) program will manage cracking of the steam generator channel head and channel head drain tube instead of the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1) program. Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation. In addition to Reactor Vessel, Internals, And Reactor Coolant System, components in the Engineered Safety Features (residual heat removal and safety injection) and Auxiliary Systems (chemical and volume control) are aligned to this row.

3.1.1-034 Stainless steel, steel with stainless steel cladding pressurizer relief tank (tank shell and heads, flanges, nozzles) exposed to treated borated water >60°C

(>140°F)

Cracking due to SCC AMP XI.M1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, and AMP XI.M2, Water Chemistry No Not applicable. There are no in-scope stainless steel, steel with stainless steel cladding pressurizer relief tank (tank shell and heads, flanges, nozzles) exposed to treated borated water >60°C (>140°F) in the Reactor Vessel, Internals, and Reactor Coolant System. The associated NUREG-2191 aging items are not used.

3.1.1-035 Stainless steel, steel with stainless steel cladding reactor coolant system cold leg, hot leg, surge line, and spray line piping and fittings exposed to reactor coolant Cracking due to cyclic loading AMP XI.M1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD No Consistent with NUREG-2191.

3.1.1-036 Steel, stainless steel pressurizer integral support exposed to any environment Cracking due to cyclic loading AMP XI.M1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD No Consistent with NUREG-2191.

Table 3.1.1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 23 of 115

Virgil C. Summer Nuclear Station Page 3-64 Supplement 1 Application for Subsequent License Renewal 3.1.1-068 Nickel alloy steam generator tubes exposed to secondary feedwater or steam Changes in dimension (denting) due to corrosion of carbon steel tube support plate AMP XI.M19, Steam Generators, and AMP XI.M2, Water Chemistry No Not applicable. There are no carbon steelnickel alloy tube support plates in the Reactor Vessel, Internals, and Reactor Coolant System. The "tube bundle support and baffle plate" component is stainless steel and is addressed in rows 3.1.1-005, -071, and -076. The associated NUREG-2191 aging items are not used.

3.1.1-069 Nickel alloy steam generator tubes and sleeves exposed to secondary feedwater or steam Cracking due to outer diameter SCC, intergranular attack AMP XI.M19, Steam Generators, and AMP XI.M2, Water Chemistry No Consistent with NUREG-2191 with exceptions.

Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation.

3.1.1-070 Nickel alloy steam generator tubes, repair sleeves, and tube plugs exposed to reactor coolant Cracking due to primary water SCC AMP XI.M19, Steam Generators, and AMP XI.M2, Water Chemistry No Consistent with NUREG-2191 with exceptions.

Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation.

3.1.1-071 Steel, chrome plated steel, stainless steel, nickel alloy steam generator U-bend supports including anti-vibration bars exposed to secondary feedwater or steam Cracking due to SCC or other mechanism(s); loss of material due general (steel only), pitting, crevice corrosion AMP XI.M19, Steam Generators, and AMP XI.M2, Water Chemistry No Consistent with NUREG-2191, with exceptions, and a different aging management program is credited for some components. The ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1) program is used instead of the Steam Generators (B2.1.10) program to manage cracking and loss of material for the auxiliary feedwater nozzle thermal sleeve and feedwater nozzle thermal sleeve. Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation.

3.1.1-072 Steel steam generator tube support plate, tube bundle wrapper, supports and mounting hardware exposed to secondary feedwater or steam Loss of material due to general, pitting, crevice corrosion, erosion, ligament cracking due to corrosion AMP XI.M19, Steam Generators, and AMP XI.M2, Water Chemistry (corrosion based aging effects and mechanisms only)

No Consistent with NUREG-2191 with exceptions.

Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation.

Table 3.1.1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 24 of 115

Virgil C. Summer Nuclear Station Page 3-65 Supplement 1 Application for Subsequent License Renewal 3.1.1-073 Nickel alloy steam generator tubes and sleeves exposed to phosphate chemistry in secondary feedwater or steam Loss of material due to wastage, pitting corrosion AMP XI.M19, Steam Generators, and AMP XI.M2, Water Chemistry No Not applicable. There are no in-scope nickel alloy steam generator tubes and sleeves exposed to phosphate chemistry in secondary feedwater or steam in the Reactor Vessel, Internals, and Reactor Coolant System.

The associated NUREG-2191 aging items are not used.

3.1.1-074 Steel steam generator upper assembly and separators including feedwater inlet ring and support exposed to secondary feedwater or steam Wall thinning due to flow-accelerated corrosion AMP XI.M19, Steam Generators, and AMP XI.M2, Water Chemistry No Consistent with NUREG-2191 with exceptions.

Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation.

3.1.1-075 Steel steam generator tube support lattice bars exposed to secondary feedwater or steam Wall thinning due to flow-accelerated corrosion, general corrosion AMP XI.M19, Steam Generators, and AMP XI.M2, Water Chemistry No Not applicable. There are no in-scope steel steam generator tube support lattice bars exposed to secondary feedwater or steam in the Reactor Vessel, Internals, and Reactor Coolant System. The associated NUREG-2191 aging items are not used.

3.1.1-076 Steel, chrome plated steel, stainless steel, nickel alloy steam generator U-bend supports including anti-vibration bars exposed to secondary feedwater or steam Loss of material due to wear, fretting AMP XI.M19, Steam Generators No Consistent with NUREG-2191, with exceptions, and a different aging management program is credited for some components. The ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1) program is used instead of the Steam Generators (B2.1.10) program to manage loss of material for the auxiliary feedwater nozzle thermal sleeve and feedwater nozzle thermal sleeve. Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation.

Table 3.1.1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 25 of 115

Virgil C. Summer Nuclear Station Page 3-66 Supplement 1 Application for Subsequent License Renewal 3.1.1-077 Nickel alloy steam generator tubes and sleeves exposed to secondary feedwater or steam Loss of material due to wear, fretting AMP XI.M19, Steam Generators No Consistent with NUREG-2191, with exceptions, with a TLAA evaluation included. Wear of steam generator tubes at tube support plates is a TLAA, evaluated in Section 4.7.4, Steam Generator Tube Wear Evaluation.

Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation.

3.1.1-078 Nickel alloy steam generator components such as, secondary side nozzles (vent, drain, and instrumentation) exposed to secondary feedwater or steam Cracking due to SCC AMP XI.M2, Water Chemistry, and AMP XI.M32, One-Time Inspection, or AMP XI.M1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD.

No Not applicable. The steam generators are recirculating steam generators, not once-through. The associated NUREG-2191 aging items are not used.

3.1.1-079 Stainless steel; steel with nickel alloy or stainless steel cladding; and nickel alloy reactor coolant pressure boundary components exposed to reactor coolant Loss of material due to pitting, crevice corrosion AMP XI.M2, Water Chemistry, and AMP XI.M32, One-Time Inspection No Not applicable - BWR only.

3.1.1-080 Stainless steel or steel with stainless steel cladding pressurizer relief tank: tank shell and heads, flanges, nozzles (none-ASME Section XI components) exposed to treated borated water >60°C (>140°F)

Cracking due to SCC AMP XI.M2, Water Chemistry, and AMP XI.M32, One-Time Inspection No Not applicable. There are no in-scope stainless steel or steel with stainless steel cladding pressurizer relief tank:

tank shell and heads, flanges, nozzles (non-ASME Section XI components) exposed to treated borated water >60°C (>140°F) in the Reactor Vessel, Internals, and Reactor Coolant System. The associated NUREG-2191 aging items are not used.

3.1.1-081 Stainless steel pressurizer spray head exposed to reactor coolant Cracking due to SCC AMP XI.M2, Water Chemistry, and AMP XI.M32, One-Time Inspection No Not applicable. There is no in-scope stainless steel pressurizer spray head exposed to reactor coolant in the Reactor Vessel, Internals, and Reactor Coolant System.

The associated NUREG-2191 aging items are not used.

Table 3.1.1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 26 of 115

---

1

Virgil C. Summer Nuclear Station Page 3-72 Supplement 1 Application for Subsequent License Renewal 3.1.1-111 Nickel alloy steam generator tubes exposed to secondary feedwater or steam Reduction of heat transfer due to fouling AMP XI.M2, Water Chemistry, and AMP XI.M19, Steam Generators No Consistent with NUREG-2191 with exceptions.

Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation.

3.1.1-113 Steel reactor vessel external attachments exposed to indoor, uncontrolled air Loss of material due to general, pitting, crevice corrosion, wear AMP XI.M1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD No Not applicable - BWR only.

3.1.1-114 Reactor coolant system components defined as ASME Section XI Code Class components (ASME Code Class 1 reactor coolant pressure boundary components, reactor vessel interior attachments, or core support structure components; or ASME Class 2 or 3 components -

including ASME defined appurtenances, component supports, and associated pressure boundary welds, or components subject to plant-specific equivalent classifications for these ASME code classes)

Cracking due to SCC, IGSCC, PWSCC, IASCC (SCC mechanisms for stainless steel, nickel alloy components only), fatigue or cyclic loading; loss of material due to general corrosion (steel only), pitting corrosion, crevice corrosion, or wear AMP XI.M1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, and AMP XI.M2, Water Chemistry (water chemistry-related or corrosion-related aging effect mechanisms only)

No Not applicable. Cracking and loss of material of reactor coolant system components defined as ASME Section XI Code Class components (ASME Code Class 1 reactor coolant pressure boundary components or core support structure components, or ASME Class 2 or 3 components - including ASME defined appurtenances, component supports, and associated pressure boundary welds, or components subject to plant-specific equivalent classifications for these ASME code classes) is addressed by rows 3.1.1-020, 3.1.1-033, 3.1.1-035, 3.1.1-036, 3.1.1-037, 3.1.1-039, 3.1.1-042, 3.1.1-045, 3.1.1-088, and 3.1.1-116. The associated NUREG-2191 aging items are not used.

3.1.1-115 Stainless steel piping, piping components exposed to concrete None None Yes (SRP-SLR Section 3.1.2.2.15)

Not applicable. There are no in-scope stainless steel piping, piping components exposed to concrete in the Reactor Vessel, Internals, and Reactor Coolant System.

The associated NUREG-2191 aging items are not used.

Table 3.1.1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 27 of 115

Virgil C. Summer Nuclear Station Page 3-75 Supplement 1 Application for Subsequent License Renewal 3.1.1-125 Nickel alloy steam generator tubes at support plate locations exposed to secondary feedwater or steam Cracking due to flow-induced vibration, high-cycle fatigue AMP XI.M19, Steam Generators No Consistent with NUREG-2191 with exceptions.

Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation.

3.1.1-127 Steel (with stainless steel or nickel alloy cladding) steam generator heads and tubesheets exposed to reactor coolant Loss of material due to boric acid corrosion AMP XI.M2, Water Chemistry, and AMP XI.M19, Steam Generators No Consistent with NUREG-2191, with exceptions, and a different aging management program is credited for some components. The ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1) program will manage loss of material of the steel with stainless steel cladding steam generator primary inlet and outlet nozzle, and the stainless steel primary inlet and outlet nozzle safe ends, exposed to reactor coolant, instead of the Steam Generators (B2.1.10) program.

Exceptions apply to the NUREG-2191 recommendations for Steam Generators (B2.1.10) program implementation.

3.1.1-128 Stainless steel, nickel alloy nozzles safe ends and welds: high pressure core spray; low pressure core spray; recirculating water, low pressure coolant injection or RHR injection mode exposed to reactor coolant Cracking due to SCC, IGSCC AMP XI.M7, BWR Stress Corrosion Cracking, and AMP XI.M2, Water Chemistry No Not applicable - BWR only.

Table 3.1.1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 28 of 115

Virgil C. Summer Nuclear Station Page 3-103 Supplement 1 Application for Subsequent License Renewal Table 3.1.2-4 Reactor Vessel, Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Subcomponent Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Anti-vibration bar SS Stainless steel (E) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 AB Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 A

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 AB Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 A

Steam Generators (B2.1.10)

IV.D1.RP-225 3.1.1-076 AB Anti-vibration bar retaining ring and bar SS Nickel alloy (E) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 AB Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 A

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 AB Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 A

Steam Generators (B2.1.10)

IV.D1.RP-225 3.1.1-076 AB Auxiliary feedwater internal spray pipe PB;SP Nickel alloy (E) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

(I) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

Auxiliary feedwater nozzle PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

IV.C2.R-431 3.1.1-124 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

(I) Treated water Cumulative fatigue damage TLAA IV.D1.R-33 3.1.1-005 A

Loss of material ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-368 3.1.1-012 C

Water Chemistry (B2.1.2)

IV.D1.RP-368 3.1.1-012 C

Wall thinning Flow-Accelerated Corrosion (B2.1.8)

IV.D1.R-37 3.1.1-061 A

Serial No.24-101 Page 29 of 115

Virgil C. Summer Nuclear Station Page 3-104 Supplement 1 Application for Subsequent License Renewal Auxiliary feedwater nozzle thermal sleeve LTC Nickel alloy (E) Treated water

>60°C (>140°F)

Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-384 3.1.1-071 E, 1 Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-226 3.1.1-071 E, 1 Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-225 3.1.1-076 E, 1 Blowdown header FD Nickel alloy (E) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

(I) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

Channel head PB Steel with stainless steel cladding (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

IV.C2.R-431 3.1.1-124 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

(I) Reactor coolant Cracking Steam Generators (B2.1.10)

IV.D1.RP-232 3.1.1-033 E, 2 Water Chemistry (B2.1.2)

IV.D1.RP-232 3.1.1-033 C

Cumulative fatigue damage TLAA IV.D1.R-221 3.1.1-008 A

Loss of material Steam Generators (B2.1.10)

IV.D1.R-436 3.1.1-127 AB Water Chemistry (B2.1.2)

IV.D1.R-436 3.1.1-127 A

Channel head divider plate FD Nickel alloy (E) Reactor coolant Cracking Steam Generators (B2.1.10)

IV.D1.RP-367 3.1.1-025 AB Water Chemistry (B2.1.2)

IV.D1.RP-367 3.1.1-025 A

Cumulative fatigue damage TLAA IV.D1.R-221 3.1.1-008 A

Table 3.1.2-4 Reactor Vessel, Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Subcomponent Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 30 of 115

Virgil C. Summer Nuclear Station Page 3-105 Supplement 1 Application for Subsequent License Renewal Channel head drain tube PB Stainless steel (I) Reactor coolant Cracking Steam Generators (B2.1.10)

IV.D1.RP-232 3.1.1-033 E, 2 Water Chemistry (B2.1.2)

IV.D1.RP-232 3.1.1-033 C

Cumulative fatigue damage TLAA IV.D1.R-221 3.1.1-008 A

Loss of material Steam Generators (B2.1.10)

IV.D1.R-436 3.1.1-127 CD Water Chemistry (B2.1.2)

IV.D1.R-436 3.1.1-127 C

Feedwater distribution ring FD Steel (E) Treated water Loss of material Steam Generators (B2.1.10)

IV.D1.RP-161 3.1.1-072 CD Water Chemistry (B2.1.2)

IV.D1.RP-161 3.1.1-072 C

Steam Generators (B2.1.10)

IV.D1.RP-225 3.1.1-076 CD (I) Treated water Loss of material Steam Generators (B2.1.10)

IV.D1.RP-161 3.1.1-072 CD Water Chemistry (B2.1.2)

IV.D1.RP-161 3.1.1-072 C

Steam Generators (B2.1.10)

IV.D1.RP-225 3.1.1-076 CD Wall thinning Steam Generators (B2.1.10)

IV.D1.RP-49 3.1.1-074 AB Water Chemistry (B2.1.2)

IV.D1.RP-49 3.1.1-074 A

Feedwater distribution ring safe end FD Nickel alloy (E) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

(I) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

Feedwater distribution ring spray nozzle SP Nickel alloy (E) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

(I) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

Table 3.1.2-4 Reactor Vessel, Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Subcomponent Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 31 of 115

Virgil C. Summer Nuclear Station Page 3-106 Supplement 1 Application for Subsequent License Renewal Feedwater nozzle PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

IV.C2.R-431 3.1.1-124 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

(I) Treated water Cumulative fatigue damage TLAA IV.D1.R-33 3.1.1-005 A

Loss of material ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-368 3.1.1-012 C

Water Chemistry (B2.1.2)

IV.D1.RP-368 3.1.1-012 C

Wall thinning Flow-Accelerated Corrosion (B2.1.8)

IV.D1.R-37 3.1.1-061 A

Feedwater nozzle thermal sleeve LTC Nickel alloy (E) Treated water

>60°C (>140°F)

Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-384 3.1.1-071 E, 1 Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-226 3.1.1-071 E, 1 Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-225 3.1.1-076 E, 1 Moisture separator assembly FD Steel (E) Steam Loss of material Steam Generators (B2.1.10)

IV.D1.RP-161 3.1.1-072 CD Water Chemistry (B2.1.2)

IV.D1.RP-161 3.1.1-072 C

Wall thinning Steam Generators (B2.1.10)

IV.D1.RP-49 3.1.1-074 AB Water Chemistry (B2.1.2)

IV.D1.RP-49 3.1.1-074 A

(I) Treated water Loss of material Steam Generators (B2.1.10)

IV.D1.RP-161 3.1.1-072 CD Water Chemistry (B2.1.2)

IV.D1.RP-161 3.1.1-072 C

Wall thinning Steam Generators (B2.1.10)

IV.D1.RP-49 3.1.1-074 AB Water Chemistry (B2.1.2)

IV.D1.RP-49 3.1.1-074 A

Table 3.1.2-4 Reactor Vessel, Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Subcomponent Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 32 of 115

Virgil C. Summer Nuclear Station Page 3-107 Supplement 1 Application for Subsequent License Renewal Moisture separator column assembly FD Nickel alloy (E) Steam Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

Steam Generators (B2.1.10)

IV.D1.RP-225 3.1.1-076 CD (I) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

Steam Generators (B2.1.10)

IV.D1.RP-225 3.1.1-076 CD Primary inlet and outlet nozzle PB Steel with stainless steel cladding (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

IV.C2.R-431 3.1.1-124 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

(I) Reactor coolant Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-232 3.1.1-033 A

Water Chemistry (B2.1.2)

IV.D1.RP-232 3.1.1-033 A

Cumulative fatigue damage TLAA IV.D1.R-221 3.1.1-008 A

Loss of material ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.R-436 3.1.1-127 E, 3 Water Chemistry (B2.1.2)

IV.D1.R-436 3.1.1-127 C

Primary inlet and outlet nozzle safe end PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

V.A.EP-103b 3.2.1-007 A

Loss of material One-Time Inspection (B2.1.20)

IV.C2.R-452a 3.1.1-136 A

(I) Reactor coolant Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-232 3.1.1-033 A

Water Chemistry (B2.1.2)

IV.D1.RP-232 3.1.1-033 A

Cumulative fatigue damage TLAA IV.D1.R-221 3.1.1-008 A

Loss of material ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.R-436 3.1.1-127 E, 3 Water Chemistry (B2.1.2)

IV.D1.R-436 3.1.1-127 C

Table 3.1.2-4 Reactor Vessel, Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Subcomponent Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 33 of 115

Virgil C. Summer Nuclear Station Page 3-108 Supplement 1 Application for Subsequent License Renewal Primary inlet and outlet nozzle weld PB Nickel alloy (E) Air - indoor uncontrolled Loss of material One-Time Inspection (B2.1.20)

IV.C2.R-452a 3.1.1-136 C

(I) Reactor coolant Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.C2.RP-159 3.1.1-045 C

Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor Coolant Pressure Boundary Components (B2.1.5)

IV.C2.RP-159 3.1.1-045 C

Water Chemistry (B2.1.2)

IV.C2.RP-159 3.1.1-045 C

Loss of material Water Chemistry (B2.1.2)

IV.C2.RP-23 3.1.1-088 A

Primary manway PB Steel with stainless steel cladding (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

IV.C2.R-431 3.1.1-124 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

(I) Reactor coolant Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-232 3.1.1-033 A

Water Chemistry (B2.1.2)

IV.D1.RP-232 3.1.1-033 A

Cumulative fatigue damage TLAA IV.D1.R-221 3.1.1-008 A

Loss of material Steam Generators (B2.1.10)

IV.D1.R-436 3.1.1-127 CD Water Chemistry (B2.1.2)

IV.D1.R-436 3.1.1-127 C

Primary manway cover PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

IV.C2.R-431 3.1.1-124 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

Primary manway cover bolting PB Steel (E) Air - indoor uncontrolled Cumulative fatigue damage TLAA IV.C2.R-18 3.1.1-005 A

Loss of material Bolting Integrity (B2.1.9)

IV.D1.RP-166 3.1.1-064 A

Loss of preload Bolting Integrity (B2.1.9)

IV.D1.RP-46 3.1.1-067 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

Table 3.1.2-4 Reactor Vessel, Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Subcomponent Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 34 of 115

Virgil C. Summer Nuclear Station Page 3-109 Supplement 1 Application for Subsequent License Renewal Primary manway cover insert PB Stainless steel (E) Reactor coolant Cracking ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-232 3.1.1-033 A

Water Chemistry (B2.1.2)

IV.D1.RP-232 3.1.1-033 A

Loss of material Steam Generators (B2.1.10)

IV.D1.R-436 3.1.1-127 CD Water Chemistry (B2.1.2)

IV.D1.R-436 3.1.1-127 C

Secondary manway PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

IV.C2.R-431 3.1.1-124 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

(I) Steam Loss of material ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-368 3.1.1-012 A

Water Chemistry (B2.1.2)

IV.D1.RP-368 3.1.1-012 A

ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.R-31 3.1.1-044 A

Secondary manway cover PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

IV.C2.R-431 3.1.1-124 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

(I) Steam Loss of material ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-368 3.1.1-012 C

Water Chemistry (B2.1.2)

IV.D1.RP-368 3.1.1-012 C

Secondary manway cover bolting PB Steel (E) Air - indoor uncontrolled Cumulative fatigue damage TLAA IV.C2.R-18 3.1.1-005 A

Loss of material Bolting Integrity (B2.1.9)

IV.D1.RP-166 3.1.1-064 A

Loss of preload Bolting Integrity (B2.1.9)

IV.D1.RP-46 3.1.1-067 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

Table 3.1.2-4 Reactor Vessel, Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Subcomponent Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 35 of 115

Virgil C. Summer Nuclear Station Page 3-111 Supplement 1 Application for Subsequent License Renewal Secondary side shell (upper head and steam outlet nozzle)

PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

IV.C2.R-431 3.1.1-124 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

(I) Steam Cumulative fatigue damage TLAA IV.D1.R-33 3.1.1-005 A

Loss of material ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1)

IV.D1.RP-368 3.1.1-012 A

Water Chemistry (B2.1.2)

IV.D1.RP-368 3.1.1-012 A

Wall thinning Flow-Accelerated Corrosion (B2.1.8)

IV.D1.R-37 3.1.1-061 A

Steam flow limiter RF Nickel alloy (I) Steam Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 C

Cumulative fatigue damage TLAA IV.D1.R-46 3.1.1-002 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 CD Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 C

Support pad SS Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

IV.C2.R-431 3.1.1-124 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

IV.D1.R-17 3.1.1-049 A

Tube HT;PB Nickel alloy (I) Reactor coolant Cracking Steam Generators (B2.1.10)

IV.D1.R-44 3.1.1-070 AB Water Chemistry (B2.1.2)

IV.D1.R-44 3.1.1-070 A

Cumulative fatigue damage TLAA IV.D1.R-46 3.1.1-002 A

(E) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.R-47 3.1.1-069 AB Water Chemistry (B2.1.2)

IV.D1.R-47 3.1.1-069 A

Steam Generators (B2.1.10)

IV.D1.R-437 3.1.1-125 AB Loss of material Steam Generators (B2.1.10)

IV.D1.RP-233 3.1.1-077 AB TLAA IV.D1.RP-233 3.1.1-077 E, 4 Reduction of heat transfer Steam Generators (B2.1.10)

IV.D1.R-407 3.1.1-111 AB Water Chemistry (B2.1.2)

IV.D1.R-407 3.1.1-111 A

Table 3.1.2-4 Reactor Vessel, Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Subcomponent Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 36 of 115

Virgil C. Summer Nuclear Station Page 3-112 Supplement 1 Application for Subsequent License Renewal Tube bundle stay rod and spacer SS Steel (E) Treated water Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 AB Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 A

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 AB Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 A

Steam Generators (B2.1.10)

IV.D1.RP-225 3.1.1-076 AB Tube bundle support and baffle plate FD;SS Stainless steel (E) Treated water

>60°C (>140°F)

Cracking Steam Generators (B2.1.10)

IV.D1.RP-384 3.1.1-071 AB Water Chemistry (B2.1.2)

IV.D1.RP-384 3.1.1-071 A

Cumulative fatigue damage TLAA IV.C2.R-18 3.1.1-005 C

Loss of material Steam Generators (B2.1.10)

IV.D1.RP-226 3.1.1-071 AB Water Chemistry (B2.1.2)

IV.D1.RP-226 3.1.1-071 A

Steam Generators (B2.1.10)

IV.D1.RP-225 3.1.1-076 AB Tube bundle wrapper FD;SS Steel (E) Treated water Loss of material Steam Generators (B2.1.10)

IV.D1.RP-161 3.1.1-072 AB Water Chemistry (B2.1.2)

IV.D1.RP-161 3.1.1-072 A

Tube plug PB Nickel alloy (E) Reactor coolant Cracking Steam Generators (B2.1.10)

IV.D1.R-40 3.1.1-070 AB Water Chemistry (B2.1.2)

IV.D1.R-40 3.1.1-070 A

Cumulative fatigue damage TLAA IV.D1.R-46 3.1.1-002 C

Tubesheet PB Steel with nickel alloy cladding (I) Reactor coolant Cumulative fatigue damage TLAA IV.D1.R-221 3.1.1-008 A

Loss of material Steam Generators (B2.1.10)

IV.D1.R-436 3.1.1-127 AB Water Chemistry (B2.1.2)

IV.D1.R-436 3.1.1-127 A

(E) Treated water Loss of material Steam Generators (B2.1.10)

IV.D1.RP-161 3.1.1-072 CD Water Chemistry (B2.1.2)

IV.D1.RP-161 3.1.1-072 C

Tube-to-tubeshee t weld PB Nickel alloy (E) Reactor coolant Cracking Steam Generators (B2.1.10)

IV.D1.RP-385 3.1.1-025 AB Water Chemistry (B2.1.2)

IV.D1.RP-385 3.1.1-025 A

Cumulative fatigue damage TLAA IV.D1.R-221 3.1.1-008 A

Table 3.1.2-4 Reactor Vessel, Internals, and Reactor Coolant System - Steam Generators - Aging Management Evaluation Subcomponent Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 37 of 115

Page 3-197 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Aging Management Review 3.3.2.1.11 Domestic Water Materials The materials of construction for the domestic water system component types are:

Copper alloy Copper alloy (>15% Zn)

Stainless steel Steel Steel with internal lining Environment The domestic water system component types are exposed to the following environments:

Air - indoor uncontrolled Air with borated water leakage Concrete Raw water Aging Effects Requiring Management The following aging effects, associated with the domestic water system, require management:

Cracking Long-term loss of material Loss of coating or lining integrity Loss of material Loss of preload Serial No.24-101 Page 38 of 115

Page 3-200 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Aging Management Review 3.3.2.1.13 Fire Service Materials The materials of construction for the fire service system component types are:

Copper alloy Copper alloy (>15% Zn)

Ductile iron Ductile iron with internal coating Ductile iron with internal lining Gray cast iron Gray cast iron with internal lining Nickel alloy Polymer Stainless steel Steel Environment The fire service system component types are exposed to the following environments:

Air - indoor uncontrolled Air - outdoor Air with borated water leakage Diesel exhaust Fuel oil Gas Lubricating oil Raw water Soil Serial No.24-101 Page 39 of 115

Page 3-201 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Aging Management Review Aging Effects Requiring Management The following aging effects, associated with the fire service system, require management:

Cracking Cracking or blistering Flow blockage Hardening or loss of strength Long-term loss of material Loss of coating or lining integrity Loss of material Loss of material or cracking Loss of preload Aging Management Programs The following aging management programs manage the aging effects for the fire service system component types:

Bolting Integrity (B2.1.9)

Boric Acid Corrosion (B2.1.4)

Buried and Underground Piping and Tanks (B2.1.28)

External Surfaces Monitoring of Mechanical Components (B2.1.23)

Fire Protection (B2.1.15)

Fire Water System (B2.1.16)

Fuel Oil Chemistry (B2.1.18)

Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B2.1.29)

Lubricating Oil Analysis (B2.1.26)

One-Time Inspection (B2.1.20)

Selective Leaching (B2.1.21)

Serial No.24-101 Page 40 of 115

Page 3-246 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Aging Management Review

[3.3.1-202] - Loss of material and cracking of stainless steel components exposed to concrete is not an aging effect for components that are not potentially exposed to groundwater. Stainless steel piping components exposed to concrete in the spent fuel cooling and domestic water systems are embedded within interior concrete structures and are not potentially exposed to groundwater.

3.3.2.2.10 Loss of Material Due to Pitting and Crevice Corrosion in Aluminum Alloys Loss of material due to pitting and crevice corrosion could occur in aluminum piping, piping components, and tanks exposed to an air, condensation, underground, raw water, or waste water environment for a sufficient duration of time. Environments that can result in pitting and/or crevice corrosion of aluminum alloys are those that contain halides (e.g., chloride) in the presence of moisture. The moisture level and halide concentration in atmospheric and uncontrolled air are greatly dependent on geographical location and site-specific conditions. Moisture level and halide concentration should generally be considered high enough to facilitate pitting and/or crevice corrosion of aluminum alloys in atmospheric and uncontrolled air, unless demonstrated otherwise.

The periodic introduction of moisture or halides into an environment from secondary sources should also be considered. Leakage of fluids from mechanical connections (e.g., insulated bolted flanges and valve packing); onto a component in indoor controlled air is an example of a secondary source that should be considered. Halide concentrations should generally be considered high enough to facilitate loss of material of aluminum alloys in untreated aqueous solutions, unless demonstrated otherwise. Plant-specific OE and the condition of aluminum alloy components are evaluated to determine if prolonged exposure to the plant-specific air, condensation, underground, or water environments has resulted in pitting or crevice corrosion.

Loss of material due to pitting and crevice corrosion is not an aging effect requiring management for aluminum alloys if: (a) plant-specific OE does not reveal a history of loss of material due to pitting or crevice corrosion and (b) a one time inspection demonstrates that the aging effect is not occurring or is occurring so slowly that it will not affect the intended function of the components.

The applicant documents the results of the plant specific OE review in the SLRA.

In the environment of air-indoor controlled, pitting and crevice corrosion is only expected to occur as the result of a source of moisture and halides. Alloy susceptibility may be considered when reviewing OE and interpreting inspection results. Inspections focus on the most susceptible alloys and locations.

Serial No.24-101 Page 41 of 115

Virgil C. Summer Nuclear Station Page 3-264 Supplement 1 Application for Subsequent License Renewal 3.3.1-102 Boral; boron steel, and other materials (excluding Boraflex) spent fuel storage racks: neutron-absorbing sheets (PWR), spent fuel storage racks:

neutron-absorbing sheets (BWR) exposed to treated borated water, treated water Reduction of neutron-absorbing capacity; change in dimensions and loss of material due to effects of SFP environment AMP XI.M40, Monitoring of Neutron-Absorbing Materials other than Boraflex No Consistent with NUREG-2191. No Auxiliary Systems components are aligned to this item. Only components in Structures and Component Supports (Fuel Handling Building) are aligned to this item.

3.3.1-103 Concrete, concrete cylinder piping, reinforced concrete, asbestos cement, cementitious piping, piping components exposed to soil, concrete Cracking due to chemical reaction, weathering, or corrosion of reinforcement (reinforced concrete only); loss of material due to delamination, exfoliation, spalling, popout, or scaling AMP XI.M41, Buried and Underground Piping and Tanks No Not applicable. There are no in-scope concrete, concrete cylinder piping, reinforced concrete, asbestos cement, or cementitious piping, piping components exposed to soil or concrete in the Auxiliary Systems. The associated NUREG-2191 aging items are not used.

3.3.1-104 HDPE, fiberglass piping, piping components exposed to soil, concrete Cracking, blistering, loss of material due to exposure to ultraviolet light, ozone, radiation, temperature, or moisture AMP XI.M41, Buried and Underground Piping and Tanks No Not applicable. There are no in-scope HDPE or fiberglass piping, piping components exposed to soil or concrete in the Auxiliary Systems. The associated NUREG-2191 aging items are not used.

3.3.1-107 Stainless steel, nickel alloy piping, piping components exposed to soil, concrete Loss of material due to pitting, crevice corrosion, MIC (soil only)

AMP XI.M41, Buried and Underground Piping and Tanks No Not applicable. Loss of material of stainless steel reactor water makeup tank exposed to concrete is addressed in row 3.3.1-229. Aging of stainless steel spent fuel cooling and domestic water piping exposed to interior/above ground concrete that is not potentially exposed to groundwater is addressed in row 3.3.1-202. There are no other stainless steel or nickel alloy piping, piping components exposed to soil or concrete in the Auxiliary Systems. The associated NUREG-2191 aging items are not used.

Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 42 of 115

Virgil C. Summer Nuclear Station Page 3-291 Supplement 1 Application for Subsequent License Renewal 3.3.1-262 Titanium piping, piping components, heat exchanger components exposed to closed-cycle cooling water, treated water Cracking due to SCC AMP XI.M20, Open-Cycle Cooling Water System, or AMP XI.M21A, Closed Treated Water Systems, or AMP XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components No Not applicable. There are no in-scope titanium piping, piping components, or heat exchanger components exposed to closed-cycle cooling water or treated water in the Auxiliary Systems. The associated NUREG-2191 aging items are not used.

3.3.1-263 Polymeric piping, piping components, ducting, ducting components, seals exposed to air, condensation, raw water, raw water (potable), treated water, waste water, underground, concrete, soil Hardening or loss of strength due to polymeric degradation; loss of material due to peeling, delamination, wear; cracking or blistering due to exposure to ultraviolet light, ozone, radiation, or chemical attack; flow blockage due to fouling AMP XI.M36, External Surfaces Monitoring of Mechanical Components, or AMP XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components No Consistent with NUREG-2191. Hardening or loss of strength, loss of material, and cracking or blistering of polymeric components exposed to air - indoor uncontrolled (external) is managed by the External Surfaces Monitoring of Mechanical Components (B2.1.23) program. Hardening or loss of strength, loss of material, and cracking or blistering of polymeric components exposed to treated water or waste water (internal) is managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25) program. Hardening or loss of strength, loss of material, cracking or blistering, and flow blockage of polymeric components exposed to air - indoor uncontrolled (internal) is managed by the inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25) program.

3.3.1-265 Steel heat exchanger radiator tubes exposed to fuel oil Reduction of heat transfer due to fouling AMP XI.M30, Fuel Oil Chemistry, and AMP XI.M32, One-Time Inspection No Not applicable. There are no in-scope steel heat exchanger radiator tubes exposed to fuel oil in the Auxiliary Systems. The associated NUREG-2191 aging items are not used.

3.3.1-266 Steel heat exchanger radiator tubes exposed to fuel oil Reduction of heat transfer due to fouling AMP XI.M30, Fuel Oil Chemistry No Not applicable. There are no in-scope steel heat exchanger radiator tubes exposed to fuel oil in the Auxiliary Systems. The associated NUREG-2191 aging items are not used.

Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 43 of 115

Virgil C. Summer Nuclear Station Page 3-354 Supplement 1 Application for Subsequent License Renewal Expansion joint (tube)

PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Diesel exhaust Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.H2.AP-104 3.3.1-088 A

Filter housing (fuel oil)

PB;SI Gray cast iron (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Fuel oil Loss of material Fuel Oil Chemistry (B2.1.18)

VII.H2.AP-105a 3.3.1-070 A

Steel (E) Air - outdoor Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Fuel oil Loss of material Fuel Oil Chemistry (B2.1.18)

VII.H2.AP-105a 3.3.1-070 A

Filter housing (lube oil)

PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Lubricating oil Loss of material Lubricating Oil Analysis (B2.1.26)

VII.H2.AP-127 3.3.1-097 A

One-Time Inspection (B2.1.20)

VII.H2.AP-127 3.3.1-097 A

Filter silencer body PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Air - indoor uncontrolled Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.F1.A-778 3.3.1-249 C

Flame arrestor PBFB Aluminum (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.H2.A-451a 3.3.1-189 A

Loss of material One-Time Inspection (B2.1.20)

VII.H2.A-763a 3.3.1-234 A

(I) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.H2.A-451a 3.3.1-189 A

Loss of material One-Time Inspection (B2.1.20)

VII.H2.A-763a 3.3.1-234 A

(E) Air - outdoor Cracking One-Time Inspection (B2.1.20)

VII.H2.A-451a 3.3.1-189 A

Loss of material One-Time Inspection (B2.1.20)

VII.H2.A-763a 3.3.1-234 A

Table 3.3.2-10 Auxiliary Systems - Diesel Generator Services - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 44 of 115

Virgil C. Summer Nuclear Station Page 3-360 Supplement 1 Application for Subsequent License Renewal Piping, piping components LB;PB;SI Steel (I) Air - dry Loss of material Compressed Air Monitoring (B2.1.14)

VII.D.A-764 3.3.1-235 A

(E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Air - indoor uncontrolled Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.F1.A-778 3.3.1-249 C

(E) Air - outdoor Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.H2.AP-202 3.3.1-045 A

(I) Condensation Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.H2.A-26 3.3.1-055 A

(I) Diesel exhaust Cumulative fatigue damage TLAA VII.E1.A-34 3.3.1-002 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.H2.AP-104 3.3.1-088 A

(E) Fuel oil Loss of material Fuel Oil Chemistry (B2.1.18)

VII.H2.AP-105a 3.3.1-070 A

(I) Fuel oil Loss of material Fuel Oil Chemistry (B2.1.18)

VII.H2.AP-105a 3.3.1-070 A

(I) Gas None None VII.J.AP-6 3.3.1-121 A

(I) Lubricating oil Loss of material Lubricating Oil Analysis (B2.1.26)

VII.H2.AP-127 3.3.1-097 A

One-Time Inspection (B2.1.20)

VII.H2.AP-127 3.3.1-097 A

(I) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.C1.A-532 3.3.1-193 A

Loss of material; flow blockage Open-Cycle Cooling Water System (B2.1.11)

VII.H2.AP-194 3.3.1-037 A

(E) Soil Loss of material Buried and Underground Piping and Tanks (B2.1.28)

VII.I.AP-198 3.3.1-109 A

(I) Waste water Long-term loss of material One-Time Inspection (B2.1.20)

VII.E5.A-785 3.3.1-193 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-281 3.3.1-091 A, 1 Pump casing (fuel oil transfer)

PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Fuel oil Loss of material Fuel Oil Chemistry (B2.1.18)

VII.H2.AP-105a 3.3.1-070 A

Table 3.3.2-10 Auxiliary Systems - Diesel Generator Services - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 45 of 115

Virgil C. Summer Nuclear Station Page 3-362 Supplement 1 Application for Subsequent License Renewal Sight glass LB;PB Glass (I) Air - dry None None VII.J.AP-48 3.3.1-117 A

(E) Air - indoor uncontrolled None None VII.J.AP-48 3.3.1-117 A

(I) Closed-cycle cooling water None None VII.J.AP-166 3.3.1-117 A

(I) Condensation None None VII.J.AP-97 3.3.1-117 A

(I) Lubricating oil None None VII.J.AP-15 3.3.1-117 A

(I) Waste water None None VII.J.AP-277 3.3.1-119 A

Sight glass (body)

LB;PB Copper alloy

(>15% Zn)

(E) Air - indoor uncontrolled Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)

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

(I) Lubricating oil Loss of material Lubricating Oil Analysis (B2.1.26)

VII.H2.AP-133 3.3.1-099 A

One-Time Inspection (B2.1.20)

VII.H2.AP-133 3.3.1-099 A

(I) Waste water Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-473c 3.3.1-160 A

Loss of material Selective Leaching (B2.1.21)

VII.E5.A-547 3.3.1-072 A

Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-272 3.3.1-095 A, 1 Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.H2.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.H2.AP-221a 3.3.1-006 A

(I) Condensation Cracking One-Time Inspection (B2.1.20)

VII.H2.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.H2.AP-221a 3.3.1-006 A

Steel (I) Air - dry Loss of material Compressed Air Monitoring (B2.1.14)

VII.D.A-764 3.3.1-235 A

(E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.H2.AP-202 3.3.1-045 A

Table 3.3.2-10 Auxiliary Systems - Diesel Generator Services - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 46 of 115

Virgil C. Summer Nuclear Station Page 3-365 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-10 Plant-Specific Notes: None 1.

Delivery of downstream flow is not credited.

Valve body LB;PB;SI Stainless steel (I) Fuel oil Loss of material One-Time Inspection (B2.1.20)

VII.H2.AP-136 3.3.1-071 A

(I) Lubricating oil Loss of material Lubricating Oil Analysis (B2.1.26)

VII.H2.AP-138 3.3.1-100 A

One-Time Inspection (B2.1.20)

VII.H2.AP-138 3.3.1-100 A

(I) Raw water Loss of material; flow blockage Open-Cycle Cooling Water System (B2.1.11)

VII.H2.AP-55 3.3.1-040 A

Steel (I) Air - dry Loss of material Compressed Air Monitoring (B2.1.14)

VII.D.A-764 3.3.1-235 A

(E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Air - indoor uncontrolled Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.F1.A-778 3.3.1-249 C

(E) Air - outdoor Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.H2.AP-202 3.3.1-045 A

(E) Fuel oil Loss of material Fuel Oil Chemistry (B2.1.18)

VII.H2.AP-105a 3.3.1-070 A

(I) Fuel oil Loss of material Fuel Oil Chemistry (B2.1.18)

VII.H2.AP-105a 3.3.1-070 A

(I) Lubricating oil Loss of material Lubricating Oil Analysis (B2.1.26)

VII.H2.AP-127 3.3.1-097 A

One-Time Inspection (B2.1.20)

VII.H2.AP-127 3.3.1-097 A

(I) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.C1.A-532 3.3.1-193 A

Loss of material; flow blockage Open-Cycle Cooling Water System (B2.1.11)

VII.H2.AP-194 3.3.1-037 A

(I) Waste water Long-term loss of material One-Time Inspection (B2.1.20)

VII.E5.A-785 3.3.1-193 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-281 3.3.1-091 A, 1 Table 3.3.2-10 Auxiliary Systems - Diesel Generator Services - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 47 of 115

Virgil C. Summer Nuclear Station Page 3-366 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-11 Auxiliary Systems - Domestic Water - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Bolting LB Steel (E) Air - indoor uncontrolled Loss of material Bolting Integrity (B2.1.9)

VII.I.A-03 3.3.1-012 A

Loss of preload Bolting Integrity (B2.1.9)

VII.I.AP-124 3.3.1-015 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

Eyewash - safety shower (stanchion)

LB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.G.A-532 3.3.1-193 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-270 3.3.1-088 A

Eyewash - safety shower (valve body)

LB Copper alloy

(>15% Zn)

(E) Air - indoor uncontrolled Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)

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

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.AP-66 3.3.1-009 A

(I) Raw water Loss of material Selective Leaching (B2.1.21)

VII.G.A-47 3.3.1-072 A

Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-271 3.3.1-093 A

Orifice LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.C1.AP-221a 3.3.1-006 A

(I) Raw water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-270 3.3.1-088 A

Piping, piping components LB Copper alloy (E) Air - indoor uncontrolled None None VII.J.AP-144 3.3.1-114 A

(I) Raw water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-271 3.3.1-093 A

Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.C1.AP-221a 3.3.1-006 A

(I) Raw water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-270 3.3.1-088 A

(E) Concrete None None VII.J.AP-19 3.3.1-202 A,1 Serial No.24-101 Page 48 of 115

Virgil C. Summer Nuclear Station Page 3-367 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-11 Plant-Specific Notes: None 1.

Piping is embedded within interior concrete that is not potentially exposed to groundwater.

2.

1.5 gallon water heater is lined with glasteel. Lining is not credited; the only component function is leakage boundary, and delivery of downstream flow is not credited. Potential degradation of the lining cannot affect other components.

Pump casing (hot water recirculating)

LB Copper alloy (E) Air - indoor uncontrolled None None VII.J.AP-144 3.3.1-114 A

(I) Raw water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-271 3.3.1-093 A

Tank (hot water)

LB Steel with internal lining (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Raw water Loss of coating or lining integrity Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B2.1.29)

VII.C1.A-416 3.3.1-138 A

Loss of material Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B2.1.29)

VII.C1.A-414 3.3.1-139 A

Tank (water heater)

LB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

Tank (water heater)

LB Steel (I) Raw water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-270 3.3.1-088 A,2 Tank (water heater)

LB Steel (I) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.G.A-532 3.3.1-193 A,2 Valve body LB Copper alloy (E) Air - indoor uncontrolled None None VII.J.AP-144 3.3.1-114 A

(I) Raw water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-271 3.3.1-093 A

Waterhammer arrestor LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.C1.AP-221a 3.3.1-006 A

(I) Raw water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-270 3.3.1-088 A

Table 3.3.2-11 Auxiliary Systems - Domestic Water - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 49 of 115 I-------+--------+-------+-----+-----+------------+----------+-----+-~

I I

Virgil C. Summer Nuclear Station Page 3-371 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-13 Auxiliary Systems - Fire Service - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Bolting PB Stainless steel (E) Raw water Loss of material Bolting Integrity (B2.1.9)

VII.I.A-423 3.3.1-142 A

Loss of preload Bolting Integrity (B2.1.9)

VII.I.AP-124 3.3.1-015 A

Steel (E) Air - indoor uncontrolled Loss of material Bolting Integrity (B2.1.9)

VII.I.A-03 3.3.1-012 A

Loss of preload Bolting Integrity (B2.1.9)

VII.I.AP-124 3.3.1-015 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(E) Raw water Loss of material Bolting Integrity (B2.1.9)

VII.I.A-423 3.3.1-142 A

Loss of preload Bolting Integrity (B2.1.9)

VII.I.AP-124 3.3.1-015 A

(E) Soil Loss of material Buried and Underground Piping and Tanks (B2.1.28)

VII.I.AP-241 3.3.1-109 A

Loss of preload Bolting Integrity (B2.1.9)

VII.I.AP-124 3.3.1-015 A

Exhaust silencer PB Steel (E) Air - outdoor Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Diesel exhaust Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.H2.AP-104 3.3.1-088 A

Flame arrestor PBFB Steel (I) Air - indoor uncontrolled Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.F4.A-778 3.3.1-249 C

(E) Air - outdoor Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

Flexible hose PB Copper alloy

(>15% Zn)

(E) Air - indoor uncontrolled Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)

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

(I) Fuel oil Loss of material Fuel Oil Chemistry (B2.1.18)

VII.G.AP-132 3.3.1-069 A

One-Time Inspection (B2.1.20)

VII.G.AP-132 3.3.1-069 A

Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

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

Loss of material One-Time Inspection (B2.1.20)

VII.G.AP-221a 3.3.1-006 A

(I) Diesel exhaust Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.H2.AP-128 3.3.1-083 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.H2.AP-104 3.3.1-088 A

(I) Raw water Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.A-55 3.3.1-066 A

Serial No.24-101 Page 50 of 115

Virgil C. Summer Nuclear Station Page 3-373 Supplement 1 Application for Subsequent License Renewal Piping, piping components LB;PB Ductile iron with internal lining (I) Raw water Loss of coating or lining integrity; loss of material or cracking (for cementitious coatings/linings)

Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B2.1.29)

VII.G.A-416 3.3.1-138 A

Loss of material Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B2.1.29)

VII.G.A-414 3.3.1-139 A

VII.G.A-415 3.3.1-140 A

(E) Soil Loss of material Selective Leaching (B2.1.21)

VII.G.A-02 3.3.1-072 A

Buried and Underground Piping and Tanks (B2.1.28)

VII.I.AP-198 3.3.1-109 A

Gray cast iron (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.G.A-532 3.3.1-193 A

Loss of material Selective Leaching (B2.1.21)

VII.G.A-51 3.3.1-072 A

Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.A-33 3.3.1-064 A

(E) Soil Loss of material Selective Leaching (B2.1.21)

VII.G.A-02 3.3.1-072 A, 5 Buried and Underground Piping and Tanks (B2.1.28)

VII.I.AP-198 3.3.1-109 A, 5 Gray cast iron with internal lining (I) Raw water Loss of coating or lining integrity; loss of material or cracking (for cementitious coatings/linings)

Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B2.1.29)

VII.G.A-416 3.3.1-138 A

Loss of material Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks (B2.1.29)

VII.G.A-414 3.3.1-139 A

VII.G.A-415 3.3.1-140 A

(E) Soil Loss of material Selective Leaching (B2.1.21)

VII.G.A-02 3.3.1-072 A, 5 Buried and Underground Piping and Tanks (B2.1.28)

VII.I.AP-198 3.3.1-109 A, 5 Polymer (E) Air - indoor uncontrolled Hardening or loss of strength; loss of material; cracking or blistering External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-797a 3.3.1-263 A

Table 3.3.2-13 Auxiliary Systems - Fire Service - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 51 of 115 I

Virgil C. Summer Nuclear Station Page 3-374 Supplement 1 Application for Subsequent License Renewal Piping, piping components LB;PB Polymer (I) Air - indoor uncontrolled Hardening or loss of strength; loss of material; cracking or blistering; flow blockage Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.F1.A-797b 3.3.1-263 A

Stainless steel Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

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

Loss of material One-Time Inspection (B2.1.20)

VII.G.AP-221a 3.3.1-006 A

(E) Air - outdoor Cracking One-Time Inspection (B2.1.20)

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

Loss of material One-Time Inspection (B2.1.20)

VII.G.AP-221a 3.3.1-006 A

(I) Fuel oil Loss of material Fuel Oil Chemistry (B2.1.18)

VII.G.AP-136 3.3.1-071 A

One-Time Inspection (B2.1.20)

VII.G.AP-136 3.3.1-071 A

(I) Raw water Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.A-55 3.3.1-066 A

Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Air - indoor uncontrolled Flow blockage Fire Water System (B2.1.16)

VII.G.A-404 3.3.1-131 A

Loss of material Fire Protection (B2.1.15)

VII.G.AP-150 3.3.1-058 A, 4 Fire Water System (B2.1.16)

VII.G.A-403 3.3.1-130 C

(E) Air - outdoor Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Diesel exhaust Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.H2.AP-104 3.3.1-088 A

(I) Fuel oil Loss of material Fuel Oil Chemistry (B2.1.18)

VII.G.AP-234a 3.3.1-070 A

(I) Gas None None VII.J.AP-6 3.3.1-121 A

(I) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.G.A-532 3.3.1-193 A

Loss of material Fire Water System (B2.1.16)

VII.G.A-400c 3.3.1-127 A

Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.A-33 3.3.1-064 A, 1 Table 3.3.2-13 Auxiliary Systems - Fire Service - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 52 of 115

Virgil C. Summer Nuclear Station Page 3-375 Supplement 1 Application for Subsequent License Renewal Piping, piping components (spectacle flange)

PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

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

Loss of material One-Time Inspection (B2.1.20)

VII.G.AP-221a 3.3.1-006 A

(I) Raw water Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.A-55 3.3.1-066 A

Pump casing (jockey)

PB Gray cast iron (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.G.A-532 3.3.1-193 A

Loss of material Selective Leaching (B2.1.21)

VII.G.A-51 3.3.1-072 A

Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.A-33 3.3.1-064 A

Pump casing (motor-and engine-driven column)

PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.G.A-532 3.3.1-193 A

Loss of material Fire Water System (B2.1.16)

VII.G.A-33 3.3.1-064 A

(I) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.G.A-532 3.3.1-193 A

Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.A-33 3.3.1-064 A

Pump casing (motor-and engine-driven)

PB Gray cast iron (E) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.G.A-532 3.3.1-193 A

Loss of material Fire Water System (B2.1.16)

VII.G.A-33 3.3.1-064 A

Selective Leaching (B2.1.21)

VII.G.A-51 3.3.1-072 A

(I) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.G.A-532 3.3.1-193 A

Loss of material Selective Leaching (B2.1.21)

VII.G.A-51 3.3.1-072 A

Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.A-33 3.3.1-064 A

Spray Nozzle FD Copper alloy

(>15% Zn)

(E) Air - indoor uncontrolled Loss of material Fire Water System (B2.1.16)

VII.G.A-403 3.3.1-130 A

Spray Nozzle FD Copper alloy

(>15% Zn)

(I) Air - indoor uncontrolled Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.A-403 3.3.1-130 A

Table 3.3.2-13 Auxiliary Systems - Fire Service - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 53 of 115 I

I

Virgil C. Summer Nuclear Station Page 3-378 Supplement 1 Application for Subsequent License Renewal Strainer element FLT Copper alloy

(>15% Zn)

(E) Raw water Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.C1.A-473b 3.3.1-160 E, 3 Loss of material Fire Water System (B2.1.16)

VII.G.AP-197 3.3.1-064 A

Selective Leaching (B2.1.21)

VII.G.A-47 3.3.1-072 A

Nickel alloy (E) Raw water Loss of material Fire Water System (B2.1.16)

VII.G.A-403 3.3.1-130 AC Stainless steel (E) Raw water Loss of material Fire Water System (B2.1.16)

VII.G.A-55 3.3.1-066 A

Strainer element (fire pump suction)

FLT Copper alloy (E) Raw water Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.AP-197 3.3.1-064 A

Tank (diesel fire pump fuel oil)

PB Steel (E) Air - outdoor Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Fuel oil Loss of material Fuel Oil Chemistry (B2.1.18)

VII.G.AP-234a 3.3.1-070 A

Tank (low pressure carbon dioxide)

PB Steel (E) Air - outdoor Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Gas None None VII.J.AP-6 3.3.1-121 A

Tank (retarding chamber)

PB Gray cast iron (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Raw water Long-term loss of material One-Time Inspection (B2.1.20)

VII.G.A-532 3.3.1-193 A

Loss of material Selective Leaching (B2.1.21)

VII.G.A-51 3.3.1-072 A

Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.A-33 3.3.1-064 A

Valve body LB;PB Copper alloy (E) Air - indoor uncontrolled None None VII.J.AP-144 3.3.1-114 A

(I) Raw water Loss of material; flow blockage Fire Water System (B2.1.16)

VII.G.AP-197 3.3.1-064 A, 1 Table 3.3.2-13 Auxiliary Systems - Fire Service - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 54 of 115

Virgil C. Summer Nuclear Station Page 3-383 Supplement 1 Application for Subsequent License Renewal Fuel transfer tube (penetration sleeve)

PB;SS Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C1.AP-209a 3.3.1-004 A, 2 Loss of material One-Time Inspection (B2.1.20)

VII.C1.AP-221a 3.3.1-006 A, 2 (I) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C1.AP-209a 3.3.1-004 A, 2 Loss of material One-Time Inspection (B2.1.20)

VII.C1.AP-221a 3.3.1-006 A, 2 Steel (E) Air - indoor uncontrolled Loss of material ASME Section XI, Subsection IWE (B2.1.30) 10 CFR Part 50, Appendix J (B2.1.33)

II.A3.C-16 3.5.1-028 C, 1 ASME Section XI, Subsection IWE (B2.1.30)

II.A3.C-16 3.5.1-028 C, 1 (I) Air - indoor uncontrolled Loss of material 10 CFR Part 50, Appendix J (B2.1.33)

II.A3.C-16 3.5.1-028 C, 1 ASME Section XI, Subsection IWE (B2.1.30)

II.A3.C-16 3.5.1-028 C, 1 (E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

Gate seal PB Elastomer (I) Air - dry Hardening or loss of strength Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E1.A-504 3.3.1-085 A

(E) Air - indoor uncontrolled Hardening or loss of strength External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.AP-102 3.3.1-076 A

(E) Treated borated water Hardening or loss of strength External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.A3.AP-100 3.3.1-085 E, 3 Piping, piping components LB;PB;SI Stainless steel (I) Air - dry Loss of material Compressed Air Monitoring (B2.1.14)

VII.D.A-764 3.3.1-235 A

(E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.C1.AP-221a 3.3.1-006 A

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

Pulsation dampener (upender hydraulic)

LB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Treated water Long-term loss of material One-Time Inspection (B2.1.20)

VII.C2.A-439 3.3.1-193 A

Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-73 3.4.1-014 A

Water Chemistry (B2.1.2)

VIII.E.SP-73 3.4.1-014 A

Pump casing (upender hydraulic -

cylinder)

LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.C1.AP-221a 3.3.1-006 A

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

Table 3.3.2-14 Auxiliary Systems - Fuel Handling - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 55 of 115

Virgil C. Summer Nuclear Station Page 3-387 Supplement 1 Application for Subsequent License Renewal Heat exchanger (compressor -

tubesheet)

PB Stainless steel (I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 C

(E) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-80 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-80 3.4.1-085 A

Heat exchanger (recombiner cooler condenser

- channel)

PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C2.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.C2.AP-221a 3.3.1-006 C

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-275 3.3.1-095 A, 1, 2

Heat exchanger (recombiner cooler condenser

- shell)

PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.AP-189 3.3.1-046 A

Heat exchanger (recombiner cooler condenser

- tube)

PB Stainless steel (E) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 C

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-275 3.3.1-095 A, 1, 2

Heat exchanger (recombiner cooler condenser

- tubesheet)

PB Stainless steel (E) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 C

(I) Gas None None VII.J.AP-22 3.3.1-120 C

Orifice LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C2.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.C2.AP-221a 3.3.1-006 A

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

Table 3.3.2-15 Auxiliary Systems - Gaseous Waste Processing - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 56 of 115 I

I

Virgil C. Summer Nuclear Station Page 3-388 Supplement 1 Application for Subsequent License Renewal Piping, piping components LB;PB;SI Copper alloy (E) Air - indoor uncontrolled None None VII.J.AP-144 3.3.1-114 A

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.F.SP-101 3.4.1-016 A

Water Chemistry (B2.1.2)

VIII.F.SP-101 3.4.1-016 A

Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C2.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.C2.AP-221a 3.3.1-006 A

(I) Gas None None VII.J.AP-22 3.3.1-120 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1, 2

Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Air - indoor uncontrolled Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.F2.A-778 3.3.1-249 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.AP-202 3.3.1-045 A

(I) Gas None None VII.J.AP-6 3.3.1-121 A

(I) Treated water Long-term loss of material One-Time Inspection (B2.1.20)

VII.C2.A-439 3.3.1-193 A

Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-73 3.4.1-014 A

Water Chemistry (B2.1.2)

VIII.E.SP-73 3.4.1-014 A

(I) Waste water Long-term loss of material One-Time Inspection (B2.1.20)

VII.E5.A-785 3.3.1-193 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-281 3.3.1-091 A, 1, 2

Pump casing (decay tank drain)

LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C2.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.C2.AP-221a 3.3.1-006 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1 Table 3.3.2-15 Auxiliary Systems - Gaseous Waste Processing - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 57 of 115 I

I

Virgil C. Summer Nuclear Station Page 3-390 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-15 Plant-Specific Notes:

1.

This waste water environment is associated with primary system gaseous waste condensation, or the product of hydrogen recombiners. It is not expected to contain contaminants, but is not monitored by the Water Chemistry (B2.1.2) program. The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25) program will manage loss of material in this environment.

2.

Delivery of downstream flow is not credited.

Valve body LB;PB;SI Copper alloy

(>15% Zn)

(E) Air - indoor uncontrolled Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)

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

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.AP-66 3.3.1-009 A

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.F.SP-101 3.4.1-016 A

Water Chemistry (B2.1.2)

VIII.F.SP-101 3.4.1-016 A

Selective Leaching (B2.1.21)

VII.C2.AP-32 3.3.1-072 A

Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.C2.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.C2.AP-221a 3.3.1-006 A

(I) Gas None None VII.J.AP-22 3.3.1-120 A

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1, 2

Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.AP-202 3.3.1-045 A

(I) Treated water Long-term loss of material One-Time Inspection (B2.1.20)

VII.C2.A-439 3.3.1-193 A

Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-73 3.4.1-014 A

Water Chemistry (B2.1.2)

VIII.E.SP-73 3.4.1-014 A

(I) Waste water Long-term loss of material One-Time Inspection (B2.1.20)

VII.E5.A-785 3.3.1-193 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-281 3.3.1-091 A, 1, 2

Table 3.3.2-15 Auxiliary Systems - Gaseous Waste Processing - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 58 of 115 I

I

===================

Virgil C. Summer Nuclear Station Page 3-399 Supplement 1 Application for Subsequent License Renewal Heat exchanger (reactor building instrument air dryer condenser -

channel)

LB Copper alloy

(>15% Zn)

(E) Air - indoor uncontrolled Cracking External Surfaces Monitoring of Mechanical Components (B2.1.23)

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

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.AP-66 3.3.1-009 C

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.AP-199 3.3.1-046 C

Selective Leaching (B2.1.21)

VII.C2.AP-43 3.3.1-072 C

Piping, piping components LB;PB;SI Copper alloy (E) Air - indoor uncontrolled None None VII.J.AP-144 3.3.1-114 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.AP-199 3.3.1-046 A

Stainless steel (I) Air - dry Loss of material Compressed Air Monitoring (B2.1.14)

VII.D.A-764 3.3.1-235 A

(E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

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

Loss of material One-Time Inspection (B2.1.20)

VII.D.AP-221a 3.3.1-006 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1 Steel (I) Air - dry Loss of material Compressed Air Monitoring (B2.1.14)

VII.D.A-764 3.3.1-235 A

(E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Air - indoor uncontrolled Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.C1.A-778 3.3.1-249 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Waste water Long-term loss of material One-Time Inspection (B2.1.20)

VII.E5.A-785 3.3.1-193 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-281 3.3.1-091 A, 1 Strainer body LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

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

Loss of material One-Time Inspection (B2.1.20)

VII.D.AP-221a 3.3.1-006 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 A

Table 3.3.2-19 Auxiliary Systems - Instrument Air - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 59 of 115

Virgil C. Summer Nuclear Station Page 3-400 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-19 Plant-Specific Notes: None 1.

Delivery of downstream flow is not credited.

Tank (portable bottle for local valve operation)

PB Steel (I) Air - dry Loss of material Compressed Air Monitoring (B2.1.14)

VII.D.A-764 3.3.1-235 A

(E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

Trap body LB Aluminum (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.D.A-451a 3.3.1-189 A

Loss of material One-Time Inspection (B2.1.20)

VII.F3.A-763a 3.3.1-234 A

(I) Waste water Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-451c 3.3.1-189 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-776c 3.3.1-247 A

Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

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

Loss of material One-Time Inspection (B2.1.20)

VII.D.AP-221a 3.3.1-006 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A

Valve body LB;PB;SI Stainless steel (I) Air - dry Loss of material Compressed Air Monitoring (B2.1.14)

VII.D.A-764 3.3.1-235 A

(E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

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

Loss of material One-Time Inspection (B2.1.20)

VII.D.AP-221a 3.3.1-006 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 A

Steel (I) Air - dry Loss of material Compressed Air Monitoring (B2.1.14)

VII.D.A-764 3.3.1-235 A

(E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(I) Air - indoor uncontrolled Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.C1.A-778 3.3.1-249 C

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Waste water Long-term loss of material One-Time Inspection (B2.1.20)

VII.E5.A-785 3.3.1-193 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-281 3.3.1-091 A, 1 Table 3.3.2-19 Auxiliary Systems - Instrument Air - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 60 of 115

Virgil C. Summer Nuclear Station Page 3-404 Supplement 1 Application for Subsequent License Renewal Heat exchanger (concentrates sample cooler -

channel)

PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.F2.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.F2.A-770a 3.3.1-241 A

(I) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 C

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-275 3.3.1-095 A, 1 Heat exchanger (concentrates sample cooler -

shell)

PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.AP-189 3.3.1-046 A

Heat exchanger (concentrates sample cooler -

tube and tubesheet)

PB Stainless steel (E) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 C

(I) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 C

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-275 3.3.1-095 A, 1 Heat exchanger (evaporator -

channel)

LB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Treated water Long-term loss of material One-Time Inspection (B2.1.20)

VII.E1.A-439 3.3.1-193 A

Loss of material One-Time Inspection (B2.1.20)

VIII.B1.SP-74 3.4.1-014 C

Water Chemistry (B2.1.2)

VIII.B1.SP-74 3.4.1-014 C

Heat exchanger (evaporator -

shell)

LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.F2.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.F2.A-770a 3.3.1-241 A

(I) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 C

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-275 3.3.1-095 A

Table 3.3.2-22 Auxiliary Systems - Liquid Waste Processing - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 61 of 115

Virgil C. Summer Nuclear Station Page 3-405 Supplement 1 Application for Subsequent License Renewal Heat exchanger (evaporator condenser -

channel)

PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.AP-189 3.3.1-046 A

Heat exchanger (evaporator condenser -

shell)

PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.F2.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.F2.A-770a 3.3.1-241 A

(I) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 C

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-275 3.3.1-095 A, 1 Heat exchanger (evaporator condenser - tube and tubesheet)

PB Stainless steel (I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 C

(E) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 C

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-275 3.3.1-095 A, 1 Heat exchanger (evaporator distillate cooler -

channel)

PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.F2.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.F2.A-770a 3.3.1-241 A

(I) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 C

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-275 3.3.1-095 A, 1 Heat exchanger (evaporator distillate cooler -

shell)

PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.F2.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.F2.A-770a 3.3.1-241 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 C

Table 3.3.2-22 Auxiliary Systems - Liquid Waste Processing - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 62 of 115

Virgil C. Summer Nuclear Station Page 3-406 Supplement 1 Application for Subsequent License Renewal Heat exchanger (evaporator distillate cooler -

tube and tubesheet)

PB Stainless steel (E) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 C

(I) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 C

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-275 3.3.1-095 A, 1 Heat exchanger (evaporator feed preheater -

channel)

LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.F2.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.F2.A-770a 3.3.1-241 A

(I) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 C

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-275 3.3.1-095 A

Heat exchanger (evaporator feed preheater - shell)

LB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Treated water Long-term loss of material One-Time Inspection (B2.1.20)

VII.E1.A-439 3.3.1-193 A

Loss of material One-Time Inspection (B2.1.20)

VIII.B1.SP-74 3.4.1-014 C

Water Chemistry (B2.1.2)

VIII.B1.SP-74 3.4.1-014 C

Heat exchanger (evaporator vent condenser -

channel)

PB Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.AP-189 3.3.1-046 A

Heat exchanger (evaporator vent condenser -

shell)

PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.F2.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.F2.A-770a 3.3.1-241 A

(I) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 C

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-275 3.3.1-095 A, 1 Table 3.3.2-22 Auxiliary Systems - Liquid Waste Processing - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 63 of 115

Virgil C. Summer Nuclear Station Page 3-408 Supplement 1 Application for Subsequent License Renewal Piping, piping components LB;PB;SI Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.F2.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.F2.AP-221a 3.3.1-006 A

(I) Steam Cracking One-Time Inspection (B2.1.20)

VII.F2.A-748 3.3.1-219 A

Water Chemistry (B2.1.2)

VII.F2.A-748 3.3.1-219 A

Cumulative fatigue damage TLAA VII.E1.A-57 3.3.1-002 A

Loss of material One-Time Inspection (B2.1.20)

VII.F2.A-567 3.3.1-170 A

Water Chemistry (B2.1.2)

VII.F2.A-567 3.3.1-170 A

(I) Treated borated water Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

Wall thinning Flow-Accelerated Corrosion (B2.1.8)

VII.E1.A-407 3.3.1-126 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1 (I) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1 Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Gas None None VII.J.AP-6 3.3.1-121 A

Pump casing (chemical drain tank)

LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.F2.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.F2.AP-221a 3.3.1-006 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A

Pump casing (evaporator concentrates)

LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.F2.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.F2.AP-221a 3.3.1-006 A

(I) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A

Table 3.3.2-22 Auxiliary Systems - Liquid Waste Processing - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 64 of 115

Virgil C. Summer Nuclear Station Page 3-412 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-22 Plant-Specific Notes: None 1.

Delivery of downstream flow is not credited.

Valve body LB;PB;SI Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.F2.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.F2.AP-221a 3.3.1-006 A

(I) Steam Cracking One-Time Inspection (B2.1.20)

VII.F2.A-748 3.3.1-219 A

Water Chemistry (B2.1.2)

VII.F2.A-748 3.3.1-219 A

Loss of material One-Time Inspection (B2.1.20)

VII.F2.A-567 3.3.1-170 A

Water Chemistry (B2.1.2)

VII.F2.A-567 3.3.1-170 A

(I) Treated borated water Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1 (I) Waste water

>60°C (>140°F)

Cracking Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.A-721 3.3.1-155 A

Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1 Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Gas None None VII.J.AP-6 3.3.1-121 A

(I) Treated water Long-term loss of material One-Time Inspection (B2.1.20)

VII.E1.A-439 3.3.1-193 A

Loss of material One-Time Inspection (B2.1.20)

VIII.B1.SP-74 3.4.1-014 A

Water Chemistry (B2.1.2)

VIII.B1.SP-74 3.4.1-014 A

Table 3.3.2-22 Auxiliary Systems - Liquid Waste Processing - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 65 of 115

Virgil C. Summer Nuclear Station Page 3-415 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-25 Auxiliary Systems - Nuclear and Miscellaneous Drains - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Bolting LB;PB Stainless steel (E) Waste water Cracking Bolting Integrity (B2.1.9)

VII.I.A-426 3.3.1-145 A

Loss of material Bolting Integrity (B2.1.9)

VII.I.A-423 3.3.1-142 A

Loss of preload Bolting Integrity (B2.1.9)

VII.I.AP-124 3.3.1-015 A

Steel (E) Air - indoor uncontrolled Loss of material Bolting Integrity (B2.1.9)

VII.I.A-03 3.3.1-012 A

Loss of preload Bolting Integrity (B2.1.9)

VII.I.AP-124 3.3.1-015 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(E) Waste water Loss of material Bolting Integrity (B2.1.9)

VII.I.A-423 3.3.1-142 A

Loss of preload Bolting Integrity (B2.1.9)

VII.I.AP-124 3.3.1-015 A

Level glass LB Glass (E) Air - indoor uncontrolled None None VII.J.AP-48 3.3.1-117 A

(I) Waste water None None VII.J.AP-277 3.3.1-119 A

Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A

Orifice LB;PB;RF Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 3 Serial No.24-101 Page 66 of 115

Virgil C. Summer Nuclear Station Page 3-418 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-25 Plant-Specific Notes:

1.

Flow blockage is not applicable to piping components with a leakage boundary function (i.e., those that do not support a function of delivering downstream flow).

2.

Piping is embedded within interior concrete that is not potentially exposed to groundwater.

3.

Delivery of downstream flow is not credited.

Tank (waste drain)

LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A

Valve body LB;PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Treated borated water Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

(I) Waste water Loss of material; flow blockage Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1 Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Waste water Long-term loss of material One-Time Inspection (B2.1.20)

VII.E5.A-785 3.3.1-193 A

Loss of material; flow blockage Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-281 3.3.1-091 A, 1 Table 3.3.2-25 Auxiliary Systems - Nuclear and Miscellaneous Drains - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 67 of 115

Virgil C. Summer Nuclear Station Page 3-420 Supplement 1 Application for Subsequent License Renewal Flow element LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Treated borated water Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

Heat exchanger (auxiliary sample cooler - shell)

LB Stainless steel (I) Closed-cycle coolingTreated water Loss of material Closed Treated Water Systems (B2.1.12)

Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.C2.A-52 VIII.E.SP-80 3.3.1-049 3.4.1-085 C

E, 1 (E) Condensation Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 C

Steel (E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Closed-cycle coolingTreated water Loss of material Closed Treated Water Systems (B2.1.12)

Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.C2.AP-189 VIII.E.SP-77 3.3.1-046 3.4.1-015 A

E, 1 (E) Condensation Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

Heat exchanger (sample cooler -

shell)

PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 C

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 C

Steel (E) Air - indoor uncontrolled Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.AP-189 3.3.1-046 A

Table 3.3.2-26 Auxiliary Systems - Nuclear Sampling - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 68 of 115

Virgil C. Summer Nuclear Station Page 3-421 Supplement 1 Application for Subsequent License Renewal Heat exchanger (sample cooler -

tube)

PB Nickel alloy (E) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-471 3.3.1-147 C, 2 (I) Treated borated water >60°C

(>140°F)

Cracking One-Time Inspection (B2.1.20)

IV.C2.RP-40 3.1.1-082 C, 2 Water Chemistry (B2.1.2)

IV.C2.RP-40 3.1.1-082 C, 2 Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 C, 2 Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 C, 2 (I) Treated water

>60°C (>140°F)

Cracking One-Time Inspection (B2.1.20)

V.C.E-457 3.2.1-114 C, 2 Water Chemistry (B2.1.2)

V.C.E-457 3.2.1-114 C, 2 Loss of material One-Time Inspection (B2.1.20)

V.D1.E-428 3.2.1-022 C, 2 Water Chemistry (B2.1.2)

V.D1.E-428 3.2.1-022 C, 2 Heat exchanger (sample cooler chiller - channel)

LB Steel (E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.AP-189 3.3.1-046 A

(E) Condensation Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.F1.A-417 3.3.1-096b A

Heat exchanger (water bath)

LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 C

(I) Closed-cycle coolingTreated water Loss of material Closed Treated Water Systems (B2.1.12)

Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.C2.A-52 VIII.E.SP-80 3.3.1-049 3.4.1-085 C

E, 1 Table 3.3.2-26 Auxiliary Systems - Nuclear Sampling - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 69 of 115

Virgil C. Summer Nuclear Station Page 3-422 Supplement 1 Application for Subsequent License Renewal Piping, piping components LB;PB;SI Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 A

(E) Condensation Cracking One-Time Inspection (B2.1.20)

VII.I.A-734b 3.3.1-205 A

Loss of material One-Time Inspection (B2.1.20)

VII.I.A-761b 3.3.1-232 A

(I) Gas None None VII.J.AP-22 3.3.1-120 A

(I) Treated borated water Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

(I) Treated borated water >60°C

(>140°F)

Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-82 3.3.1-028 A

Water Chemistry (B2.1.2)

VII.E1.AP-82 3.3.1-028 A

Cumulative fatigue damage TLAA VII.E1.A-57 3.3.1-002 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

(I) Treated water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VIII.E.SP-87 3.4.1-085 E, 1 One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

(I) Treated water

>60°C (>140°F)

Cracking One-Time Inspection (B2.1.20)

VIII.E.SP-88 3.4.1-011 A

Water Chemistry (B2.1.2)

VIII.E.SP-88 3.4.1-011 A

Cumulative fatigue damage TLAA VII.E1.A-57 3.3.1-002 A

Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 3 Table 3.3.2-26 Auxiliary Systems - Nuclear Sampling - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 70 of 115

Virgil C. Summer Nuclear Station Page 3-424 Supplement 1 Application for Subsequent License Renewal Pump casing (sample cooler chiller)

LB Steel (E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

VII.I.A-79 3.3.1-009 A

(I) Closed-cycle coolingTreated water Loss of material Closed Treated Water Systems (B2.1.12)

Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.C2.AP-202 VIII.E.SP-73 3.3.1-045 3.4.1-014 A

E, 1 (E) Condensation Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

Pump casing (sodium hydroxide)

LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Treated water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VIII.E.SP-87 3.4.1-085 E, 1 Pump casing (waste)

LB Polymer (E) Air - indoor uncontrolled Hardening or loss of strength; loss of material; cracking or blistering External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-797a 3.3.1-263 A

(I) Waste water Hardening or loss of strength; loss of material; cracking or blistering Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.C2.A-797b 3.3.1-263 A

Sample flask LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Treated borated water Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

(I) Treated water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VIII.E.SP-87 3.4.1-085 E, 1 Sample sink LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A

Strainer body LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

Table 3.3.2-26 Auxiliary Systems - Nuclear Sampling - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 71 of 115

Virgil C. Summer Nuclear Station Page 3-425 Supplement 1 Application for Subsequent License Renewal Tank (chemical)

LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 C

(I) Treated water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VIII.E.SP-87 3.4.1-085 E, 1 Tank (flush /

dilution)

LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 C

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 C

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 C

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 C

Tank (flush water)

LB Stainless steel (I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

Tank (sample cooler chiller reservoir)

LB Steel (I) Closed-cycle coolingTreated water Loss of material Closed Treated Water Systems (B2.1.12)

Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.C2.AP-202 VIII.E.SP-73 3.3.1-045 3.4.1-014 A

E, 1 (E) Condensation Loss of material External Surfaces Monitoring of Mechanical Components (B2.1.23)

VII.I.A-77 3.3.1-078 A

Table 3.3.2-26 Auxiliary Systems - Nuclear Sampling - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 72 of 115

Virgil C. Summer Nuclear Station Page 3-426 Supplement 1 Application for Subsequent License Renewal Valve body LB;PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 A

(E) Condensation Cracking One-Time Inspection (B2.1.20)

VII.I.A-734b 3.3.1-205 A

Loss of material One-Time Inspection (B2.1.20)

VII.I.A-761b 3.3.1-232 A

(I) Gas None None VII.J.AP-22 3.3.1-120 A

(I) Treated borated water Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

(I) Treated borated water >60°C

(>140°F)

Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-82 3.3.1-028 A

Water Chemistry (B2.1.2)

VII.E1.AP-82 3.3.1-028 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

(I) Treated water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VIII.E.SP-87 3.4.1-085 E, 1 One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

(I) Treated water

>60°C (>140°F)

Cracking One-Time Inspection (B2.1.20)

VIII.E.SP-88 3.4.1-011 A

Water Chemistry (B2.1.2)

VIII.E.SP-88 3.4.1-011 A

Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A,3 Waste sump and panel enclosure LB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A

Table 3.3.2-26 Auxiliary Systems - Nuclear Sampling - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 73 of 115

Virgil C. Summer Nuclear Station Page 3-427 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-26 Plant-Specific Notes:

1.

The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25) program has been substituted for the Water Chemistry (B2.1.2) program and the One-Time Inspection (B2.1.20) program to manage the applicable aging effects for chemical treatment components and for auxiliary sample cooler flowpath components.

2.

Sample coolers provide a safety-related pressure boundary for the component cooling system, but are not credited with a heat transfer function for license renewal.

3.

Delivery of downstream flow is not credited.

Serial No.24-101 Page 74 of 115

Virgil C. Summer Nuclear Station Page 3-428 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-27 Auxiliary Systems - Radiation Monitoring - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Flow element LB;PB;RF Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 A

(I) Treated borated water Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1 Piping, piping components LB;PB;SI Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 A

(I) Treated borated water Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1 Pump casing (air sample)

SI Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

Serial No.24-101 Page 75 of 115

Virgil C. Summer Nuclear Station Page 3-429 Supplement 1 Application for Subsequent License Renewal Table 3.3.2-27 Plant-Specific Notes: None 1.

Delivery of downstream flow is not credited.

Radiation monitor LB;PB Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 A

(I) Treated borated water Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1 Valve body LB;PB;SI Stainless steel (E) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Air - indoor uncontrolled Cracking One-Time Inspection (B2.1.20)

VII.E1.AP-209a 3.3.1-004 A

Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-221a 3.3.1-006 A

(I) Closed-cycle cooling water Loss of material Closed Treated Water Systems (B2.1.12)

VII.C2.A-52 3.3.1-049 A

(I) Treated borated water Loss of material One-Time Inspection (B2.1.20)

VII.E1.AP-79 3.3.1-125 A

Water Chemistry (B2.1.2)

VII.E1.AP-79 3.3.1-125 A

(I) Treated water Loss of material One-Time Inspection (B2.1.20)

VIII.E.SP-87 3.4.1-085 A

Water Chemistry (B2.1.2)

VIII.E.SP-87 3.4.1-085 A

(I) Waste water Loss of material Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25)

VII.E5.AP-278 3.3.1-095 A, 1 Table 3.3.2-27 Auxiliary Systems - Radiation Monitoring - Aging Management Evaluation Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 76 of 115

Virgil C. Summer Nuclear Station Page 3-488 Supplement 1 Application for Subsequent License Renewal 3.4.1-012 Steel tanks exposed to treated water Loss of material due to general, pitting, crevice corrosion, MIC AMP XI.M2, Water Chemistry, and AMP XI.M32, One-Time Inspection No Consistent with NUREG-2191, with a different aging management program credited for some components. In addition to Steam and Power Conversion Systems, components in Auxiliary Systems (industrial cooler) are aligned to this item. For Auxiliary Systems (industrial cooler), a different aging management program is credited. The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25) program manages loss of material of steel components exposed to treated water that is not managed by the Water Chemistry (B2.1.2) program and One-Time Inspection (B2.1.20) program.

3.4.1-014 Steel piping, piping components exposed to steam, treated water Loss of material due to general, pitting, crevice corrosion, MIC (treated water only)

AMP XI.M2, Water Chemistry, and AMP XI.M32, One-Time Inspection No Consistent with NUREG-2191, with a different aging management program credited for some components. In addition to Steam and Power Conversion Systems, components in Auxiliary Systems (component cooling, chilled water, liquid waste processing, fuel handling, chemical and volume control, nuclear sampling, and gaseous waste processing) are aligned to this item. For Auxiliary Systems (chilled water and nuclear sampling), a different aging management program is credited. The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25) manages loss of material of steel components exposed to treated water that is not managed by the Water Chemistry (B2.1.2) program and the One-Time Inspection (B2.1.20) program.

Table 3.4.1 Summary of Aging Management Programs for Steam and Power Conversion System Evaluated in Chapter VIII of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 77 of 115

Virgil C. Summer Nuclear Station Page 3-489 Supplement 1 Application for Subsequent License Renewal 3.4.1-015 Steel heat exchanger components exposed to treated water Loss of material due to general, pitting, crevice corrosion, MIC AMP XI.M2, Water Chemistry, and AMP XI.M32, One-Time Inspection No Consistent with NUREG-2191, with a different aging management program credited for some components. In addition to Steam and Power Conversion Systems, components in Auxiliary Systems (boron recycle, nuclear sampling, and gaseous waste processing) are aligned to this item. For Auxiliary Systems (nuclear sampling), a different aging management program is credited. The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.25) manages loss of material of steel components exposed to treated water that is not managed by the Water Chemistry (B2.1.2) program and the One-Time Inspection (B2.1.20) program.

3.4.1-016 Copper alloy, aluminum piping, piping components exposed to treated water, treated borated water Loss of material due to pitting, crevice corrosion, MIC (copper alloy only)

AMP XI.M2, Water Chemistry, and AMP XI.M32, One-Time Inspection No Consistent with NUREG-2191. In addition to Steam and Power Conversion Systems, components in Auxiliary Systems (demineralized water-nuclear services, fuel handling, nuclear sampling, gaseous waste processing, air handling, and local ventilation and cooling) are aligned to this item.

3.4.1-018 Copper alloy, stainless steel heat exchanger tubes exposed to treated water Reduction of heat transfer due to fouling AMP XI.M2, Water Chemistry, and AMP XI.M32, One-Time Inspection No Consistent with NUREG-2191. In addition to Steam and Power Conversion Systems, components in Auxiliary Systems (reactor makeup water supply) are aligned to this item.

3.4.1-019 Stainless steel, steel heat exchanger components exposed to raw water Loss of material due to general (steel only),

pitting, crevice corrosion, MIC; flow blockage due to fouling AMP XI.M20, Open-Cycle Cooling Water System No Not applicable. There are no in-scope stainless steel or steel heat exchanger components exposed to raw water in the Steam and Power Conversion Systems. The associated NUREG-2191 aging items are not used.

Table 3.4.1 Summary of Aging Management Programs for Steam and Power Conversion System Evaluated in Chapter VIII of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 78 of 115

Page 3-575 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Aging Management Review 3.5.2.1.14 Miscellaneous Structural Commodities Materials The materials of construction for the Miscellaneous Structural Commodities Subcomponents are:

• Cementitious coatings (Pyrocrete, BIO K-10 Mortar, Cafecote, and other similar materials)

• Elastomer

• Elastomer, rubber and other similar materials

• Gypsum

• Silicates (Marinite, Kaowool, Cerafiber, Cera blanket, or other similar materials)

• Stainless steel

• Steel

• Subliming compounds (Thermo-lag, Darmatt, 3M Interam, and other similar materials)

Environment The Miscellaneous Structural Commodities Subcomponents subcomponents are exposed to the following environments:

• Air

• Air - indoor uncontrolled

• Air - outdoor

• Air with borated water leakage

• Groundwater

• Soil Serial No.24-101 Page 79 of 115

Page 3-607 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Aging Management Review

[3.5.1-099] - Plant-specific OE has not identified pitting or crevice corrosion or cracking for stainless steel components exposed to air or condensation environment. The ASME Section XI, Subsection IWF (B2.1.32) program will manage the aging of stainless steel component supports to ensure that these components continue to perform their intended functions during the subsequent period of extended operation. There are no aluminum support components that are within the scope of the ASME Section XI, Subsection IWF (B2.1.32) program.

[3.5.1-100] - Plant-specific OE has not identified pitting or crevice corrosion or cracking for stainless steel components exposed to air or condensation environment. The Structures Monitoring (B2.1.35) program will manage the aging of stainless steel and aluminum alloy component supports to ensure that these components continue to perform their intended functions during the subsequent period of extended operation. In addition to Structures and Component Supports, stainless steel components in Auxiliary Systems (materials handling) are aligned to this row with management by the Structures Monitoring (B2.1.35) program. The Fire Protection (B2.1.15) program will manage the loss of material and cracking of stainless steel associated with fireproofing and fire barriers.

3.5.2.2.2.5 Cumulative Fatigue Damage Due to Fatigue Evaluations involving time-dependent fatigue, cyclical loading, or cyclical displacement of component support members, anchor bolts, and welds for Groups B1.1, B1.2, and B1.3 component supports are TLAAs as defined in 10 CFR 54.3 only if a CLB fatigue analysis exists.

TLAAs are required to be evaluated in accordance with 10 CFR 54.21(c). The evaluation of this TLAA is addressed in Section 4.3, Metal Fatigue Analysis, and/or Section 4.7, Other Plant Specific Time-Limited Aging Analyses, of this SRP-SLR. For plant-specific cumulative usage factor calculations, the method used is appropriately defined and discussed in the applicable TLAAs.

[3.5.1-053] - There are no TLAAs associated with component support members, anchor bolts, and welds for Groups B1.1 and B1.2 component supports. Group B1.3 component supports are associated with BWRs; therefore, not applicable.

Serial No.24-101 Page 80 of 115

Virgil C. Summer Nuclear Station Page 3-637 Supplement 1 Application for Subsequent License Renewal 3.5.1-088 Structural bolting Loss of preload due to self-loosening AMP XI.S6, Structures Monitoring No Consistent with NUREG-2191, however, a different aging management program is credited for bolting associated with Auxiliary Systems (materials handling) and the Reactor Building. Loss of preload of bolting in Auxiliary Systems (materials handling) will be managed by the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems (B2.1.13) program. Loss of preload of Reactor Building stainless steel bolting will be managed by the ASME Section XI, Subsection IWE (B2.1.30) and 10 CFR Part 50, Appendix J (B2.1.33) programs.

3.5.1-089 Support members; welds; bolted connections; support anchorage to building structure Loss of material due to boric acid corrosion AMP XI.M10, Boric Acid Corrosion No Consistent with NUREG-2191.

3.5.1-090 Support members; welds; bolted connections; support anchorage to building structure Loss of material due to general (steel only),

pitting, crevice corrosion AMP XI.M2, Water Chemistry, and AMP XI.S3, ASME Section XI, Subsection IWF No Not applicable. There are no in-scope stainless steel ASME piping and component support members; welds; bolted connections; support anchorage to building structure in a treated water environment in the Containments, Structures, and Component Supports.

The associated NUREG-2191 aging items are not used.

3.5.1-091 Support members; welds; bolted connections; support anchorage to building structure Loss of material due to general, pitting corrosion AMP XI.S3, ASME Section XI, Subsection IWF No Consistent with NUREG-2191 with exceptions.

Exceptions apply to the NUREG-2191 recommendations for ASME Section XI, Subsection IWF (B2.1.32) program implementation.

3.5.1-092 Support members; welds; bolted connections; support anchorage to building structure Loss of material due to general, pitting corrosion AMP XI.S6, Structures Monitoring No Consistent with NUREG-2191., however, a different aging management program is credited for some steel components associated with Miscellaneous Structural Commodities. The Fire Protection (B2.1.15) program manages loss of material for steel associated with fireproofing and fire barriers, and seismic gap covers.

Table 3.5.1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 81 of 115

Virgil C. Summer Nuclear Station Page 3-639 Supplement 1 Application for Subsequent License Renewal 3.5.1-098 Stainless steel, aluminum alloy support members; welds; bolted connections; support anchorage to building structure None None No Not applicable. Boric acid corrosion is not an aging effect requiring management for stainless steel or aluminum alloy. The associated NUREG-2191 aging items are not used.

3.5.1-099 Aluminum, stainless steel support members; welds; bolted connections; support anchorage to building structure Loss of material due to pitting and crevice corrosion; cracking due to SCC AMP XI.M32, One-Time Inspection, AMP XI.S3, ASME Section XI, Subsection IWF, or AMP XI.M36, External Surfaces Monitoring of Mechanical Components Yes (SRP-SLR Section 3.5.2.2.2.4)

Consistent with NUREG-2191 with exceptions. Loss of material and cracking of stainless steel elements is managed by the ASME Section XI, Subsection IWF (B2.1.32) program. Exceptions apply to the NUREG-2191 recommendations for ASME Section XI, Subsection IWF (B2.1.32) program implementation. See further evaluation in Section 3.5.2.2.2.4.

3.5.1-100 Aluminum, stainless steel support members; welds; bolted connections; support anchorage to building structure Loss of material due to pitting and crevice corrosion; cracking due to SCC AMP XI.M32, One-Time Inspection, AMP XI.S6, Structures Monitoring, or AMP XI.M36, External Surfaces Monitoring of Mechanical Components Yes (SRP-SLR Section 3.5.2.2.2.4)

Consistent with NUREG-2191, with a different aging management program credited for some components.

For most components, loss of material and cracking of aluminum, stainless steel elements is managed by the Structures Monitoring (B2.1.35) program. This includes components in Auxiliary Systems (material handling),

which are aligned to this row. However, the Fire Protection (B2.1.15) program manages loss of material and cracking of stainless steel associated with fireproofing and fire barriers. See further evaluation in Section 3.5.2.2.2.4.Consistent with NUREG-2191. Loss of material and cracking of aluminum, stainless steel elements is managed by the Structures Monitoring (B2.1.35) program. In addition, components in Auxiliary Systems (material handling) are aligned to this row. See further evaluation in Section 3.5.2.2.2.4.

Table 3.5.1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report Item Number Component Aging Effect/Mechanism Aging Management Program Further Evaluation Recommended Discussion Serial No.24-101 Page 82 of 115

Virgil C. Summer Nuclear Station Page 3-648 Application for Subsequent License Renewal Virgil C. Summer Nuclear Station Page 3-648 Supplement 1 Application for Subsequent License Renewal Table 3.5.2-1 Plant-Specific Notes:

1.

Concrete elements include beams, columns, walls, slabs, curbs, foundations, pads, jet impingement barriers, missile barriers, tendon access gallery, dome, ring girder and buttresses.

2.

Containment liner includes liner plates, liner leak chase channels, liner anchors, and integral attachments.

3.

Moisture barriers includes elastomeric moisture barrier between Containment liner and internal concrete basement floor.

4.

Seals and gaskets include O-rings and other elastomer materials that are part of the Containment pressure boundary.

Seals and gaskets PB Elastomer, rubber and other similar materials (E) Air - indoor uncontrolled Loss of sealing 10 CFR Part 50, Appendix J (B2.1.33)

II.A3.CP-41 3.5.1-033 A, 4 Service Level I coatings MCI Coatings (E) Air - indoor uncontrolled Loss of coating or lining integrity Protective Coating Monitoring and Maintenance (B2.1.37)

II.A3.CP-152 3.5.1-034 A

III.A4.TP-301 3.5.1-073 A

Steel elements EN;FB;FLB;J IS;MB;SS Steel (E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.A4.TP-302 3.5.1-077 A, 5 (E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

III.B5.T-25 3.5.1-089 C, 5 Sump liners PB;SS Dissimilar metal welds (E) Air - indoor uncontrolled Cumulative fatigue damage (Only if CLB fatigue analysis exists)

TLAA II.A3.C-13 3.5.1-009 A, 10 Stainless steel (E) Air - indoor uncontrolled Cumulative fatigue damage (Only if CLB fatigue analysis exists)

TLAA II.A3.C-13 3.5.1-009 A, 10 (E) Water -

standing Cracking; loss of material ASME Section XI, Subsection IWE (B2.1.30)

III.A7.T-23 3.5.1-052 E, 9 Tendon anchorage components SS Steel (E) Air - outdoor Loss of material ASME Section XI, Subsection IWL (B2.1.31)

II.A1.C-10 3.5.1-032 A

Tendons SS Steel (E) Air - indoor uncontrolled Loss of material ASME Section XI, Subsection IWL (B2.1.31)

II.A1.C-10 3.5.1-032 A

Loss of prestress TLAA II.A1.C-11 3.5.1-008 A

Table 3.5.2-1 Containment Structure - Aging Management Evaluation Structural Member Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 83 of 115

Virgil C. Summer Nuclear Station Page 3-653 Application for Subsequent License Renewal Virgil C. Summer Nuclear Station Page 3-653 Supplement 1 Application for Subsequent License Renewal Table 3.5.2-2 Plant-Specific Notes:

1.

Bellows are associated with the isolation valve chambers and guard pipes (reactor building spray and residual heat removal).

2.

Concrete elements include beams, columns, walls, slabs, foundation, duct banks, missile shields, knockdown walls, and pads.

3.

The isolation valve chambers and guard pipes (reactor building spray and residual heat removal) are extensions of the Containment pressure boundary.

4.

Steel elements include beams, columns, ladders, grating, siding, blow-off panels, stairs, missile shields, baseplates, and embedded steel.

5.

Aluminum bolting is associated with blow-off panels.

6.

The Outdoor and Large Atmospheric Metallic Storage Tanks (B2.1.17) program has been substituted for the Structures Monitoring (B2.1.35) program to manage this aging effect for the caulking used at the tank external surface and concrete foundation interface for the refueling water storage tank and the reactor make-up water storage tank.

Steel elements EN;FB;FLB; MB;SS Steel (E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 4 (E) Air - outdoor Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 4 (E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

III.B5.T-25 3.5.1-089 C, 4 Table 3.5.2-2 Structures and Component Supports - Auxiliary Building - Aging Management Evaluation Structural Member Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 84 of 115

Virgil C. Summer Nuclear Station Page 3-666 Application for Subsequent License Renewal Virgil C. Summer Nuclear Station Page 3-666 Supplement 1 Application for Subsequent License Renewal Table 3.5.2-6 Plant-Specific Notes:

1.

Concrete elements include beams, columns, walls, slabs, foundation, duct banks, knockdown walls, missile shields, and pads.

2.

Steel elements include beams, columns, ladders, grating, stairs, missile shields, baseplates, and embedded steel.

Concrete elements EN;FB;FLB; MB;SS Concrete (E) Soil Increase in porosity and permeability; cracking; loss of material (spalling, scaling)

Structures Monitoring (B2.1.35)

III.A3.TP-29 3.5.1-067 A, 1 Loss of material (spalling, scaling) and cracking Structures Monitoring (B2.1.35)

III.A3.TP-108 3.5.1-042 A, 1 (E) Water - flowing Cracking Structures Monitoring (B2.1.35)

III.A3.TP-204 3.5.1-043 A, 1 Increase in porosity and permeability; loss of strength Structures Monitoring (B2.1.35)

III.A3.TP-67 3.5.1-047 A, 1 III.A3.TP-24 3.5.1-063 A, 1 Reinforced concrete (E) Air Cracking; loss of material Fire Protection (B2.1.15)

VII.G.A-90 3.3.1-060 A, 1 Structures Monitoring (B2.1.35)

VII.G.A-90 3.3.1-060 A, 1 Doors EN;FB Steel (E) Air Loss of material Fire Protection (B2.1.15)

VII.G.A-21 3.3.1-059 A

(E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A

(E) Air - outdoor Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A

Roofing membrane EN Elastomer, rubber and other similar materials (E) Air - indoor uncontrolled Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

(E) Air - outdoor Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

Steel elements EN;FB;FLB; MB;SS Steel (E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 2 (E) Air - outdoor Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 2 Table 3.5.2-6 Structures and Component Supports - Control Building - Aging Management Evaluation Structural Member Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 85 of 115

Virgil C. Summer Nuclear Station Page 3-669 Application for Subsequent License Renewal Virgil C. Summer Nuclear Station Page 3-669 Supplement 1 Application for Subsequent License Renewal Table 3.5.2-7 Plant-Specific Notes:

1.

Aluminum elements include louvers and screens.

2.

Concrete elements include beams, columns, walls, slabs, foundation, caissons, duct banks, knockdown walls, missile shields, and pads.

3.

Steel elements include beams, columns, ladders, grating, stairs, missile shields, baseplates, and embedded steel.

Concrete elements EN;FB;FLB; MB;SS Concrete (E) Soil Increase in porosity and permeability; cracking; loss of material (spalling, scaling)

Structures Monitoring (B2.1.35)

III.A3.TP-29 3.5.1-067 A, 2 Loss of material (spalling, scaling) and cracking Structures Monitoring (B2.1.35)

III.A3.TP-108 3.5.1-042 A, 2 (E) Water - flowing Cracking Structures Monitoring (B2.1.35)

III.A3.TP-204 3.5.1-043 A, 2 Increase in porosity and permeability; loss of strength Structures Monitoring (B2.1.35)

III.A3.TP-67 3.5.1-047 A, 2 III.A3.TP-24 3.5.1-063 A, 2 Reinforced concrete (E) Air Cracking; loss of material Fire Protection (B2.1.15)

VII.G.A-90 3.3.1-060 A, 2 Structures Monitoring (B2.1.35)

VII.G.A-90 3.3.1-060 A, 2 Doors EN;FB Steel (E) Air Loss of material Fire Protection (B2.1.15)

VII.G.A-21 3.3.1-059 A

(E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A

(E) Air - outdoor Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A

Roofing membrane EN Elastomer, rubber and other similar materials (E) Air - indoor uncontrolled Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

(E) Air - outdoor Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

Steel elements EN;FB;FLB; MB;SS Steel (E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 3 (E) Air - outdoor Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 3 Table 3.5.2-7 Structures and Component Supports - Diesel Generator Building - Aging Management Evaluation Structural Member Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 86 of 115

Virgil C. Summer Nuclear Station Page 3-682 Application for Subsequent License Renewal Virgil C. Summer Nuclear Station Page 3-682 Supplement 1 Application for Subsequent License Renewal Table 3.5.2-12 Plant-Specific Notes:

1.

Concrete elements include beams, columns, walls, slabs, foundation, caissons, piers, knockdown walls, missile shields, and pads.

2.

Steel elements include beams, columns, ladders, grating, stairs, siding, missile shields, baseplates, and embedded steel.

3.

Stainless steel elements include fuel transfer canal gate, new fuel storage racks, and spent fuel storage racks.

4.

Boral panels are incorporated into the storage racks as a neutron-absorbing material.

5.

Aluminum elements include wall panel framing.

Steel elements EN;FB;FLB; MB;SS Steel (E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 2 (E) Air - outdoor Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 2 (E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

III.B5.T-25 3.5.1-089 C, 2 Table 3.5.2-12 Structures and Component Supports - Fuel Handling Building - Aging Management Evaluation Structural Member Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 87 of 115

Virgil C. Summer Nuclear Station Page 3-685 Application for Subsequent License Renewal Virgil C. Summer Nuclear Station Page 3-685 Supplement 1 Application for Subsequent License Renewal Table 3.5.2-13 Plant-Specific Notes:

1.

Concrete elements include beams, columns, walls, slabs, foundation, caissons, piers, duct banks, missile shields, and pads.

2.

Steel elements include beams, columns, ladders, grating, siding, blow-off panels, stairs, missile shields, baseplates, and embedded steel.

3.

Aluminum bolting is associated with blow-off panels.

Concrete elements EN;FB;FLB; MB;SS Concrete (E) Soil Increase in porosity and permeability; cracking; loss of material (spalling, scaling)

Structures Monitoring (B2.1.35)

III.A3.TP-29 3.5.1-067 A, 1 Loss of material (spalling, scaling) and cracking Structures Monitoring (B2.1.35)

III.A3.TP-108 3.5.1-042 A, 1 (E) Water - flowing Cracking Structures Monitoring (B2.1.35)

III.A3.TP-204 3.5.1-043 A, 1 Increase in porosity and permeability; loss of strength Structures Monitoring (B2.1.35)

III.A3.TP-67 3.5.1-047 A, 1 III.A3.TP-24 3.5.1-063 A, 1 Reinforced concrete (E) Air Cracking; loss of material Fire Protection (B2.1.15)

VII.G.A-90 3.3.1-060 A, 1 Structures Monitoring (B2.1.35)

VII.G.A-90 3.3.1-060 A, 1 Doors EN;FB;FLB Steel (E) Air Loss of material Fire Protection (B2.1.15)

VII.G.A-21 3.3.1-059 A

(E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A

(E) Air - outdoor Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

III.B5.T-25 3.5.1-089 C

Roofing membrane EN Elastomer, rubber and other similar materials (E) Air - indoor uncontrolled Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

(E) Air - outdoor Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

Steel elements EN;FB;FLB; MB;SS Steel (E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 2 (E) Air - outdoor Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 2 (E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

III.B5.T-25 3.5.1-089 C, 2 Table 3.5.2-13 Structures and Component Supports - Intermediate Building - Aging Management Evaluation Structural Member Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 88 of 115

Virgil C. Summer Nuclear Station Page 3-687 Application for Subsequent License Renewal Virgil C. Summer Nuclear Station Page 3-687 Supplement 1 Application for Subsequent License Renewal Fireproofing and fire barriers EN;FB;FLB Cementitious coatings (Pyrocrete, BIO K-10

Mortar, Cafecote, and other similar materials)

(E) Air Loss of material; cracking/delamination; change in material properties; separation Fire Protection (B2.1.15)

VII.G.A-806 3.3.1-268 A, 1, 2, 3 Elastomer (E) Air Hardening, loss of strength, shrinkage Fire Protection (B2.1.15)

VII.G.A-19 3.3.1-057 A, 1 Gypsum (E) Air - indoor uncontrolled Loss of material; cracking/delamination; change in material properties; separation Fire Protection (B2.1.15)

None None F, 6 Silicates (Marinite, Kaowool',

Cerafiber, Cera blanket, or other similar materials)

(E) Air Loss of material; cracking/delamination; change in material properties; separation Fire Protection (B2.1.15)

VII.G.A-807 3.3.1-269 A, 1, 2

Stainless steel (E) Air Loss of material; cracking Fire Protection (B2.1.15)Structures Monitoring (B2.1.35)

III.B2.T-37b 3.5.1-100 E, 4, 5C, 1 Steel (E) Air - indoor uncontrolled Loss of material Fire Protection (B2.1.15)

III.B2.TP-43 3.5.1-092 E, 4, 5

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

III.B2.T-25 3.5.1-089 C

Table 3.5.2-14 Structures and Component Supports - Miscellaneous Structural Commodities - Aging Management Evaluation Structural Member Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 89 of 115

Virgil C. Summer Nuclear Station Page 3-688 Application for Subsequent License Renewal Virgil C. Summer Nuclear Station Page 3-688 Supplement 1 Application for Subsequent License Renewal Fireproofing and fire barriers EN;FB;FLB Subliming compounds (Thermo-lag

, Darmatt, 3M

Interam, and other similar materials)

(E) Air Loss of material; cracking/delamination; change in material properties; separation Fire Protection (B2.1.15)

VII.G.A-805 3.3.1-267 A, 1, 2

Guard pipes EN Steel (E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.B5.TP-43 3.5.1-092 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

III.B5.T-25 3.5.1-089 A

Penetration seals EN;FB;FLB;P B

Elastomer (E) Air Hardening, loss of strength, shrinkage Fire Protection (B2.1.15)

VII.G.A-19 3.3.1-057 A

Elastomer, rubber and other similar materials (E) Air - indoor uncontrolled Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

(E) Air - outdoor Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

(E) Groundwater Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

(E) Soil Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

Penetration sleeves SS Steel (E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.B3.TP-43 3.5.1-092 A

(E) Air - outdoor Loss of material Structures Monitoring (B2.1.35)

III.B3.TP-43 3.5.1-092 A

(E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

III.B3.T-25 3.5.1-089 C

Seismic gap covers FB Steel (E) Air - indoor uncontrolled Loss of material Fire Protection (B2.1.15)

III.B5.TP-43 3.5.1-092 E, 5 (E) Air with borated water leakage Loss of material Boric Acid Corrosion (B2.1.4)

III.B5.T-25 3.5.1-089 C

Table 3.5.2-14 Structures and Component Supports - Miscellaneous Structural Commodities - Aging Management Evaluation Structural Member Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 90 of 115 f-----+--------+--------+-----+------+-~

I I

Virgil C. Summer Nuclear Station Page 3-689 Application for Subsequent License Renewal Virgil C. Summer Nuclear Station Page 3-689 Supplement 1 Application for Subsequent License Renewal Table 3.5.2-14 Plant-Specific Notes:

1.

Fireproofing and fire barriers include fire stops, fire wraps, fire barrier seals, coatings, and radiant energy shields.

2.

Aging management of change of material properties is applicable to fireproofing and fire barriers exposed to radiation dose greater than 1 x 10^6 rads.

3.

Change of material properties and loss of material due to elevated temperature are not applicable to cementitious coatings since these fireproofing and fire barrier materials are not exposed to an environment where the general area temperature exceeds 150°F (65.6°C) or the local area temperature exceeds 200°F (93.3°C).

4.

Steel and stainless steel materials used to secure fire barrier/fire wrap materials to the component being protected are considered to be part of the fire barrier/fire wrap itself.

5.

The Fire Protection (B2.1.15) program has been substituted for the Structures Monitoring (B2.1.35) program to manage the applicable aging effect(s) for this component type, material, and environment combination.

6.

The material is not addressed in NUREG-2191, but aging is managed by the Fire Protection (B2.1.15) program consistent with silicate fire barrier materials. This includes managing associated gypsum board joint compounds.

Seismic gap filler material EN;FB Elastomer (E) Air Hardening, loss of strength, shrinkage Fire Protection (B2.1.15)

VII.G.A-19 3.3.1-057 C

Elastomer, rubber and other similar materials (E) Air - indoor uncontrolled Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

(E) Air - outdoor Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

Table 3.5.2-14 Structures and Component Supports - Miscellaneous Structural Commodities - Aging Management Evaluation Structural Member Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 91 of 115

Virgil C. Summer Nuclear Station Page 3-705 Application for Subsequent License Renewal Virgil C. Summer Nuclear Station Page 3-705 Supplement 1 Application for Subsequent License Renewal Concrete elements EN;FB;SS Concrete (E) Soil Cracking; loss of bond; and loss of material (spalling, scaling)

Structures Monitoring (B2.1.35)

III.A3.TP-27 3.5.1-065 A, 1 Increase in porosity and permeability; cracking; loss of material (spalling, scaling)

Structures Monitoring (B2.1.35)

III.A3.TP-29 3.5.1-067 A, 1 Loss of material (spalling, scaling) and cracking Structures Monitoring (B2.1.35)

III.A3.TP-108 3.5.1-042 A, 1 (E) Water - flowing Cracking Structures Monitoring (B2.1.35)

III.A3.TP-204 3.5.1-043 A, 1 Increase in porosity and permeability; loss of strength Structures Monitoring (B2.1.35)

III.A3.TP-67 3.5.1-047 A, 1 III.A3.TP-24 3.5.1-063 A, 1 Reduction of foundation strength and cracking Structures Monitoring (B2.1.35)

III.A3.TP-31 3.5.1-046 A, 1 Reinforced concrete (E) Air Cracking; loss of material Fire Protection (B2.1.15)

VII.G.A-90 3.3.1-060 A, 1 Structures Monitoring (B2.1.35)

VII.G.A-90 3.3.1-060 A, 1 Doors EN;FB Steel (E) Air Loss of material Fire Protection (B2.1.15)

VII.G.A-21 3.3.1-059 A

(E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A

(E) Air - outdoor Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A

Masonry block walls EN;FB;SS Concrete block (E) Air - indoor uncontrolled Cracking Masonry Walls (B2.1.34)

III.A3.T-12 3.5.1-070 A

Masonry walls (E) Air Cracking; loss of material Fire Protection (B2.1.15)

VII.G.A-626 3.3.1-179 A

Masonry Walls (B2.1.34)

VII.G.A-626 3.3.1-179 A

Roofing membrane EN Elastomer, rubber and other similar materials (E) Air - indoor uncontrolled Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

(E) Air - outdoor Loss of sealing Structures Monitoring (B2.1.35)

III.A6.TP-7 3.5.1-072 A

Steel elements EN;FB;SS Steel (E) Air - indoor uncontrolled Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 2 (E) Air - outdoor Loss of material Structures Monitoring (B2.1.35)

III.A3.TP-302 3.5.1-077 A, 2 Table 3.5.2-20 Structures and Component Supports - Turbine Building - Aging Management Evaluation Structural Member Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 92 of 115

Virgil C. Summer Nuclear Station Page 3-738 Supplement 1 Application for Subsequent License Renewal Insulation Material for Electrical Cable and Connections Used in Instrumentation Circuits IN Various organic polymers (e.g., EPR, SR, EPDM, XLPE)

(E) Adverse localized environment caused by heat, radiation, or moisture Reduced electrical insulation resistance Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits (B2.1.39)

VI.A.LP-34 3.6.1-009 A

Insulation Material for Electrical Cables and Connections IN Various organic polymers (e.g., EPR, SR, EPDM, XLPE)

(E) Adverse localized environment caused by heat, radiation, or moisture Reduced electrical insulation resistance Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (B2.1.38)

VI.A.LP-33 3.6.1-008 A

Insulation Material for Inaccessible or Below Ground Instrumentation and Control Cable IN Various organic polymers such as EPR, SR, EPDM, XLPE, butyl rubber, and combined thermoplastic jacket/insulati on shield (E) Adverse localized environment caused by significant moisture Reduced electrical insulation resistance or degraded dielectric strength Electrical Insulation for Inaccessible Instrument and Control Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (B2.1.41)

VI.A.LP-35b 3.6.1-010 A

Insulation Material for Inaccessible or Below Ground Low Voltage Power Cable IN Various organic polymers such as EPR, SR, EPDM, XLPE, butyl rubber, and combined thermoplastic jacket/insulati on shield (E) Adverse localized environment caused by significant moisture Reduced electrical insulation resistance or degraded dielectric strength Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (B2.1.42)

VI.A.LP-35c 3.6.1-010 A

Table 3.6.2-2 Electrical and Instrumentation and Controls - Cables And Connections - Aging Management Evaluation Subcomponent Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 93 of 115

Virgil C. Summer Nuclear Station Page 3-739 Supplement 1 Application for Subsequent License Renewal Table 3.6.2-2 Plant-Specific Notes:

1.

Loss of material and increased electrical resistance of connection are not applicable aging effects for switchyard bus and connections. The in-scope switchyard bus and connections are subject to neither wind induced abrasion nor oxidation or loss of pre-load.

2.

Loss of material is not an applicable aging effect for transmission conductors. The in-scope transmission conductors are not subject to wind induced abrasion.

Insulation Material for Inaccessible or Below Ground Medium Voltage Cable IN Various organic polymers such as EPR, SR, EPDM, XLPE, butyl rubber, and combined thermoplastic jacket/insulati on shield (E) Adverse localized environment caused by significant moisture Reduced electrical insulation resistance or degraded dielectric strength Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (B2.1.40)

VI.A.LP-35a 3.6.1-010 A

Switchyard bus and connections CE Aluminum (E) Air - outdoor Loss of material; increased electrical resistance of connection None VI.A.LP-39 3.6.1-006 I, 1 Galvanized steel (E) Air - outdoor Loss of material; increased electrical resistance of connection None VI.A.LP-39 3.6.1-006 I, 1 Stainless steel (E) Air - outdoor Loss of material; increased electrical resistance of connection None VI.A.LP-39 3.6.1-006 I, 1 Transmission conductors CE

Aluminum, Steel (E) Air - outdoor Loss of conductor strength None VI.A.LP-38 3.6.1-004 I, 4 Loss of material None VI.A.LP-47 3.6.1-007 I, 2 Transmission connectors CE Aluminum (E) Air - outdoor Increased electrical resistance of connection None VI.A.LP-48 3.6.1-005 I, 3 Steel (E) Air - outdoor Increased electrical resistance of connection None VI.A.LP-48 3.6.1-005 I, 3 Table 3.6.2-2 Electrical and Instrumentation and Controls - Cables And Connections - Aging Management Evaluation Subcomponent Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-2191 Item Table 1 Item Notes Serial No.24-101 Page 94 of 115

Page 4-73 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Time-Limited Aging Analyses The criteria listed above were used to determine the final sentinel locations, which are summarized in Table 4.3.4-1, Summary of Equipment and Piping Sentinel Locations Requiring EAF Evaluations.

Locations with CUFen values greater than 1.0 or with CUFen values greater than that for the applicable NUREG/CR-6260 location required more-detailed analysis, monitoring, or inspection.

These locations have bounding CUFen values compared with other locations within the same transient section.

As shown in Table 4.3.4-1, the CUFen values for the RV shell-to-inlet nozzles, RV main shell, safety injection cold leg nozzles and residual heat removal hot leg nozzles are less than 1.0. Therefore, fatigue management is not required for these transient sections and associated components.

Except for the steam generator tubing, which is managed by the Steam Generators program (B2.1.10), the remaining sentinel locations in Table 4.3.4-1 have been analyzed using a flaw-tolerance evaluation, and EAF for these components will be managed by application of the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD program (B2.1.1) for the subsequent period of extended operation.

Fatigue Management NUREG-2191 (X.M1) and NUREG-2192 permit inservice inspections as a management method for EAF, so long as a flaw-tolerance evaluation, conducted in accordance with the guidance of ASME Code,Section XI, Nonmandatory Appendix A or Appendix L, is performed, in conjunction with calculated allowable-flaw sizes, to determine the acceptable time between inspections at the bounding location. The ASME Code,Section XI, Appendix A and Appendix L flaw-tolerance evaluations consist of postulating hypothetical inside-surface axial and circumferential flaws. For a postulated initial flaw, crack growth is simulated, based upon exposure to specified numbers of transient cycles, until the flaw has reached the allowable-flaw depth or the end of the subsequent period of extended operation, whichever comes first.

For the sentinel-component locations where the CUFen values were not reduced to less than 1.0 using ASME Code,Section III, Subsection NB-3200 calculations, a flaw-tolerance evaluation was generated.

The ASME Code,Section XI, Appendix A flaw-tolerance evaluation of the RV shell-to-outlet nozzle welds shows a final flaw size of 0.3576 inches, compared to the allowable end-of-evaluation flaw size of 0.670.696 inches, which equates to an allowable operating period of 80 years. The effects of environmental fatigue for the RV shell-to-outlet nozzle weld will be managed by application of the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD program (B2.1.1) for the subsequent period of extended operation, based upon the results of the flaw-tolerance evaluation.

Serial No.24-101 Page 95 of 115

Page 4-83 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Time-Limited Aging Analyses

. Table 4.3.4-3 Appendix L Inspections Location Weld No.

Last ISI Inspection Normal Charging Line CGE-1-4205A-12 CGE-1-4200-22BC 10/27/2015 Alternate Charging Line CGE-1-4106A-10 CGE-1-4100-26BC 10/22/2015 10/26/2015 Pressurizer Surge Line CGE-1-4500A-13 CGE-1-4100-19BC 03/31/1993 06/21/1993 Serial No.24-101 Page 96 of 115

Page A-6 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix A - FSAR Supplement For the 80-year operating period, aging management is based on the EPRI documents listed for the 60-year period, and a gap analysis that integrates the interim utilizes supplemental guidance from MRP 2018-022, Transmittal of MRP-191 Screening, Ranking, and Categorization Results and Interim Guidance in Support of Subsequent License Renewal at U.S. PWR Plants, for additional inspections not listed for RVI components in MRP-227, Revision 1-A. The components from MRP 2018-022 include clevis insert bolts and dowels, radial support key Stellite wear surface, and clevis insert Stellite wear surface. The gap analysis further integrates guidance for inspections of the control rod guide tube continuous section sheaths and C-tubes in accordance with WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections.

A1.8 Flow-Accelerated Corrosion The Flow-Accelerated Corrosion program is an existing condition monitoring program that manages wall thinning caused by flow-accelerated corrosion, as well as wall thinning due to erosion mechanisms. Erosion monitoring is performed for the internal surfaces of metallic piping and components to manage the aging effect of wall thinning due to cavitation, flashing, liquid droplet impingement, and solid particle erosion.

The program is consistent with NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning, and relies on implementation of EPRI guidelines listed in NSAC-202L, Revision 4, Recommendations for an Effective Flow Accelerated Corrosion Program. The erosion activity implements the recommendations of EPRI 3002005530, Recommendations for an Effective Program Against Erosive Attack.

The program includes (a) identifying flow accelerated corrosion (FAC)-susceptible piping systems and components; (b) developing FAC predictive models to reflect component geometries, materials, and operating parameters; (c) performing analyses of FAC models and, with consideration of operating experience, selecting a sample of components for inspection; (d) inspecting components; (e) evaluating inspection data to determine the need for inspection sample expansion, repairs, or replacements, and to schedule future inspections; and (f) incorporating inspection data to refine FAC modeling.

The program tracks and predicts occurrences of wall thinning due to FAC using CHECWORKS-SFA' software. The CHECWORKS-SFA' model is evaluated and updated as required to reflect any significant changes in plant-specific operating parameters such as power uprates. Wall thinning information available from the CHECWORKS-SFA' software is one of the tools used to determine the scope and required schedule for inspections of FAC-susceptible components.

Serial No.24-101 Page 97 of 115

Page A-35 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix A - FSAR Supplement WCAP 18728-NP, V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: Evaluation of Reactor Vessel Time-Limited Aging Analyses, the materials that exceeded the 1.0 x 1017 n/cm2 (E > 1.0 MeV) threshold at 72 EFPY are evaluated to determine their impact on USE during the subsequent period of extended operation. The projected USE values for the beltline and extended beltline materials were calculated and determined to remain above the USE screening criterion of 50-ft-lb at the end of the subsequent period of extended operation, with the limiting USE value being at 63 ft-lb.

The USE TLAA has been projected to the end of the subsequent period of extended operation and is dispositioned in accordance with 10 CFR 54.21(c)(1)(ii).

A3.2.3 Pressurized Thermal Shock 10 CFR 50.61(b)(1) provides rules for protection against pressurized thermal shock (PTS) events for pressurized water reactors and requires the reference temperature RTPTS for RV beltline materials to be less than the PTS screening criteria at the expiration date of the operating license unless otherwise approved by the NRC. 10 CFR 50.61(c) provides two methods for determining RTPTS, described in Regulatory Guide 1.99, Revision 2. Per WCAP-18728-NP, values were calculated performing both methods. The limiting RTPTS value is 152.5ºF for base metal and longitudinal welds and 42.5°F for circumferentially oriented welds. The beltline and extended beltline materials in the RV are below the RTPTS screening criteria values of 270°F for base metal and/or longitudinal welds, and 300°F for circumferentially oriented welds for the subsequent period of extended operation.

The PTS analyses have been projected to the end of the subsequent period of extended operation and are dispositioned in accordance with 10 CFR 54.21(c)(1)(ii).

A3.2.4 Adjusted Reference Temperature The adjusted reference temperature (ART) of the limiting beltline material is used to adjust the beltline Pressure-Temperature (P-T) limit curves to account for irradiation effects. 10 CFR 50, Appendix G, defines the fracture toughness requirements for the life of the vessel. Regulatory Guide 1.99 provides the methodology for determining the ART of the limiting material. RTNDT was evaluated in accordance with PWROG-21037-NP, Determination of Unirradiated RTNDT and Upper-Shelf Energy Values of the V.C. Summer Unit 1 Reactor Vessel Materials, which includes the generally accepted techniques outlined in ASME Code,Section III, Paragraph NB 2331, Material for Vessel, and Branch Technical Position 5-3, Fracture Toughness Requirements. The P-T limit curves for normal heatup and cooldown of the primary reactor coolant system were previously developed in WCAP-16305-NP, Revision 0, V.C: Summer Heatup and Cooldown Curves for Normal Operation, and validated in WCAP-18729-NP, V.C. Summer Nuclear Station Unit 1 Subsequent License Renewal: Heatup and Cooldown Limit Curves for Normal Operation.

The ART analyses have been projected to the end of the subsequent period of extended operation and are dispositioned in accordance with 10 CFR 54.21(c)(1)(ii).

Serial No.24-101 Page 98 of 115

Virgil C. Summer Nuclear Station Page A-49 Application for Subsequent License Renewal Appendix A - UFSAR Supplement Virgil C. Summer Nuclear Station Page A-49 Supplement 1 Application for Subsequent License Renewal Appendix A - UFSAR Supplement A4 Subsequent License Renewal Commitments Table A4.0-1 Subsequent License Renewal Commitments Program Commitment AMP Implementation 1

ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD program The ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD program is an existing condition monitoring program that will be enhanced as follows:

1. Procedures will be revised to require volumetric inspection of the pressurizer surge line hot leg nozzle every 48 years for management of EAF. Based on satisfactory results from the last inspection performed in Q1Q2 1993, the next inspection will be performed by Q1Q2 2041. (Revised -

Supplement 1)

B2.1.1 Program enhancement for SLR will be implemented by Q1Q2 2041.

2 Water Chemistry program The Water Chemistry program is an existing preventive program that is credited.

B2.1.2 Ongoing 3

Reactor Head Closure Stud Bolting program The Reactor Head Closure Stud Bolting program is an existing condition monitoring program that will be enhanced as follows:

1. Procurement documents for reactor head closure studs will be revised to incorporate guidance from RG 1.65, Revision 1 and NUREG-2191,Section XI.M3, to add a limit for the maximum measured yield strength of 150 ksi and a limit for maximum tensile strength of 170 ksi.

B2.1.3 Program enhancements for SLR will be implemented 6 months prior to the subsequent period of extended operation.

4 Boric Acid Corrosion program The Boric Acid Corrosion program is an existing condition monitoring program that is credited.

B2.1.4 Ongoing 5

Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor Coolant Pressure Boundary Components program The Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor Coolant Pressure Boundary Components program is an existing condition monitoring program that is credited.

B2.1.5 Ongoing Serial No.24-101 Page 99 of 115

Virgil C. Summer Nuclear Station Page A-50 Application for Subsequent License Renewal Appendix A - UFSAR Supplement Virgil C. Summer Nuclear Station Page A-50 Supplement 1 Application for Subsequent License Renewal Appendix A - UFSAR Supplement 6

Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) program The Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) program is an existing condition monitoring program that is credited.

B2.1.6 Ongoing 7

PWR Vessel Internals program The PWR Vessel Internals program is an existing condition monitoring program that will be enhanced as follows:

1. Procedure(s) will be revised to include a list of the components that require inspections for the Primary, Expansion, and Existing Programs categories specified in MRP-227, Revision 1-A, including the components identified in the VCSNS gap analysis. Alternatively, the latest NRC-approved version of MRP-227 that provides aging management to 80 years will be implemented. (Revised - Supplement 1)

2. Procedure will be revised to require additional spring height measurements prior to the SPEO to establish the core barrel hold down spring height and determine if replacement of the core barrel hold down spring is required.

B2.1.7 Program enhancements for SLR will be implemented 6 months prior to the subsequent period of extended operation.

8 Flow-Accelerated Corrosion program The Flow-Accelerated Corrosion program is an existing condition monitoring program that is credited.

B2.1.8 Ongoing Table A4.0-1 Subsequent License Renewal Commitments Program Commitment AMP Implementation Serial No.24-101 Page 100 of 115

Virgil C. Summer Nuclear Station Page A-62 Application for Subsequent License Renewal Appendix A - UFSAR Supplement Virgil C. Summer Nuclear Station Page A-62 Supplement 1 Application for Subsequent License Renewal Appendix A - UFSAR Supplement 24 Flux Thimble Tube Inspection program The Flux Thimble Tube Inspection program is an existing condition monitoring program that is creditedwill be enhanced as follows:

1. Procedure(s) will be revised to require that, for situations where no wear is measured in a flux thimble tube wall during wall thickness measurements, the minimum detectable wear value will be recorded and used to establish the future inspection frequency. The future inspection frequency will be a maximum of 15 calendar years between inspections. (Added - Supplement 1)

B2.1.24 OngoingProgram enhancements for SLR will be implemented 6 months prior to the subsequent period of extended operation.

25 Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program is an existing condition monitoring program that will be enhanced as follows:

1. Procedure(s) will be revised to specify inspections and tests be performed by personnel qualified in accordance with site procedures and programs to perform the specified task.

2. Procedure(s) will be revised to provide non-ASME Code inspection guidance related to lighting, distance, offset, surface coverage, presence of protective coatings, and cleaning processes. Adequate lighting will be verified at the inspection location to detect degradation. Lighting may be permanently installed, temporary, or portable (e.g., flashlight), as appropriate. For accessible surface inspections, inspecting from a distance of two feet or less will be appropriate. For viewing angles which may prevent adequate inspection, a viewing aid such as an inspection mirror or boroscope should be used.

For internal inspections, accessible surfaces will be inspected. If inspecting piping internal surfaces, a minimum of one linear foot will be inspected, if accessible. Cleaning will be performed as necessary to allow for a meaningful examination. If protective coatings are present, the condition of the coating will be documented.

3. Procedure(s) will be revised to specify the following:

a. In each 10-year period during the subsequent period of extended operation, the minimum number of inspections is completed for the various sample populations (each material, environment, and aging effect combination). If opportunistic inspections will not fulfill the minimum number of inspections by the end of each 10-year period, the program owner will initiate work orders as necessary to request additional inspections. A representative sample of 20% of the population (defined as components having the same material, environment, and aging effect combination) or a maximum of 25 components per population will be inspected. The new procedure will specify that the inspections focus on the bounding or lead components most susceptible to aging due to time in service and severity of operating conditions.

b. The rate of degradation will be evaluated and projected until the end of the subsequent period of extended operation or the next scheduled inspection, whichever is shorter. The inspection sampling bases (e.g.: selection, size, frequency) will be adjusted as necessary based on the projection.

B2.1.25 Program enhancements for SLR will be implemented 6 months prior to the subsequent period of extended operation.

Table A4.0-1 Subsequent License Renewal Commitments Program Commitment AMP Implementation Serial No.24-101 Page 101 of 115

Virgil C. Summer Nuclear Station Page A-73 Application for Subsequent License Renewal Appendix A - UFSAR Supplement Virgil C. Summer Nuclear Station Page A-73 Supplement 1 Application for Subsequent License Renewal Appendix A - UFSAR Supplement 40 Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements program The Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements program is an existing condition monitoring program that will be enhanced as follows:

1. Procedure(s) will be revised to inspect and dewater, if required, the in-scope manholes after event driven occurrences, such as heavy rain, rapid thawing of ice and snow, or flooding.

2. Procedure(s) will be revised to clarify that the frequency of manhole inspections will occur at least once a year.

3. Procedure(s) will be revised to specify that condition monitoring cable test and inspections results that utilize visual inspection and test methods that are trendable and repeatable, will be trended to provide additional information on the rate of cable or connection insulation degradation. (Added -

Supplement 1)

B2.1.40 Program enhancements for SLR will be implemented 6 months prior to the subsequent period of extended operation.

41 Electrical Insulation for Inaccessible Instrument and Control Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements program The Electrical Insulation for Inaccessible Instrument and Control Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements program is a new condition monitoring program that will manage the effects of reduced electrical insulation resistance or degraded dielectric strength of non-EQ, in scope, inaccessible (e.g., installed in buried conduits, cable trenches, cable troughs, duct banks, underground vaults, or direct buried installations), instrument and control cables, exposed to significant moisture.

Industry and plant-specific operating experience will be evaluated in the development and implementation of this program.

B2.1.41 Program will be implemented 6 months prior to the subsequent period of extended operation.

42 Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements program The Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements program is a new condition monitoring program that will manage the effects of reduced insulation resistance of non-EQ, in scope, inaccessible (e.g., installed in buried conduits, cable trenches, cable troughs, duct banks, underground vaults, or direct buried installations),

low-voltage power cables (operating voltage less than 2 kV), potentially exposed to significant moisture.

Industry and plant-specific operating experience will be evaluated in the development of this program.

B2.1.42 Program will be implemented 6 months prior to the subsequent period of extended operation.

Table A4.0-1 Subsequent License Renewal Commitments Program Commitment AMP Implementation Serial No.24-101 Page 102 of 115

Page B-11 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs B2 Aging Management Programs Table B2-1 lists the aging management programs described in this appendix and identifies the programs consistency with the corresponding NUREG-2191 program. As discussed in Section B1.4, both plant-specific and industry operating experience has been reviewed and considered as it relates to both new and existing aging management programs.

Table B2-1 VCSNS Program Consistency with NUREG-2191 Program NUREG-2191 Program Appendix B

Reference Existing or New VCSNS Program Program has NUREG-2191 Enhancements Program has Exceptions to NUREG-2191 ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD B2.1.1 Existing X

Water Chemistry (Primary and Secondary)

B2.1.2 Existing Reactor Head Closure Stud Bolting (addressed by ISI program)

B2.1.3 Existing X

X Boric Acid Corrosion B2.1.4 Existing Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-induced Corrosion in Reactor Coolant Pressure Boundary Components B2.1.5 Existing Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)

B2.1.6 Existing PWR Vessel Internals B2.1.7 Existing X

Flow-Accelerated Corrosion B2.1.8 Existing Bolting Integrity B2.1.9 Existing X

Steam Generators B2.1.10 Existing X

Open-Cycle Cooling Water System B2.1.11 Existing X

Closed Treated Water Systems B2.1.12 Existing X

Serial No.24-101 Page 103 of 115

Page B-12 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems B2.1.13 Existing X

Compressed Air Monitoring B2.1.14 Existing X

Fire Protection B2.1.15 Existing X

Fire Water System B2.1.16 Existing X

Outdoor and Large Atmospheric Metallic Storage Tanks B2.1.17 New Fuel Oil Chemistry B2.1.18 Existing X

Reactor Vessel Material Surveillance B2.1.19 Existing One-Time Inspection B2.1.20 New Selective Leaching B2.1.21 New ASME Code Class 1 Small-Bore Piping B2.1.22 Existing X

External Surfaces Monitoring of Mechanical Components B2.1.23 Existing X

Flux Thimble Tube Inspection B2.1.24 Existing X

Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components B2.1.25 Existing X

Lubricating Oil Analysis B2.1.26 Existing X

Monitoring of Neutron-Absorbing Materials Other Than Boraflex B2.1.27 Existing Buried and Underground Piping and Tanks B2.1.28 Existing X

Table B2-1 VCSNS Program Consistency with NUREG-2191 Program NUREG-2191 Program Appendix B

Reference Existing or New VCSNS Program Program has NUREG-2191 Enhancements Program has Exceptions to NUREG-2191 Serial No.24-101 Page 104 of 115

Page B-18 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs Exception Summary None Enhancements Prior to the subsequent period of extended operation, the following enhancement will be implemented in the following program element(s):

Scope of Program (Element 1) 1.

Procedures will be revised to require volumetric inspection of the pressurizer surge line hot leg nozzle every 48 years for management of EAF. Based on satisfactory results from the last inspection performed in Q21 1993, the next inspection will be performed by Q21 2041.

(Revised - Supplement 1)

Operating Experience Summary The following examples of operating experience provide objective evidence that the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD program has been, and will be effective in managing the aging effects for SSCs within the scope of the program so that the intended functions will be maintained consistent with the current licensing basis during the subsequent period of extended operation.

1.

In October 2012, UT indications were identified on four control rod drive mechanism (CRDM) penetrations during performance of volumetric examinations of the reactor vessel (RV) closure head. These examinations were performed in accordance with ASME Boiler & Pressure Vessel (BPV) Code Case N-729-1. One vent line penetration and 65 CRDM penetrations were included in the penetration inspections performed during the refueling outage. Repairs were performed on four CRDM penetration nozzles and associated J-groove welds using the Westinghouse Embedded Flaw Repair process in accordance with NRC-approved WCAP-15987 (ADAMS Accession No. ML031840237). PWSCC was identified as the apparent cause of the flaws. Corrective actions included repairing the penetrations and revising the frequency of the bare metal visual exam and the volumetric exam to every refueling outage.

2.

In April 2014, during the Spring refueling outage, volumetric inspections of the 66 RV closure head penetrations (65 CRDM and one RV closure head vent system line) identified five reactor CRDM penetrations that did not meet the requirements of 10 CFR 50.55a(g)(b)(ii)(D) and American Society of Mechanical Engineers (ASME)Section XI Code Case N-729-1. The indications were not through-wall as confirmed by volumetric and bare metal visuals. The flaws were repaired using the embedded flaw repair process in accordance with NRC-approved WCAP-15987. The apparent cause of the flaws was attributed to primary water stress corrosion cracking. The replacement RV closure head that was installed during the Spring Serial No.24-101 Page 105 of 115

Page B-41 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs Excluding the neutron panel bolts and the irradiation specimen guides and bolts, the neutron exposure of the reactor vessel components for 80 years of operation is bounded by the evaluations in MRP-191, Revision 2. The neutron fluence of the neutron panel bolts and the irradiation specimen guide bolts for the 80 years of operation was determined to be greater that the projections in MRP-191, Revision 2. As a result, a vendor expert panel evaluation determined that the inspection category of 'no additional measures' applies for the neutron panels and irradiation specimen guides.

The gap analysis integrates the applicable interim utilizes supplemental guidance from MRP 2018-022, Transmittal of MRP-191 Screening, Ranking, and Categorization Results and Interim Guidance in Support of Subsequent License Renewal at U.S. PWR Plants (ADAMS Accession No. ML19081A061) for additional as a reference for inspections of reactor vessel components not listed in MRP-227, Revision 1-A. and Guidance for inspections of the control rod guide tube (CRGT) C-tubes and sheaths is provided in WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections (ADAMS Accession No. ML19262E593). Examinations of the CRGT C-tubes and sheaths are assigned to the "expansion" inspection category.

Following are details of items included in the PWR Vessel Internals program based on the gap analysis results:

1.

The components below have been incorporated into the PWR Vessel Internals program with examinations assigned to the 'primary' inspection category in accordance with MRP-2018-022:

a.

Clevis insert bolts (Alignment and Interfacing Components) b.

Clevis insert dowels (Alignment and Interfacing Components) c.

Radial support keys Stellite wear surface (Radial Support Keys) d.

Clevis bearings Stellite wear surface (Alignment and Interfacing Components) 2.

Guidance was incorporated into the PWR Vessel Internals program with examinations assigned to the 'expansion' inspection category for the control rod guide tube (CRGT) continuous section sheaths and C-tubes (CRGT Assembly) in accordance with WCAP-17451-P, Revision 2.

The selection of RVI components to be inspected is based on a four-step ranking process that includes the designations of 'primary', 'expansion', 'existing programs' (such as American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Examination Category B-N-3, examinations of core support structures), or 'no additional measures'. The program includes expanding examinations (i.e., 'expansion' components) if the observed extent of degradation for the 'primary' components exceeds acceptance criteria. The identified examinations Serial No.24-101 Page 106 of 115

Page B-42 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs for RVI components provide reasonable assurance that the effects of age-related degradation mechanisms will be managed during the period of extended operation.

The PWR Vessel Internals program is implemented as a fleet program at Dominion. The program requirements and implementation procedures used across the fleet have been previously reviewed and evaluated by the NRC Staff and determinations were made for Surry Power Station (ADAMS Accession No. ML19360A020) and North Anna Power Station (ADAMS Accession No. ML21354A196) that the effects of aging will be adequately managed so that the intended function(s) will be maintained consistent with the CLB for the subsequent period of extended operation, as required by 10 CFR 54.21(a)(3).

NUREG-2191 Consistency The PWR Vessel Internals program is an existing program that, following enhancement, will be consistent with NUREG-2191,Section XI.M16A, PWR Vessel Internals, as modified by SLR-ISG-2021-01-PWRVI, "Updated Aging Management Criteria for Reactor Vessel Internal Components for Pressurized Water Reactors."

Exception Summary None Enhancements Prior to the subsequent period of extended operation, the following enhancements will be implemented in the following program element(s):

Scope of Program (Element 1), Detection of Aging Effects (Element 4); Monitoring and Trending (Element 5); and Acceptance Criteria (Element 6) 1.

Procedure(s) will be revised to include a list of the components that require inspections for the Primary, Expansion, and Existing Programs categories specified in MRP-227, Revision 1-A, including the components identified in the VCSNS gap analysis. Alternatively, the latest NRC-approved version of MRP-227 that provides aging management to 80 years will be implemented. (Revised - Supplement 1)

Parameters Monitored / Inspected (Element 3) and Acceptance Criteria (Element 6) 2.

Procedure will be revised to require additional spring height measurements prior to the SPEO to establish the core barrel hold down spring height and determine if replacement of the core barrel hold down spring is required.

Operating Experience Summary The following examples of operating experience provide objective evidence that the PWR Vessel Internals program has been, and will be effective in managing the aging effects for SSCs within the scope of the program so that the intended functions will be maintained consistent with the current licensing basis during the subsequent period of extended operation.

Serial No.24-101 Page 107 of 115

Page B-59 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs B2.1.10 Steam Generators Program Description The Steam Generators program is an existing condition monitoring program that manages cracking, loss of material (e.g., wall thinning), and reduction of heat transfer for the steam generators (SGs). The scope of the program includes primary-side components (e.g., U-tubes, tube plugs, channel head divider plate, channel head, tubesheet, etc.), and secondary-side components that are contained within the SG. The Steam Generators program does not include primary-side sleeves since these components are not used in the SGs. The program uses volumetric inspections for the tubes, and visual inspections for the other primary-side and secondary-side components.

The visual inspections of primary-side components listed above are performed in accordance with the Degradation Assessment (DA) that is prepared as each SG is scheduled for examination.

The Steam Generators program utilizes industry endorsed guidance regarding tube inspections, evaluation and repair, and leakage monitoring techniques to ensure tube integrity of the SGs. Aging is managed through assessment of potential degradation mechanisms, inspections, tube integrity assessments, plugging and repairs, primary-to-secondary leakage monitoring, maintenance of secondary side component integrity, primary-side and secondary-side water chemistry, and foreign material exclusion. Implementing procedures specify the performance criteria for tube integrity, condition monitoring requirements, inspection scope and frequency, acceptance criteria for the plugging or repair of flawed tubes, acceptable tube repair methods, leakage monitoring requirements, and operational leakage and accident-induced leakage requirements from the Technical Specifications (TS).

Provisions in the Steam Generators program address reporting criteria, inspection scope and frequency, assessments, plugging criteria, and water chemistry monitoring to maintain consistency with established requirements. Those requirements appear in the following documents:

Technical Specifications (and Technical Requirements Manual)

Maintenance Rule (10 CFR 50.65)

EPRI 3002020909, Steam Generator Integrity Assessment Guidelines EPRI 3002007572, PWR Steam Generator Examination Guidelines EPRI 3002018267Technical Report TR1022832, PWR Primary-to-Secondary Leak Guidelines EPRI 3002007856, Steam Generator In-Situ Pressure Test Guidelines The EPRI guidelines provide a generic industry program to implement the expectations from NEI 97-06, Revision 3, Steam Generator Program Guidelines.

The original SGs were replaced in 1994 during RF8. The replacement SGs incorporated Alloy 690 thermally-treated tubes to improve reliability and minimize aging.

Serial No.24-101 Page 108 of 115

Page B-62 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs Condition monitoring and performance monitoring assessments are performed to determine whether structural and accident leakage criteria have been satisfied during the previous operating cycle(s). Operational assessments are performed after inspections are completed to verify that structural and leakage integrity will be maintained for the operating interval between inspections, which is selected in accordance with the TS and EPRI Steam Generator Integrity Assessment Guidelines. Comparison of the results of the condition monitoring assessment with the predictions of the previous operational assessment provides feedback for evaluation of the adequacy of the operational assessment and additional insights that can be incorporated into the next operational assessment. The condition monitoring and performance monitoring methods are effective in detecting the applicable aging effects, and the frequency of monitoring is adequate to prevent significant age-related degradation.

The Steam Generators program is implemented as a Fleet program at Dominion. The program requirements and implementation procedures used across the fleet have been previously reviewed and evaluated by the NRC Staff and determinations were made for Surry Power Station (ADAMS Accession No. ML19360A020) and North Anna Power Station (ADAMS Accession No. ML21354A196) that the effects of aging will be adequately managed so that the intended function(s) will be maintained consistent with the CLB for the subsequent period of extended operation, as required by 10 CFR 54.21(a)(3).

NUREG-2191 Consistency The Steam Generators program is an existing program that is consistent, with exception, to NUREG-2191,Section XI.M19, Steam Generators.

Exception Summary The following program elements are affected:

Preventive Action (Element 2), Parameters Monitored/Inspected (Element 3), Monitoring and Trending (Element 5), and Acceptance Criteria (Element 6) 1.

NUREG-2191 indicates that the Steam Generators program relies on industry steam generator integrity assessment guidelines contained in EPRI 3002007571, Steam Generator Integrity Assessment Guidelines. The current revision of the Steam Generator Integrity Assessment Guidelines is identified as EPRI 3002020909.

An exception is being taken to use EPRI 3002020909 for steam generator integrity assessment guidelines.

Justification for Exception Element 2 - indicates that the EPRI Steam Generator Integrity Assessment Guidelines (EPRI 3002007571) include guidance for maintaining secondary side integrity. Guidance includes maintenance of secondary side water chemistry, foreign material exclusion as a means to inhibit Serial No.24-101 Page 109 of 115

Page B-63 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs wear degradation, and secondary side cleaning activities such as sludge lancing for removing deposits that may contribute to degradation. This guidance from EPRI 3002007571 is carried forward to EPRI 3002020909.

Element 3 - indicates that the EPRI Steam Generator Integrity Assessment Guidelines (EPRI 3002007571) provide guidance for secondary side activities. This guidance has been carried forward from EPRI 3002007571 to EPRI 3002020909.

Element 5 - indicates that Condition Monitoring and Operational Assessment reports are prepared in accordance with Technical Specification requirements, NEI 97-06, and the EPRI Steam Generator Integrity Assessment Guidelines (EPRI 3002007571). This guidance has been carried forward to EPRI 3002020909.

Element 6 - indicates that guidance on assessing the acceptability of flaws is provided in NEI 97-06 and associated EPRI documents, including the EPRI Steam Generator Integrity Assessment Guidelines (EPRI 3002007571). Flaw evaluations are performed to ensure that the components will continue to perform their functions consistent with the design and licensing basis, and will not affect the integrity of other components (e.g., by generating loose parts). This guidance for evaluating flaws has been carried forward to EPRI 3002020909.

As documented above, the consistency between EPRI 3002007571 and EPRI 3002020909 regarding guidance cited by NUREG-2191 for subsequent license renewal justifies using the current version of the EPRI report.

Parameters Monitored/Inspected (Element 3) 2.

NUREG-2191 indicates that the Steam Generators program relies on industry primary-to-secondary leak guidelines contained in EPRI 1022832, PWR Primary-to-Secondary Leak Guidelines. The current revision of PWR Primary-to-Secondary Leak Guidelines is identified as EPRI 3002018267.

An exception is being taken to use EPRI 3002018267 for steam generator primary-to-secondary leak guidelines.

Justification for Exception Element 3 - indicates that monitoring provided by Primary-to-Secondary Leak Guidelines (EPRI 1022832) may indicate excessive tube, plug, or sleeve degradation and the presence of loose parts or foreign objects. This guidance is carried forward to EPRI 3002018267.

As documented above, the consistency between EPRI 1022832 and EPRI 3002018267 regarding guidance cited by NUREG-2191 for subsequent license renewal justifies using the current version of the EPRI report.

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Page B-64 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs Acceptance Criteria (Element 6) 3.

NUREG-2191 indicates that the Steam Generators program relies on industry in-situ pressure test guidelines contained in EPRI 1025132, Steam Generator In-Situ Pressure Test Guidelines. The current revision of Steam Generator In-Situ Pressure Test Guidelines is identified as EPRI 3002007856.

An exception is being taken to use EPRI 3002007856 for steam generator in-situ pressure test guidelines.

Justification for Exception Element 6 - refers to EPRI Steam Generator In-Situ Pressure Test Guidelines (EPRI 1025132) for flaw evaluation. Assessment of tube and sleeve integrity, as well as plugging or repair criteria for flawed and sleeved tubes, is in accordance with plant technical specifications. Guidance on assessing the acceptability of flaws is also provided in NEI 97-06 and in EPRI Steam Generator In-Situ Pressure Test Guidelines (EPRI 1025132). This guidance for assessing the acceptability of flaws as identified in NUREG-2191 has been carried forward to EPRI 3002007856.

As documented above, the consistency between EPRI 1025132 and EPRI 3002007856 regarding guidance cited by NUREG-2191 for subsequent license renewal justifies using the current version of the EPRI report.None Enhancements None Operating Experience Summary The following examples of operating experience provide objective evidence that the Steam Generators program has been, and will be effective in managing the aging effects for SSCs within the scope of the program so that the intended functions will be maintained consistent with the current licensing basis during the subsequent period of extended operation.

1.

In January 2012, NSAL-12-1, Steam Generator Channel Head Degradation, was issued to describe degradation of the SG channel head cladding in a Westinghouse-designed steam generator. Recommended action from NSAL-12-1 was to perform a visual inspection to identify potential breaches in the cladding. Since steam generator bowl scans of each channel head are performed during primary-side inspections, it was determined that no action was necessary.

2.

In October 2012, prior to RF20, the RF18 Steam Generator Degradation and Operational Assessments were reviewed as required to validate the steam generator inspection interval.

The review, performed per EPRI Steam Generator Integrity Assessment Guidelines, concluded that the current inspection interval of every three refueling cycles remained adequate for both primary and secondary side SG inspections.

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Page B-80 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs Enhancements Prior to the subsequent period of extended operation, the following enhancements will be implemented in the following program element(s):

Scope of Program (Element 1); Parameters Monitored / Inspected (Element 3); Detection of Aging Effects (Element 4); and Acceptance Criteria (Element 6) 1.

Procedure(s) will be revised to require:

Visual inspections of rails, bridges, structural members, and structural components for loss of material due to general corrosion; deformation; cracking, and wear.

Visual inspections of rails, bolted connections for loss of material due to general corrosion; cracking; and loose or missing bolts or nuts, and other conditions indicative of loss of preload.

Operating Experience Summary The following examples of operating experience provide objective evidence that the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems program has been, and will be effective in managing the aging effects for SSCs within the scope of the program so that the intended functions will be maintained consistent with the current licensing basis during the subsequent period of extended operation.

1.

In April 2016, it was identified that the spent fuel pit bridge crane was generating foreign material along the rail as it moved through a section of its normal travel path adjacent to the spent fuel pool. Operation of the crane revealed that the foreign material was due to loss of material due to wear. The cause of the wear was attributed to misalignment of the guide rollers used to assist in maintaining the crane along the proper orientation. This misalignment resulted in contact between the rails and the seismic restraint brackets. New brackets were fabricated and installed for the guide rollers and the guide rollers were properly adjusted. The clearance between the seismic restraint brackets and the rails was increased to prevent grinding against the rail during operation. The results of subsequent inspections of the spent fuel pit bridge crane in 2019 and 2021 were satisfactory.

2.

In May 2017, during the Reactor Building closeout inspection following a refueling outage, metal flakes were identified along the reactor building polar crane bridge and trolley rails. This condition was reviewed by the reactor building polar crane subject matter expert who determined that the small amount of metal flakes was a normal byproduct of metal-to-metal wear between the wheels and the rails and that no immediate corrective actions were required. The results of subsequent inspections of the reactor building polar crane in 2018 and 2020 were satisfactory.

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Page B-130 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs The Flux Thimble Tube Inspection program is implemented as a Fleet program at Dominion. The program requirements and implementation procedures used across the fleet have been previously reviewed and evaluated by the NRC Staff and determinations were made for Surry Power Station (ADAMS Accession No. ML19360A020) and North Anna Power Station (ADAMS Accession No. ML21354A196) that the effects of aging will be adequately managed so that the intended function(s) will be maintained consistent with the CLB for the subsequent period of extended operation, as required by 10 CFR 54.21(a)(3).

NUREG-2191 Consistency The Flux Thimble Tube Inspection program is an existing program that, following enhancement, will be is consistent with NUREG-2191,Section XI.M37, Flux Thimble Tube Inspection.

Exception Summary None Enhancements Prior to the subsequent period of extended operation, the following enhancement will be implemented in the following program elements:

Detection of Aging Effects (Element 4) and Monitoring and Trending (Element 5)

1. Procedure(s) will be revised to require that, for situations where no wear is measured in a flux thimble tube wall during wall thickness measurements, the minimum detectable wear value will be recorded and used to establish the future inspection frequency. The future inspection frequency will be a maximum of 15 calendar years between inspections. (Added - Supplement 1)None Operating Experience Summary The following examples of operating experience provide objective evidence that the Flux Thimble Tube Inspection program will be effective in managing the aging effects for SSCs within the scope of the program so that the intended functions will be maintained consistent with the current licensing basis during the subsequent period of extended operation.

1.

In 2015, a flux thimble tube (B-10) failed during cycle 22. The isolation valve for location B-10 was closed to terminate the leakage. During the Fall 2015 refueling outage, a camera inspection of the portion of the B-10 flux thimble tube that is inserted into the RPV verified that through wall leak occurred around the area of the lower internals as industry operating experience suggested. As an extent of condition, the 50 flux thimble tubes were replaced with equivalent spares during the Fall 2015 refueling outage. A preventive maintenance item was also generated to eddy current test the flux thimble tubes on an every third refueling outage frequency regardless of the wear projections determined by the incore flux thimble tube wear assessment procedure.

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Page B-133 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs to a loss of intended function. Industry and plant-specific operating experience will be evaluated in the development and implementation of this program.

Conclusion The continued implementation of the Flux Thimble Tube Inspection program, following enhancement, will provide reasonable assurance that aging effects will be managed such that the components within the scope of this program will continue to perform their intended functions consistent with the current licensing basis during the subsequent period of extended operation.

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Page B-205 Virgil C. Summer Nuclear Station Application for Subsequent License Renewal Supplement 1 Appendix B - Aging Management Programs Enhancements Prior to the subsequent period of extended operation, the following enhancements will be implemented in the following program element(s):

Preventive Actions (Element 2) 1.

Procedure(s) will be revised to inspect and dewater, if required, the in-scope manholes after event driven occurrences, such as heavy rain, rapid thawing of ice and snow, or flooding.

2.

Procedure(s) will be revised to clarify that the frequency of manhole inspections will occur at least once a year.

Monitoring and Trending (Element 5) 3.

Procedure(s) will be revised to specify that condition monitoring cable test and inspections results that utilize visual inspection and test methods that are trendable and repeatable, will be trended to provide additional information on the rate of cable or connection insulation degradation. (Added - Supplement 1)

Operating Experience Summary The following examples of operating experience provide objective evidence that the Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements program, has been, and will be effective in managing the aging effects for SSCs within the scope of the program so that the intended functions will be maintained consistent with the current licensing basis during the subsequent period of extended operation.

1.

In March 2011, an industry operating experience event was evaluated to identify gaps in procedures and preventive maintenance activities. The industry event described an automatic reactor scram from 100% power on loss of electrical load as a result of a ground fault on the feeder cable from the station power transformer. This industry event was evaluated during the development of the Electrical Cable Reliability Management Program (ECRMP). As a result of the evaluation, medium-voltage and low-voltage power and control cable subject to adverse service conditions (such as moist environments) were included in the ECRMP. The cables within the scope of the ECRMP program are monitored, trended, and tested for insulation degradation to ensure reliability.

2.

In April 2013, the water level in an in-scope manhole exceeded the acceptance criteria in the manhole inspection procedure. Several cables were identified to be in contact with the water.

The as-found condition was due to planned excavation, during implementation of a plant modification, that had caused temporary changes in the land grading. The rain and drain design of the manhole was determined to be working, but the short-term grading changes had caused it to be temporarily overwhelmed. A sump pump was made available until the Serial No.24-101 Page 115 of 115