ML022280089

Application for Renewed Operating License, Section 3, Aging Management Review Results - Table 3.3-2, Page 130

ML022280089
Person / Time
Site:	Summer
Issue date:	08/06/2002
From:	Byrne S South Carolina Electric & Gas Co
To:	Rajender Auluck Document Control Desk, Office of Nuclear Reactor Regulation
References
NUREG-1800, RC-02-0123
Download: ML022280089 (130)

Text

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 SECTION 3 - AGING MANAGEMENT REVIEW 3.0 AGING MANAGEMENT REVIEW RESULTS For those structures and components that are identified as being subject to an aging man agement review, 10 CFR 54.21 (a)(3) requires demonstration that the effects of aging will be adequately managed so that their intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation.

This section describes the results of the aging management reviews of the components and structures determined, during the scoping and screening processes, to be subject to an aging management review. During the screening process, some structures and components (SCs) were incorporated into commodity groups based on similarity of their design or mate rials of construction. Use of commodity groups made it possible to address an entire group of SCs with a single evaluation. In the aging management reviews described in the following sections, further definition of commodity groups was performed based on design, material, environmental, and functional characteristics in order to disposition an entire group with a single aging management review.

Organization of this chapter parallels Chapter 3, "Aging Management Review Results" of NUREG-1 800, Standard Review Plan for the Review of License Renewal Applications for Nuclear Power Plants (NUREG-1800), dated April 2001. The major sections of this Chapter are:

3.1 Aging Management of Reactor Vessel, Internals, and Reactor Coolant System 3.2 Aging Management of Engineered Safety Features 3.3 Aging Management of Auxiliary Systems 3.4 Aging Management of Steam and Power Conversion Systems 3.5 Aging Management of Containments, Structures, and Component Supports 3.6 Aging Management of Electrical and Instrumentation and Controls Components and structures subject to an aging management review were evaluated to demonstrate that the effects of aging will be managed so that the intended functions will be maintained consistent with the current licensing basis for the period of extended operation.

The components, aging effects/mechanism, and aging management programs to be used for managing the effects of aging at VCSNS were compared to those listed in NUREG-1 801, Generic Aging Lessons Learned, dated April 2001. The results are documented and dis-A a ~...n

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 cussed in the following sections using the format contained in Tables 3.1-1 through 3.6-1 of NUREG-1 800. Aging management programs are described in Appendix B of this applica tion.

3.1 AGING MANAGEMENT OF REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM 3.1.1 SYSTEM DESCRIPTION VCSNS Reactor Coolant System components evaluated in this section of the application consist of the Reactor Vessel, Reactor Vessel Internals, Incore Instrumentation System, Pressurizer, Steam Generators, and associated reactor coolant system piping.

The RCS consists of three (3) closed reactor coolant loops connected in parallel to the reac tor pressure vessel. Each loop contains one steam generator, one reactor coolant pump, connecting piping and instrumentation. A pressurizer is connected, via a surge line, to the A loop reactor vessel outlet (hot leg) pipe. All components of the Reactor Coolant System are located within the Reactor Building.

Portions of the Incore Nuclear Instrumentation System (thimble tube pressure boundary),

Chemical and Volume Control System (regenerative heat exchanger and Reactor Coolant Pump seal injection and return lines), Safety Injection System (piping and valves), Residual Heat Removal System (piping and valves), Reactor Vessel Level Instrumentation/Inade quate Core Cooling Monitor System, and the Primary Sampling System (piping and isolation valves) are included in this section, because they form part of the Class 1 Reactor Coolant System boundary.

3.1.2 AGING MANAGEMENT REVIEW 3.1.2.1 Methodology Aging management review of Reactor Coolant System components and commodities con sisted of one of two approaches (or a combination of the two). The first was application of the methods described in Section 4.2 of NE' q5-10 [Reference 3.1-1]. The VCSNS AMR methodology follows the approach recommc ided in NEI 95-10 and is based on geninc industry guidance for determining aging effects for both mechanical and civil/structural com ponents. The guidance represents a set of rules that allow the evaluator to identify aging DAnE 'l C 13C -2 3.0

- AGING MANAGiEMENT REVIEW

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 effects for a given material and environment combination. The material and environment based rules in the generic industry guidance documents are derived from known age-related degradation mechanisms and industry operating experience. The guidance was reviewed for applicability to VCSNS materials of construction and component internal and external operating environments and was used to identify aging effects for components, and com modities. The results of the evaluation of materials and environment combinations, using the VCSNS methodology, are aging effects; and, if the aging effects adversely affect intended functions, the results are aging effects requiring management for the applicable components and commodities. Aging effects that require management are correlated to aging manage ment programs.

The second approach involved applying the information contained in NRC-approved indus try Generic Topical Reports applicable to Reactor Coolant System and related components.

The Generic Topical Reports provide both a list of components/ commodities requiring aging management and related aging management programs.

In either case, the aging management review identifies one or more aging management pro grams to be used to demonstrate that the effects of aging will be managed so that the intended functions will be maintained consistent with the CLB for the period of extended operation. The programs to be used for managing the effects of aging were compared to those listed in NUREG-1 801 [Reference 3.1-2] and evaluated for consistency with NUREG 1801 programs that are relied on for license renewal. The results are documented and dis cussed in Table 3.1-1 using the format suggested by the NRC Standard Review Plan for License Renewal (NUREG-1800) [Reference 3.1-3]. Aging management programs are described in Appendix B of this application.

3.1.2.2 Operating Experience Site:

VCSNS site-specific operating experience was reviewed. The site-spe cific operating experience included a review of (1) Corrective Action Program, (2) Licensee Event Reports, (3) Maintenance Rule Data Base, and (4) interviews with Systems Engineers. No additional aging effects requiring management were identified beyond those identified using the methods described in the previous Section.

Industry:

An evaluation of industry operating experience published since the effective date of NUREG-1801 was performed to identify any additional aging effects requiring management. No additional aging effects requir ing management were identified beyond those identified using the methods described in the previous Section.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 On-Going:

On-going review of plant-specific and industry operating experience is performed in accordance with the plant Operating Experience Program.

3.1.3 AGING MANAGEMENT PROGRAMS 3.1.3.1 Aging Management Programs Evaluated In NUREG-1801 That Are Relied On For License Renewal Table 3.1-1 shows the component and commodity groups (combinations of materials and environments), and aging management programs evaluated in NUREG-1 801 that are relied on for license renewal of the Reactor Coolant System, The table is based on Table 3.1-1 of NUREG-1 800 and provides a discussion of the applicability of the component commodity group and details regarding the degree to which VCSNS aging management programs are consistent with those recommended in NUREG-1 801. The discussion section includes (1) information regarding the applicability of NUREG-1801 component/commodity group to VCSNS, (2) any issues recommended in NUREG-1801 that require further evaluation, (3) details regarding VCSNS components to be included in the component/commodity group, and (4) any additional materials to be added to the component/commodity groups beyond those identified in NUREG-1801.

3.1.3.2 Further Evaluation Of Aging Management As Recommended By NUREG-1801 Further evaluation of aging management as recommended by NUREG-1801 has been incorporated into the "Discussion" column of Table 3.1-1. A cross-reference is provided to the section of the application where TLAAs are discussed.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended Reactor cool-Cumulative TLAA, evaluated Yes, TLAA The TLAA is applicable to Class 1 compo ant pressure fatigue damage in accordance with nents at VCSNS. See Section 4.3 of this boundary 10 CFR 54.21 (c) application for the TLAA discussion for fatigue components of Class 1 components.

2 Steam gener-Loss of material Inservice inspec-Yes, detection of The component/component type AMR results ator shell due to pitting and tion; water chem-aging effects is to for VCSNS are consistent with NUREG-1 801 assembly crevice corrosion istry be further evalu-in material, environment, aging effect, and ated credited program. IN 90-04 which is refer enced for this NUREG-1801 item as the basis for enhanced detection of aging effects in the shell, addressed flaw growth at girth welds due to service loading. IN 90-04 contains only general indication that pits on the surface served as crack initiation sites, and not that pitting corrosion resulted in sufficient degrada tion to cause loss of component function. No subsequent industry experience has further identified pitting corrosion resulting in report able indications for the shell. Cracking as the S.-.,.,..

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 2

result of flaw growth is an aging effect/mecha (cont.)

nism that is managed at VCSNS by the ISI Plan (Appendix B.1.7). The Chemistry Pro gram (Appendix B.1.4) manages general cor rosion, pitting corrosion and crevice corrosion.

Consistent with NUREG-1 801, this group con tains alloy steel portions of the Steam Genera tors. (Specifically the upper and lower shell and the transition cone) In addition to this, VCSNS has included the elliptical head.

3 Pressure ves-Loss of fracture TLAA, evaluated Yes, TLAA The TLAA is applicable to loss of fracture sel ferritic toughness due to in accordance with toughness of the pressure vessel at VCSNS.

materials that neutron irradia-Appendix G of 10 See Section 4.2 of this application for the have a neu-tion embrittlement CFR 50 and RG TLAA discussion of loss of fracture toughness tron fluence 1.99 of the pressure vessel.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 3

(E>1 MeV)

(cont.)

4 Reactor ves-Loss of fracture Reactor vessel Yes, plant specific The component/component type AMR results sel beltline toughness due to surveillance for VCSNS are consistent with NUREG-1 801 shell and neutron irradia-in material, environment, aging effect, and welds tion embrittlement credited program. The upper shell and noz zles are not considered the limiting compo nents for radiation embrittlement due to their physical distance from the active fuel assem blies. The Reactor Vessel Surveillance pro gram (Appendix B.1.24) will manage radiation embrittlement by addressing the most limiting sub-components with respect to exposure to the greatest fluence postulated to occur during the period of extended operation.

Consistent with NUREG-1 801, this group con tains stainless steel clad alloy steel reactor vessel components.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 5

Westing-Loss of fracture Plant specific Yes, plant specific The component/component type AMR results house and toughness due to for VCSNS are consistent with NUREG-1 801 Babcock &

neutron irradia-in material, environment, aging effect, and Wilcox(B&W) tion embrittle-credited program. The Reactor Vessel Inter baffle/former ment and void nals Inspection program (Appendix B.2.4) will bolts swelling manage the Loss of Fracture Toughness due to Neutron irradiation Embrittlement and Void Swelling for baffle former bolts.

Consistent with NUREG-1801, this group con tains stainless steel baffle former bolts for a Westinghouse plant.

6 Small-bore Crack initiation Inservice inspec-Yes, parameters The component/component type AMR results reactor cool-and growth due to tion; water chem-monitored/

for VCSNS are consistent with NUREG-1 801 ant system stress corrosion istry; one-time inspected and in material, environment, aging effect, and and con-cracking (SCC),

inspection detection of aging credited program. Small Bore Class 1 Piping nected sys-intergranular effects are to be Inspections (Appendix B.2.7), the Chemistry tems piping stress corrosion further evaluated Program (Appendix B.1.4), and In-Service cracking (IGSCC),

Inspection (ISI) Plan (Appendix B.1.7), are

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 6

and thermal and credited for management of these aging (cont.)

mechanical load-effects, and meet the intent of the NUREG ing 1801 listed programs.

Consistent with NUREG-1 801, this group.

contains cracking of small bore ASME class 1 stainless steel piping.

7 Vessel shell Crack growth due TLAA Yes, TLAA This group addresses a TLAA for underclad to cyclic loading cracking of vessels with ASME SA-508 class 2 material. The vessel at VCSNS is constructed of ASME SA-533 grade B class 1 (not ASME SA-508) material, therefore this aging effect is not applicable.

8 Reactor inter-Changes in Plant specific Yes, plant specific The component/component type AMR results nals dimension due to for VCSNS are consistent with NUREG-1 801 void swelling in material, environment, aging effect, and credited program. Some additional reactor internals components have been included in rafl.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 8

NUREG-1801. Materials listed in NUREG (cont.)

1801 and used at VCSNS are both SS and Ni alloy. However, the clevis inserts are Ni alloy at VCSNS instead of stainless steel as speci fied in NUREG-1801. The credited program is Reactor Vessel Internals Inspection (Appen dix B.2.4).

Consistent with NUREG-1801, this group con tains void swelling of the stainless steel and Ni-alloy reactor internals components. Addi tionally, irradiation creep is an aging mecha nism affecting baffle and former bolts.

9 PWR core Crack initiation Plant specific Yes, plant specific The component/component type AMR results support pads, and growth due to for VCSNS are consistent with NUREG-1801 instrument SCC and/or pri-in material, environment and aging effect.

tubes (bot-mary water stress Chemistry Program (Appendix B.1.4), Alloy tom head corrosion cracking 600 Aging Management Program (Appendix (PWSCC)

B.1.1) and In-Service Inspection (ISI) Plan A IILEi*

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Itm Gouponentnism EManagement Evaluation Discussion Item Group Mechanism Program Recommended 9

penetra-(Appendix B.1.7) are credited for manage (cont.)

tions), pres-ment of these aging effects.

surizer spray heads, and Consistent with NUREG-1801, this group con nozzles for tains cracking of various Ni alloy components.

the steam At VCSNS only the core support pads and generator bottom head penetration tubes are included in instruments this grouping.

and drains 10 Cast austen-Crack initiation Plant specific Yes, plant specific The component/component type AMR results itic stainless and growth due to for VCSNS are consistent with NUREG-1 801 steel (CASS)

SCC in material, environment and aging effect.

reactor cool-NUREG-1801 recommends evaluation of a ant system plant-specific aging management program.

piping The Chemistry Program (Appendix B.1.4) and In-Service Inspection (ISI) Plan (Appen dix B.1.7) are credited for management of these aging effects.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 10 Consistent with NUREG-1801, this group con (cont.)

tains cracking and crack growth of the of cast stainless steel RCS piping and fittings.

11 Pressurizer Crack initiation Inservice inspec-Yes, AMP for The component/component type AMR results instrumenta-and growth due to tion; water chem-PWSCC of Inconel for VCSNS are consistent with NUREG-1 801 tion penetra-PWSCC istry 182 weld is to be in material, environment, aging effect, and tions and evaluated credited program. At VCSNS this group has heater been used to envelope inconel 82/182 weld sheaths and metal for the pressurizer safe end rather than sleeves made alloy 600 bas,, metal for instrument penetra of Ni-alloys tions and heater sleeves. Alloy 600 Aging Management Program (Appendix B.1.1) is credited for management of this aging effect.

Consistent with NUREG-1801, this group con tains cracking and crack growth due to pri mary water stress corrosion cracking of Nickel-Based Alloy Pressurizer instrument penetrations and heater sleeves.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 12 Westing-Crack initiation Plant specific Yes, plant specific The component/component type AMR results house and and growth due to for VCSNS are consistent with NUREG-1801 B&W baffle SCC and irradia-in material, environment and aging effect. The former bolts tion-assisted credited aging management programs are stress corrosion Reactor Vessel Internals Inspection (Appen cracking (IASCC) dix B.2.4) and Chemistry Program (Appendix B.1.4).

Consistent with NUREG-1801, this group con tains cracking of the reactor internals stainless steel baffle former bolts.

13 Westing-Loss of preload Plant specific Yes, plant specific The component/component type AMR results house and due to stress for VCSNS are consistent with NUREG-1801 B&W baffle relaxation in material, environment and aging effects.

former bolts The credited aging management program is Reactor Vessel Internals Inspection (Appen dix B.2.4).

Consistent with NUREG-1801, this group 3.0 - AGING MANAGIEMENTI IREVIEW t

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 13 contains loss of preload of the stainless steel (cont.)

reactor internals baffle former bolts.

14 Steam gener-Loss of section Plant specific Yes, plant specific This NUREG-1801 group addresses erosion ator feedwa-thickness due to of steam generator feedwater impingement ter

erosion, plate and supports. These components do not impingement have a license renewal intended function for plate and VCSNS, therefore aging management is not support required.

15 (Alloy 600)

Crack initiation Steam generator Yes, effectiveness This group addresses cracking of various Steam gener-and growth due to tubing integrity; of a proposed aging effect/mechanisms of steam generator ator tubes, PWSCC, outside water chemistry AMP is to be eval-tube bundles, sleeves and plugs. VCSNS has repair diameter stress uated Westinghouse Delta 75 steam generators with sleeves, and corrosion cracking thermally treated alloy 690 tubes. Phosphate plugs (ODSCC), and/or water chemistry control has not been used at intergranular VCSNS. The credited aging management pro attack (IGA); or grams are the Chemistry Program (Appendix loss of material B.1.4) and Steam Generator Management due to wastage Program (Appendix B.1.10).

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 15 and pitting corro (cont.)

sion, and fretting and wear; or deformation due to corrosion at tube support plate intersections 16 Tube support Loss of section Plant specific Yes, plant specific This NUREG-1801 group addresses erosion lattice bars thickness due to of steam generator tube support lattice bars.

made of car-flow-accelerated This group is applicable to Combustion Engi bon steel corrosion (FAC) neering steam generators and does not apply to VCSNS.

17 Carbon steel Ligament cracking Plant specific Yes, effectiveness This NUREG-1801 group addresses cracking tube support due to corrosion of a proposed of carbon steel steam generator tube sup plate AMP is to be eval-ports. The tube supports at VCSNS are made uated of 405 stainless steel The alloy 690 anti-vibra tion bars are also included in this group. The Chemistry Program (Appendix B.1.4) alone is J.U - AU.*INU.i MANAJ*IMI:N I KtVIIVV PAGE.*z 15 Or 2o4l

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 17 sufficient to manage cracking.

(cont.)

18 Reactor ves-Crack initiation Reactor head clo-No The component/component type AMR results sel closure and growth due to sure studs for VCSNS are consistent with NUREG-1 801 studs and SCC and/or in material, environment and credited pro stud assem-IGSCC gram. A clarification to the aging effect requir bly ing management is required; i.e. Loss of closure integrity rather than cracking is the effect requiring management and the addi tional mechanism of stress relaxation being managed. The credited aging management program is Reactor Head Closure Studs Pro gram (Appendix B.1.8).

Consistent with NUREG-1801, this group con tains alloy steel reactor vessel closure head bolts for PWR's.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 19 CASS pump Loss of fracture Inservice inspec-No The component/component type AMR results casing and toughness due to tion for VCSNS are consistent with NUREG-1 801 valve body thermal aging in material, environment and credited pro embrittlement gram. This group addresses loss of fracture toughness (thermal embrittlement) due to thermal aging as an aging effect for cast aus tenitic stainless steel (CASS) where tempera tures continuously exceed 4820 F. The Reactor Coolant System is designed to operate at 6500 F. The applicable components fabricated from CASS are certain Reactor Coolant Sys tem Class 1 valve bodies and the reactor cool ant pump casing.

The credited aging management program is the In-Service Inspection (ISI) Plan (Appen dix B.1.7).

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 19 contains loss of fracture toughness of the cast (cont.)

stainless steel ASME class 1 pumps and valves.

20 CASS piping Loss of fracture Thermal aging No The component/component type AMR results toughness due to embrittlement of for VCSNS are consistent with NUREG-1801 thermal aging CASS in material, environment and credited pro embrittlement gram. This group addresses loss of fracture toughness (thermal embrittlement) due to thermal aging as an aging effect for cast aus tenitic stainless steel (CASS) where tempera tures continuously exceed 4820 F. The Reactor Coolant System is designed to operate at 6501F. The applicable components fabricated from CASS are the reactor coolant loop piping elbows and the 45-degree accumulator noz zle. Additionally, the control rod drive latch housings have been included in this group. In a May 9, 2000 letter, Christopher I. Grimes, Chief License Renewal and Standardization

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 20 Chief License Renewal and Standardization (cont.)

Branch clarified that not all CASS components are subject to thermal aging. The components fabricated from CASS were evaluated using the acceptance criteria set forth in the above NRC letter. The screening criteria are sup ported by the SER for WCAP-14575-A which concludes that if the screening criteria are met the material is determined "not susceptible" and no additional inspections or evaluations are required because the material has ade quate toughness.

Based on the material chemistry for the CASS components at VCSNS, these components are not susceptible to a loss of fracture tough ness due to thermal aging. The components have low molybdenum content and have delta ferrite levels of less than 20%. Therefore an J - JUI.NBP MRN~irpIJmrIM 1,vlrVV S^

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 20 aging management program is not required (cont.)

for loss of fracture toughness (thermal embrit tlement) due to thermal aging of these compo nents.

21 BWR piping Wall thinning due Flow accelerated No This NUREG-1 801 group addresses loss of and fittings; to flow acceler-corrosion material due to flow accelerated corrosion of steam gener-ated corrosion steam generator steam and feed nozzles and ator compo-safe ends.

nents VCSNS has not identified flow accelerated corrosion as a valid aging mechanism for these components.

22 Reactor cool-Loss of material Bolting integrity No The component/component type AMR results ant pressure due to wear; loss for VCSNS are consistent with NUREG-1 801 boundary of preload due to in material and environment. VCSNS is a (RCPB) valve stress relaxation; Westinghouse plant and only PWR and recir closure crack initiation culating steam generator components are applicable. A clarification to the aging effect/

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 22 bolting, man-and growth due Bolting integrity No mechanisms requiring management is (cont.)

way and to cyclic loading required. Loss of closure integrity rather than holding bolt-and/or SCC loss of preload or cracking is the effect requir ing, and clo-ing management and the additional mecha sure bolting nism of stress relaxation being managed.

in high-pres-Wear is not considered a valid aging effect/

sure and mechanisms requiring management for the high-temper-control rod drive flange bolting. In-Service ature sys-Inspection (ISI) Plan (Appendix B.1.7) is tems credited for management of these aging effects.

Consistent with NUREG-1801, this group con tains alloy steel and stainless steel class 1 bolting (other than reactor vessel closure head bolts) and steam generator class 2 bolting.

23 CRD nozzle Crack initiation Ni-alloy nozzles No The component/component type AMR results and growth due to and penetrations; for VCSNS are consistent with NUREG-1801 PWSCC water chemistry in material, environment, aging effect, and 3.U - AINU MANAMN I KVIVV

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 23 credited programs. The credited aging man (cont.)

agement program is the Alloy 600 Aging Man agement Program (Appendix B.1.1).

Consistent with NUREG-1801, this group con tains PWSCC of Ni-alloy control rod drive head penetration nozzles.

24 Reactor ves-Crack initiation Inservice inspec-No The component/component type AMR results sel nozzles and growth due to tion; water chem-for VCSNS are consistent with NUREG-1 801 safe ends cyclic Iom, g,

istry in material, environment, aging effect, and and CRD and/or SCC, and credited program. The pressurizer relief tank housing; PWSCC is not in-scope for VCSNS.

reactor cool ant system Consistent with NUREG-1801, the materials components include stainless steel, stainless steel clad (except carbon steel, Ni alloy and cast stainless steel.

The NUREG-1801 Table 1 "Component" col umn provides an exception for cast stainless steel, however, its "Item Number In GALL"

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 24 CASS and column includes cast stainless steel pumps (cont.)

bolting) and valves. VCSNS has included these com ponents in this group.

Consistent with NUREG-1801, the credited aging management programs are the Chemis try Program (Appendix B.1.4) and In-Service Inspection (ISI) Plan (Appendix B.1.7).

Whereas both the Chemistry Program and ISI are credited, ISI for this group is primarily directed at welded connections (and thereby crack growth). As such, the Chemistry Pro gram itself provides adequate management for the non-welded portions of components/

component types within this group (such as the RCP main closure flange and casing and the pressurizer tubing, couplings, and immer sion heater well assemblies). Additionally the Alloy 600 Aging Management Program 3.0 - AGING MANAGIEMIN I Kr:VIWVV nA-01-fmm 12&12

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 24 (Appendix B.1.1) is credited for management (cont.)

of primary water stress corrosion of Ni-alloy.

Consistent with NUREG-1801, this group con tains cracking and crack growth of many of the Class 1 components in a PWR. In addition to the listed components, other reactor vessel components have been included in the group.

25 Reactor ves-Loss of fracture Thermal aging and No No cast austenitic stainless steel reactor ves sel internals toughness due to neutron irradiation sel internal components are in scope for CASS com-thermal aging, embrittlement VCSNS.

ponents neutron irradia tion embrittle ment, and void swelling 26 External sur-Loss of material Boric acid corro-No The component/component type AMR results faces of car-due to boric acid sion for VCSNS are consistent with NUREG-1801 bon steel corrosion in material, environment, aging effect, and

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 26 components credited program. The pressurizer relief tank (cont.)

in reactor is not in-scope for VCSNS. The credited aging coolant sys-management program is Boric Acid Corrosion tem pressure Surveillances (Appendix B.1.2).

boundary Consistent with NUREG-1 801, this group con tains boric acid corrosion of carbon (and alloy) steel reactor coolant system components.

27 Steam gener-Loss of material Inservice inspec-No This NUREG-1801 group addresses erosion ator second-due to erosion tion of steam generator manways and hand holes ary manways of once-through steam generators. VCSNS and hand-has Westinghouse recirculating steam gener holds (car-ators.

bon steel) 28 Reactor inter-Loss of material Inservice inspec-No The component/component type AMR results nals, reactor due to wear tion for VCSNS are consistent with NUREG-1 801 vessel clo-in material, environment, aging effect, and sure studs, credited program. The materials listed in 3.0 - AGING MANAEM:N I IIVII.VV ro-Air-Zj Ur ZOZ

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 28 and core sup-NUREG-1801 and used at VCSNS are the (cont.)

port pads same; however, the material for the clevis insert is alloy 600, instead of stainless steel.

The components referenced in NUREG-1801 are the upper core plate alignment pins, ves sel flange, radial keys, clevis inserts and flux thimbles. VCSNS has also included the head vessel alignment pins in this group. The Reac tor Vessel Internals Inspection (Appendix B.2.4) is credited for reactor vessel Internals.

The In-Service Inspection (ISI) Plan (Appen dix B.1.7) is credited for the vessel flange.

The Bottom Mounted Instrumentation Inspec tion (Appendix B.1.3) is credited for aging management of the bottom mounted flux thim bles.

Consistent with NUREG-1 801, this group con tains wear of components (other than bolting)

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 28 of the reactor vessel and internals compo (cont.)

nents that are routinely dissembled.

29 Pressurizer Crack initiation Inservice inspec-No The component/component type AMR results integral sup-and growth due to tion for VCSNS are consistent with NUREG-1 801 port cyclic loading in material, environment, aging effect, and credited program. The credited aging man agement program is In-Service Inspection (ISI) Plan (Appendix B.1.7).

This NUREG-1801 group addresses crack ini tiation and growth of the pressurizer integral support.

30 Upper and Loss of preload Inservice inspec-No The component/component type AMR results lower inter-due to stress tion; loose part for VCSNS are consistent with NUREG-1801 nals assem-relaxation and/or neutron in material, environment, and aging effect. The bly noise monitoring Reactor Vessel Internals Inspection (Appen (Westing-dix B.2.4) is credited for reactor vessel Inter house) nals. VCSNS does not credit Loose Parts 3.0 - AGING MANAGEMENT RVIW PAGE 27 OF 252 C

f 3.0 - AGING MANAGEMENT REVIEW PAGE 27 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 30 Monitoring or Neutron Noise Monitoring.

(cont.)

Consistent with NUREG-1801, this group con tains loss of preload of the stainless steel holddown spring and the Ni-alloy clevis insert bolts.

31 Reactor ves-Loss of fracture PWR vessel inter-No The component/component type AMR results sel internals toughness due to nals; water chem-for VCSNS are consistent with NUREG-1 801 in fuel zone neutron irradia-istry in material, environment, and aging effect.

region tion embrittle-VCSNS is a Westinghouse plant and only the (except West-ment and void Westinghouse components are applicable.

inghouse and swelling The Reactor Vessel Internals Inspection pro B&W baffle gram (Appendix B.2.4) will manage the loss former bolts) of fracture toughness for applicable compo nents. The Chemistry Program is not credited for managing loss of fracture toughness.

Consistent with NUREG-1801, this group con tains loss of fracture toughness due to 3.U f-A#*a3l/'4I Mi iI.2*PlIPI?

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect, Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 31 irradiation embrittlement in components in (cont.)

close proximity to the core.

32 Steam gener-Crack initiation Inservice inspec-No The component/component type AMR results ator upper and growth due to tion; water chem-for VCSNS are consistent with NUREG-1801 and lower SCC, PWSCC, istry in material, environment, aging effect, and

heads, and/or IASCC credited program. NUREG-1801 group only tubesheets, identifies the steam generator primary side and primary nozzles and safe ends. VCSNS has included nozzles and all of the primary side of the steam generator safe ends except tubes, plug and sleeves. VCSNS is a Westinghouse plant and has recirculating steam generator. The credited aging manage ment programs are Chemistry Program (Appendix B.1.4), In-Service Inspection Plan (Appendix B.1.7) and Alloy 600 Aging Man agement Program (Appendix B.1.1).

Consistent with NUREG-1801, this group con tains cracking of steam generator primary

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 32 nozzles and safe ends.

(cont.)

33 Vessel inter-Crack initiation PWR vessel inter-No The component/component type AMR results nals (except and growth due to nals; water chem-for VCSNS are consistent with NUREG-1801 Westing-SCC and IASCC istry in material, environment, aging effect, and house and credited program. VCSNS is a Westinghous B&W baffle plant and only Westinghouse components are former bolts) applicable. there is difference in material. The clevis inserts are alloy 600 at VCSNS instead of stainless steel as shown in NUREG-1801.

Head/vessel alignment pins, secondary core support and spray nozzles for upper plenum cooling, are being included in this item.

Although they are not addressed in this NUREG-1801 group, with respect to material, environment, aging effect requiring manage ment, and credited program the sub-compo nent AMR results are consistent with NUREG 1801. The Reactor Vessel Internals Inspection "fl -*

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 33 program (Appendix B.2.4) and the Chemistry (cont.)

Program (Appendix B.1.4) will manage crack initiation and growth in these components.

Consistent with NUREG-1801, this group con tains crack initiation and growth of the stain less steel and Ni-alloy reactor internals except baffle former bolts.

34 Reactor ves-Loss of material Reactor head clo-No The component/component type AMR results sel closure due to wear sure studs for VCSNS are consistent with NUREG-1 801 studs and in material, environment, aging effect, and stud assem-credited program. The credited program is bly and stud Reactor Head Closure Studs Program assembly (Appendix B.1.8).

Consistent with NUREG-1801, this group con tains wear of the alloy steel reactor vessel clo sure stud assembly.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 35 Reactor inter-Loss of preload Inservice inspec-No The component/component type AMR results nals (West-due to stress tion; loose part for VCSNS are consistent with NUREG-1801 inghouse relaxation monitoring in material, environment, aging effect, and upper and credited program. Material used at VCSNS is lower inter-stainless steel. NUREG-1801 lists both stain nal assem-less steel and Ni alloy. Whereas NUREG-1 801 blies, CE specifies the ASME Section Xl ISI and Loose bolts and tie Parts Monitoring, VCSNS credits only the rods)

Reactor Vessel Internals Inspection (Appen dix B.2.4).

Consistent with NUREG-1801, this group con tains loss of preload of the stainless steel reactor internals upper and lower support col umn bolts.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.1.3.3 Aging Management Evaluations That Are Different From Or Not Addressed In NUREG-1801 Aging Management Evaluations that are different from or not addressed in NUREG-1 801 are identified and discussed in Table 3.1-2. The standard six-column format has been uti lized. The discussion column provides additional details regarding the aging management conclusions reached by VCSNS for the component type.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Item Type Mechanism Program/Activity Discussion Piping and Stainless Steel Air-gas (moist None Identified None Required This grouping includes piping sys-(including Cast air) external surfaces of stain tem compo-Austenitic Stain-less steel piping system nents less Steel) components exposed to a moist air environment. At VCSNS, the ambient envi ronment does not contain contaminants of sufficient concentration to cause aging effects that require aging management.

2 Piping and Nickel-Based Air-gas (moist None Identified None Required This grouping includes piping sys-Alloy, Stainless air) external surfaces of Nickel tem compo-Steel with Nickel-Based Alloy piping system nents Based Weld components exposed to a moist air environment. At VCSNS, the ambient envi ronment does not contain contaminants of sufficient concentration to cause I2 Al fl AVII

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Program/Activity Discussion Item Type Mechanism 2

aging effects that require (cont.)

aging management.

3 Steam Gen-Carbon Steel Treated Water Loss of Material/

Chemistry Pro-This grouping includes car erator Com-Crevice Corro-gram bon steel components ponents sion, General Cor-exposed to the treated (Other than rosion, Pitting water/ steam environment Shell - Upper Corrosion, Gal-inside the steam generator.

and Lower vanic Corrosion VCSNS has determined the Barrel, Tran-Chemistry Program sition Cone, (Appendix B.1.4) provides Elliptical adequate management for Head) these secondary side com ponents of the steam gen erator, which are not specifically addressed in NUREG-1801 chapter IV.

4 Instrumenta-Stainless Steel Reactor Building Loss of Mechani-In-Service Inspec-Loss of mechanical closure tion (Pres-cal Closure Integ-tion (ISI) Plan integrity due to stress relax sure rity/ Stress ation, stress corrosion a

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SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect/

Program/Activity Discussion Item Type Mechanism 4

Retaining Relaxation, Wear cracking, and or wear of (cont.)

Only)- Incore bolted closures is an aging Thermocou-effect requiring evaluation pies Seal for the in-core thermocou ple seal assemblies. Stress relaxation (loss of preload) of bolting materials is a concern at the elevated temperatures at which the Reactor Coolant System operates. Stress corrosion cracking is a concern for high strength bolting (> 150 ksi) materials in Class 1 closure applications. Wear of bolted closures is a con cern due to relative motion during infrequent (periodic) disassembly and reassem bly operations. The 3.U APi*IIE'4UM*~

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Program/Activity Discussion Item Type Mechanism 4

In-Service Inspection (ISI)

(cont.)

Plan (Appendix B.1.7) is credited for management of these aging effects.

5 Piping and Stainless Steel Chemically Loss of Material Chemistry Pro-This grouping includes piping sys-Treated Borated due to Crevice gram stainless steel piping and tem compo-Water Corrosion, Pitting piping system components nents Corrosion in chemically treated borated water. The Chemis try Program (Appendix B.1.4) alone provides aging management for loss of material of stainless steel in chemically treated borated water environment.

6 Piping and Stainless Steel Chemically Crack Initiation Chemistry Pro-This grouping includes piping sys-Treated Borated and Growth/

gram stainless steel piping and tem compo-Water Stress Corrosion piping system components nents Cracking in chemically treated 3.0 - AGING MANAGIEMIN I Ir:VI:VV a.DAIME

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Item Type Mechanism ProgramIActivity Discussion 6

borated water. The Chemis (cont.)

try Program (Appendix B.1.4) alone provides aging management for cracking of stainless steel in a chem ically treated borated water environment.

7 Reactor Inter-Stainless Steel Chemically Loss of Material Chemistry Pro-This grouping includes nals compo-and Ni-alloy Treated Borated due to Crevice gram stainless steel and Ni-alloy

nents, Water Corrosion, Pitting Reactor Coolant System Reactor ves-Corrosion components in chemically sel, Pressur-treated borated water. The izer, RCP, Chemistry Program Incore ther-(Appendix B.1.4) alone mocouple provides aging manage seal ment for loss of stainless steel material in chemically treated borated water envi ronment.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Program/Activity Discussion Item Type Mechanism 8

Steam Gen-Nickel-Based Treated Water Loss of Material Chemistry Pro-This grouping includes Ni erator Sec-Alloy (Alloy 690 due to Crevice gram alloy steam generator sec ondary Side TT)

Corrosion, Pitting ondary side components.

Thermal Corrosion The Chemistry Program

Sleeves, (Appendix B.1.4) provides Steam Flow adequate management for Limiter loss of material of these secondary side compo nents of the steam genera tor in a treated water environment, which are not specifically addressed in GALL chapter IV.

9 Steam Gen-Nickel-Based Treated Water Crack Initiation Chemistry Pro-This grouping includes Ni erator Sec-Alloy (Alloy 690 and Growth/

gram, The In-Ser-alloy steam generator sec ondary Side TT)

Stress Corrosion vice Inspection ondary side components.

Thermal Cracking, Flaw (ISI) Plan The Chemistry Program

Sleeves, Growth at Welds (Appendix B.1.4) and the Steam Flow In-Service Inspection (ISI)

Limiter Plan (Appendix B.1.7) a a a n,

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect P

Item Type Mechanism Program/Activity Discussion 9

provide adequate manage (cont.)

ment for cracking of these secondary side compo nents of these steam gen erator in a treated water environment, which are not specifically addressed in GALL chapter IV.

10 Steam Gen-Alloy Steel Treated Water Loss of Material Chemistry Pro-This grouping includes alloy erator Feed-(Chrome Moly) due to Crevice gram, The In-Ser-feedwater distribution com water Corrosion, Pitting vice Inspection ponents. The Chemistry Distribution Corrosion; Crack (ISI) Plan Program (Appendix B.1.4)

Pipe & Fit-initiation and and the In-Service Inspec tings growth/ Stress tion (ISI) Plan (Appendix corrosion cracking B.1.7) provide adequate management for loss of material and cracking of these secondary side com ponents of the steam gen erator.

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K LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Program/Activity Discussion Item Type Mechanism 11 Reactor Inter-Stainless Steel Chemically Crack Initiation Chemistry Pro-This grouping includes nals compo-and Nickel-Treated Borated and Growth/

gram stainless steel and Ni-alloy

nents, Based Alloy Water Stress Corrosion Reactor Coolant System Reactor ves-Cracking components in chemically sel, Pressur-treated borated water. The izer, RCP, Chemistry Program Incore ther-(Appendix B.1.4) alone mocouple provides aging manage seal ment for cracking of stain less steel and Ni-alloy in a chemically treated borated water environment.

12 Capillary Stainless Steel Treated Water None Identified None Required This group includes stain tubes and less steel capillary tubes associated and associated compo components nents exposed to treated water and is consistent in material and environment with NUREG-1801 closed cycle cooling water 3.0 - AGING MANAGEMENT REVIEW f

PAGE OF" 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL Component Type Material I

r T

Environment Aging Effect /

Mechanism F

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I Tube Sup port Plates Plates, AVBs, Flow Distribu tion Baffle Secondary Side for Steam Gen erators Stainless Steel/

Nickel Based Tips & Rings

'--:ated Water Loss of Material due to Crevice Corrosion, Pitting Corrosion; Crack Initiation and Growth/ Stress Corrosion Crack ing, Primary Water Stress Cor rosion Cracking)

Program/Activity Chemistry Pro gram Discussion components. However, at VCSNS, no aging effects were determined to require management due to no means of oxygen or other contaminant entry existing for the deaerated distilled water inside these capillary tubes and associated com ponents.

This grouping includes stainless steel Ni-alloy steam generator compo nents in treated water. The Chemistry Program (Appendix B.1.4) alone provides aging manage ment for loss of material and cracking of stainless steel and Ni-alloy in a n __________________

J ___________________

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-I801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect Program/Activity Discussion Item Type Mechanism 13 treated water/ steam envi (cont.)

ronment.

14 Piping and Stainless Steel Treated Water Loss of Material Chemistry Pro-This grouping includes piping sys-due to Crevice gram stainless steel piping and tem compo-Corrosion, Pitting associated components nents Corrosion exposed to treated water from the Reactor Makeup Water system for Pressur izer Relief Tank spray. It is consistent in material and environment, aging effect and credited program with NUREG-1801 closed-cycle cooling water components.

The Chemistry Program (Appendix B.1.4) provides adequate management for this component, material and environment that is not specifically addressed in 3..

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.1-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE REACTOR COOLANT SYSTEM THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Item Type Mechanism Program/Activity Discussion 14 NUREG-1801 chapter IV.

(cont.)

15 Piping and Stainless Steel Air-gas None Identified None Required This grouping includes the piping sys-internal surfaces of stain tern compo-less steel piping system nents components exposed to a gas environment that is not subject to wetting. The gas environment does not con tain contaminants of suffi cient concentration to cause aging effects that require aging management.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 3.

1.4 REFERENCES

3.1-1 NEI 95-10, Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule, Nuclear Energy Institute, Revision 3, March 2001.

3.1-2 NUREG-1 801, "Generic Aging Lessons Learned Report," Volumes 1 and 2, NRC, April 2001.

3.1-3 NUREG-1 800, "Standard Review Plan for Review of License Renewal Appli cations for Nuclear Power Plants," NRC, April 2001.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.2 AGING MANAGEMENT OF ENGINEERED SAFETY FEATURES 3.2.1 SYSTEM DESCRIPTION Engineered Safety Features (ESF) are provided to mitigate the consequences of postulated accidents up to and including a design basis accident as discussed in Chapter 15 of the FSAR. The ESF systems provided for VCSNS have sufficient redundancy and indepen dence of components and power sources that, under postulated accident conditions, the fol lowing are accomplished:

1. Core cooling limits the core thermal transient, thereby preventing excessive metal-water reactions and maintaining coolable core geometry.

2. Reactor Building structural integrity is maintained.

3. Radiation dose to the public is maintained within the limits of 10 CFR 100.

The ESF systems include the following systems:

"* Chemical and Volume Control System

"* Containment Isolation System

"* Hydrogen Removal System

"* Reactor Building Spray System

"* Refueling Water System

"* Residual Heat Removal System

"* Safety Injection System 3.2.2 AGING MANAGEMENT REVIEW 3.2.2.1 Methodology Aging management review of Engineered Safety Features System components and com modities involved consideration and evaluation of the materials, environments, and stres sors that are associated with each component, or commodity grouping under review, as discussed in Section 4.2 of NEI 95-10 [Reference 3.2-1]. The VCSNS AMR methodology follows the approach recommended in NEI 95-10 and is based on generic industry guidance for determining aging effects for both mechanical and civil/structural components. The guid ance represents a set of rules that allow the evaluator to identify aging effects for a given material and environment combination. The material and environment-based rules in the DAf%-

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 generic industry guidance documents are derived from known age-related degradation mechanisms and industry operating experience. The guidance was reviewed for applicability to VCSNS materials of construction and component internal and external operating environ ments and was used to identify aging effects for components, structures, and commodities.

The results of the evaluation of materials and environment combinations, using the VCSNS methodology, are aging effects; and, if the aging effects adversely affect intended functions, the results are aging effects requiring management for the applicable components and com modities. Aging effects that require management are correlated to aging management pro grams.

The aging management review identifies one or more aging management programs to be used to demonstrate that the effects of aging will be managed so that the intended functions will be maintained consistent with the CLB for the period of extended operation. The pro grams to be used for managing the effects of aging were compared to those listed in NUREG-1801 [Reference 3.2-2] and evaluated for consistency with NUREG-1801 pro grams that are relied on for license renewal. The results are documented and discussed in Table 3.2-1 using the format suggested by the NRC Standard Review Plan for License Renewal (NUREG-1800) [Reference 3.2-3].

3.2.2.2 Operating Experience Site:

VCSNS site-specific operating experience was reviewed. The site-spe cific operating experience included a review of (1) Corrective Action Program, (2) Licensee Event Reports, (3) Maintenance Rule Data Base, and (4) interviews with Systems Engineers. No additional aging effects requiring management were identified beyond those identified using the methods described in the previous Section.

Industry:

An evaluation of industry operating experience published since the effective date of NUREG-1801 was performed to identify any additional aging effects requiring management. No additional aging effects requir ing management were identified beyond those identified using the methods described in the previous Section.

On-Going:

On-going review of plant-specific and industry operating experience is performed in accordance with the plant Operating Experience Program.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 3.2.3 AGING MANAGEMENT PROGRAMS 3.2.3.1 Aging Management Programs Evaluated In NUREG-1801 That Are Relied On For License Renewal Table 3.2-1 shows the component and commodity groups (combinations of materials and environments) and aging management programs evaluated in NUREG-1801 that are relied on for license renewal of the Engineered Safety Features Systems. The table is based on Table 3.2-1 of NUREG-1800 [Reference 3.2-3] and provides a discussion of the applicability of the component commodity group and details regarding the degree to which VCSNS aging management programs are consistent with those recommended in NUREG-1 801. The dis cussion section includes (1) information regarding the applicability of NUREG-1801 compo nent/commodity group to VCSNS, (2) any issues recommended in NUREG-1 801 that require further evaluation, (3) details regarding VCSNS components to be included in the component/commodity group, and (4) any additional materials to be added to the compo nent/commodity groups beyond those identified in NUREG-1801.

3.2.3.2 Further Evaluation Of Aging Management As Recommended By NUREG-1801 Further evaluation of aging management as recommended by NUREG-1 801 has been incorporated into the "Discussion" column of Table 3.2-1. A cross-reference is provided to the section of the application where TLAAs are discussed.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect/

Aging Further Am Comp Aging Management Evaluation Discussion Item Group Mechanism Program Recommended Piping, fit-Cumulative TLAA, evaluated Yes, TLAA The TLAA is applicable to Class 2 and 3 pip tings, and fatigue damage in accordance with ing systems at VCSNS. See Section 4.3.2 for valves in 10 CFR 54.21(c) the TLAA discussion of Class 2 and 3 piping emergency systems. VCSNS is a Westinghouse PWR core cooling plant.

system 2

Components Loss of material Plant specific Yes, plant specific The VCSNS Containment Spray System is in contain-due to general made of stainless steel, rather than carbon ment spray corrosion steel.

(PWR only),

standby gas Four systems at VCSNS have been identified treatment whose only license renewal function is to pro system (BWR vide containment isolation. These systems only), con-are: Auxiliary Coolant (Closed Loop) / CRDM tainment iso-Cooling Water (AC), Demineralized Water lation, and Nuclear Service (DN), RB Leak Rate Testing emergency (LR) and Nitrogen Blanketing (NG). AC, LR, core cooling and NG contain carbon steel components in systems scope. Inspections for Mechanical

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect/

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 2

Components (Appendix B.2.11) are credited (cont.)

for detecting and managing the loss of mate rial due to general corrosion on the external surfaces of carbon steel components. The air gas environments inside NG and LR compo nents do not contain contaminants of sufficient concentration to cause general corrosion severe enough to warrant managing. The Chemistry Program (Appendix B.1.4) is cred ited with providing aging management of cor rosion of the interior of AC System components.

Consistent with NUREG-1 801, this group con tains carbon steel in ambient air, and treated water environments. Additionally compressed gas is included in this group.

3 Components Loss of material Plant specific Yes, plant specific This group contains the Refueling Water Stor in due to pitting and age Tank (RWST) and systems whose only 3.0 - AGING MANAGEMENT REVIEW PAGE 50 OF 252 3.0 - AGING MANAGEMENT REVIEW

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 3

containment crevice corrosion Plant specific Yes, plant specific license renewal function is to provide contain (cont.)

spray (PWR ment isolation.

only),

standby gas VCSNS has determined that loss of material treatment of the underside of the RWST is not an aging system (BWR effect requiring management as this stainless only), con-steel tank is not buried.

tainment iso lation, and Four systems at VCSNS have been identified emergency whose only license renewal function is to pro core cooling vide containment isolation. These systems systems are: AC, DN, LR and NG. Pitting and crevice corrosion does not require aging management for the exterior environments of stainless steel components. Inspections for Mechanical Com ponents (Appendix B.2.11) is credited for detecting and managing the loss of material due to pitting, crevice, and galvanic corrosion on the external surfaces of carbon steel 5.U - AUINIU MANAM.UMIN I I.VIWVV

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 3

components. The air-gas environments inside (cont.)

NG and LR components do not contain con taminants of sufficient concentration to cause pitting and crevice corrosion severe enough to warrant managing. The Chemistry Program (Appendix B.1.4) is credited with providing aging management of corrosion of the interior of AC and DN System components.

Consistent with NUREG-1801, this group con tains both carbon and stainless steel in ambi ent air, and treated water environments.

Additionally compressed gas is included in this group.

4 Containment Loss of material Plant specific Yes, plant specific Microbiologically influenced corrosion has isolation due to microbio-been determined not to be a valid aging valves and logically influ-effects/mechanisms for the component/com associated enced corrosion ponent type material and environment combi piping (MIC) nation represented by this group. The four

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 4

systems at VCSNS that have been identified (cont.)

to provide containment isolation are not sub ject to wetting from raw water. These systems are: AC, DN, LR and NG.

5 High-pres-Loss of material Plant specific Yes, plant specific NUREG-1 801 V.D1.2-c addresses Emergency sure safety due to erosion Core Cooling System orifices. The compo injection nent/component type AMR results are consis (charging) tent with the identified GALL item in material pump mini-and environment. However, the identified flow orifice GALL item recommends plant specific evalua tion of the credited program. VCSNS consid ers this aging effect/mechanism a design problem, and does not have an identified aging management program for erosion of mini-flow orifices.

6 External sur-Loss of material Plant specific Yes, plant specific The component/component type AMR results face of car-due to general for VCSNS are consistent with NUREG-1 801 bon steel corrosion in material, environment, aging effect and J.U - AlIN, M, N I.Mt I

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 6

components credited program.

(cont.)

Consistent with NUREG-1801, this group con tains the external surfaces of carbon steel components. In addition to carbon steel, VCSNS has included cast iron in this group.

Consistent with NUREG-1801, the aging mechanism for this group is general corrosion.

NUREG-1801 recommends a plant specific evaluation of the credited program. The cred ited program/activity at VCSNS is Inspections for Mechanical Components (Appendix B.2.11).

7 Piping and fit-Loss of fracture Thermal aging No The component/component type AMR results tings of toughness due to embrittlement of for VCSNS are not consistent with NUREG CASS in thermal aging CASS 1801 in material, environment, aging effect emergency embrittlement and program. VCSNS does not have cast I

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r LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 7

core cooling stainless steel in ESF Systems subject to tern (cont.)

systems peratures over 4820 F.

8 Components Loss of material Open-cycle cool-No The component/component type AMR results serviced by due to general, ing water system for VCSNS are not consistent with NUREG open-cycle pitting, and crev-1801 in material, environment, aging effect cooling sys-ice corrosion, and program. VCSNS component/component tem MIC, and biofoul-type AMR results for components serviced by ing; buildup of open-cycle cooling systems are contained in deposit due to Auxiliary Systems, Section 3.3.

biofouling 9

Components Loss of material Closed-cycle cool-No The component/component type AMR results serviced by due to general, ing water system for VCSNS are consistent with NUREG-1 801 closed-cycle pitting, and crev-in material, environment and aging effect.

cooling sys-ice corrosion NUREG-1801 recommends a closed cycle tem cooling program. The credited program/activ ity at VCSNS is the Chemistry Program (Appendix B.1.4). The Chemistry Program has been in effect since initial plant startup 3.0 - AGING MANAGEMENT REVIEW P"AGEim 55 OFp 2

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 9

and has proven effective in maintaining sys (cont.)

tems' chemistry and detecting abnormal con ditions. A review of operating experience confirms the effectiveness of the Chemistry Program to manage aging effects when con tinued into the period of extended operation. A verification program is, therefore, not war ranted for the components/ component types in this group. The aging mechanisms for this group include loss of material due to general corrosion, crevice corrosion and pitting corro sion. In addition to these aging mechanisms, stress corrosion cracking is managed for this group at VCSNS.

Consistent with NUREG-1801, this group includes carbon steel and stainless steel com ponents in borated or treated water environ ments.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 9

(cont.)

Consistent with NUREG-1 801, this group includes heat exchanger components.

VCSNS does not utilize heat exchangers in the Containment Spray System (Reactor Building Spray System at VCSNS). Some components may also be shown or listed in Auxiliary Systems, Section 3.3.

10

Pumps, Crack initiation Water chemistry No The component/component type AMR results valves, pip-and growth due to for VCSNS are consistent with NUREG-1 801 ing and fit-SCC in material, environment and aging effects.

tings, and The credited program/activity at VCSNS is the tanks in con-Chemistry Program (Appendix B.1.4).

tainment spray and Consistent with NUREG-1 801, this group emergency includes stainless steel and stainless steel core cooling cladding in borated or treated water environ system ments.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 10 Consistent with NUPir3-1801, this group (cont.)

includes stress corrosion cracking of stainless steel and stainless steel clad pumps, valves, piping, fittings and tanks. In addition to this aging mechanism, crevice and pitting corro sion are also managed for this group at VCSNS.

11 Carbon steel Loss of material Boric acid corro-No The component/component type AMR results components due to boric acid sion for VCSNS are consistent with NUREG-1801 corrosion corro-in material, environment, aging effect and sion credited program. The credited program/activ ity at VCSNS is Boric Acid Corrosion Surveil lances (Appendix B.1.2).

Consistent with NUREG-1 801, this group con tains external surfaces of carbon and low alloy steel components/component types in an ambient air environment, where there is a potential for leaking and dripping of chemically

-A INA VI...PAE.58.OF.25 3.0 - AGING MANAGEMENT REVIEW PAGE 58 OF 252

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 11 treated borated water onto component sur (cont.)

faces.

12 Closure bolt-Loss of material Bolting integrity No Loss of mechanical closure integrity is not ing in high-due to general considered an aging effect requiring evalua pressure or corrosion; crack tion for Non-Class 1 component bolted clo high-temper-initiation and sures within the scope of license renewal at ature sys-growth due to VCSNS. As such, the specific bolting/fastener tems cyclic loading and/

materials of subject components/component or SCC types within the scope of license renewal were not itemized as a separate Non-Class 1 com ponent/component type. Rather, bolting was treated as a "piece-part" (or sub-component/

sub-part) of Non-Class 1 components/compo nent types.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.2.3.3 Aging Management Evaluations That Are Different From Or Not Addressed In NUREG-1801 Aging Management Evaluations that are different from or not addressed in NUREG-1801 are identified and discussed in Table 3.2-2. The standard six-column format has been uti lized. The discussion column provides additional details regarding the aging management conclusions reached by VCSNS for the component type.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE ENGINEERED SAFETY FEATURES THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Program/Activity Discussion Item Type Mechanism Piping and Stainless Steel Air-gas None Identified None Required This grouping includes piping sys-(including Cast) internal and external sur tern compo-faces of stainless steel pip nents (This ing system components includes exposed to non-corrosive tanks pump gas environment. At casings filter VCSNS, the ambient envi housings and ronment of the yard and heat sheltered environments do exchanger not contain contaminants of components.)

sufficient concentration to cause aging effects that require aging management.

2 Piping and Carbon Steel Air-gas (dry)

None Identified None Required This grouping includes piping sys-external surfaces of carbon tern compo-steel piping system compo nents nents exposed to air that are not subject to wetting. It also includes the internal surface of these 3.0 - AGING MANAGFEMENT REVIEVW

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P"AGEl 61 OF 252J

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE ENGINEERED SAFETY FEATURES THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect P

Item Type Mechanism ProgramlActivity Discussion 2

components when exposed (cont.)

to dry air or non-corrosive process gasses.

3 Recombiner Nickel-based Air-gas None Identified None Required This grouping contains the H2 Alloy Post-accident H2 recom biner. Nickel-based alloys do not require aging man agement in the air environ ment of the Reactor Building.

4 Piping and Carbon Steel, Oil None Identified None Required This grouping includes oil piping sys-copper-nickel coated surfaces of system tem compo-components exposed to nents lubricating oil that are not subject to wetting. These components are various components in the RCP lube oil systems that are continuously in service.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE ENGINEERED SAFETY FEATURES THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Program/Activity Discussion Item Type Mechanism 5

Reactor Stainless Steel, Treated Water Loss of Material/

Chemistry Pro-Consistent with NUREG Building Carbon Steel (Less Than General Corro-gram and Above 1801 for non-ESF systems, Spray com-140OF with Caus-sion (carbon steel Ground Tank the Chemistry Program ponents tic) only), Crevice Inspection (Appendix B.1.4) is cred associated Corrosion, Pitting ited for management of the with NaOH Corrosion; Crack-specified aging effects in addition Pip-ing/ Stress Corro-the associated caustic ing and pip-sion Cracking treated water environment.

ing system However, due to the lack of components oxygen control in the supply to the Sodium Hydroxide Storage Tank a one-time inspection is required as part of the Above Ground Tank Inspection (Appen dix B.2.1) at VCSNS to ensure that carbon steel portions are not experienc ing sufficient degradation to cause loss of intended n £ 

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SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE ENGINEERED SAFETY FEATURES THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect P

Item Type Mechanism Program/Activity Discussion 5

function during the period of (cont.)

extended operation.

6 Capillary Stainless Steel Treated Water None Identified None Required This group includes stain tubes and less steel capillary tubes associated and associated compo components nents exposed to treated water and is consistent in material and environment with NUREG-1801 closed cycle cooling water compo nents. However, at VCSNS, no aging effects were deter mined to require manage ment due to no means of oxygen or other contami nant entry existing for the deaerated distilled water inside these capillary tubes and associated compo nents.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE ENGINEERED SAFETY FEATURES THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Program/Activity Discussion Item Type Mechanism 7

Refueling Stainless Steel Treated Water Loss of Material Chemistry Pro-The components in the Water Stor-due to Crevice gram, Above grouping are partially con age Tank Corrosion, Pitting Ground Tank sistent with a NUREG-1 801 (including Corrosion; Crack-Inspection Engineered Safety Feature attached pip-ing Due To Corro-item with respect to mate ing) sive Impacts Of rial, environment, aging Alternate Wetting effect requiring manage And Drying ment and aging manage ment program (Chemistry Program). However, addi tional aging effects require management at VCSNS for this ESF grouping.

NUREG-1801 does not address the corrosive impacts of alternate wet ting and drying of vented tanks (or tanks without a cover gas) that could con centrate contaminants a

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SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE ENGINEERED SAFETY FEATURES THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect/

Program/Activity Discussion Item Type Mechanism 7

above bulk fluid concentra (cont.)

tions and result in further degradation.

The Chemistry Program (Appendix B.1.4) will man age the conditions required for a loss of material or cracking of the components in this grouping to occur in bulk fluid concentrations. In addition, the one-time Above Ground Tank Inspection (Appendix B.2.1) will manage the cor rosive impacts of alternate wetting and drying to occur in stainless steel in the treated water environment.

These programs, A

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.2-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE ENGINEERED SAFETY FEATURES THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Program/Activity Discussion Item Type Mechanism 7

when continued into the (cont.)

period of extended opera tion, will provide reasonable assurance that the compo nent intended function(s) will be maintained under all CLB conditions.

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2.4 REFERENCES

3.2-1 NEI 95-10, Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule, Nuclear Energy Institute, Revision 3, March 2001.

3.2-2 NUREG-1801, "Generic Aging Lessons Learned Report," Volumes 1 and 2, NRC, April 2001.

3.2-3 NUREG-1800, "Standard Review Plan for Review of License Renewal Appli cations for Nuclear Power Plants," NRC, April 2001.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS 3.3.1 SYSTEM DESCRIPTION The Auxiliary Systems are those systems used to support normal and emergency plant operations. The systems provide cooling, ventilation, sampling and other required functions.

The Auxiliary Systems include the following systems:

Air Handling and Local Ventilation and Cooling Systems Boron Recycle System Chilled Water System Component Cooling Water System Diesel Generator Services Systems Fire Service System Fuel Handling System Gaseous Waste Processing System Instrument Air Supply System Liquid Waste Processing System Nuclear Plant Drains Non-Nuclear Plant Drains Nuclear Sampling System Radiation Monitoring System Reactor Makeup Water Supply System Roof Drains System

• Station Service Air System

• Service Water System Spent Fuel Cooling System

• Thermal Regeneration System 3.3.2 AGING MANAGEMENT REVIEW 3.3.2.1 Methodology Aging management review (AMR) of Auxiliary Systems components and commodities involved consideration and evaluation of the materials, environments, and stressors that are associated with each component, or commodity grouping under review, as discussed in Section 4.2 of NEI 95-10 [Reference 3.3-1]. The VCSNS AMR methodology follows the approach recommended in NEI 95-10 and is based on generic industry guidance for deter-A

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The aging management review identifies one or more aging management programs to be used to demonstrate that the effects of aging will be managed so that the intended functions will be maintained consistent with the CLB for the period of extended operation. The pro grams to be used for managing the effects of aging were compared to those listed in NUREG-1801 [Reference 3.3-2] and evaluated for consistency with NUREG-1801 pro grams that are relied on for license renewal. The results are documented and discussed in Table 3.3-1 using the format suggested by the NRC Standard Review Plan for License Renewal (NUREG-1800) [Reference 3.3-3].

3.3.2.2 Operating Experience Site:

VCSNS site-specific operating experience was reviewed. The site-spe cific operating experience included a review of (1) Corrective Action Program, (2) Licensee Event Reports, (3) Maintenance Rule Data Base, and (4) interviews with Systems Engineers. No additional aging effects requiring management were identified beyond those identified using the methods described in the previous Section.

Industry:

An evaluation of industry operating experience published since the effective date of NUREG-1 801 was performed to identify any additional aging effects requiring management. No additional aging effects requir ing management were identified beyond those identified using the methods described in the previous Section.

On-Going:

On-going review of plant-specific and industry operating experience is performed in accordance with the plant Operating Experience Program.

3.U - AGING MANAiEMENT IRE VIEW DAIdE 97 M.E -

2

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 3.3.3 AGING MANAGEMENT PROGRAM 3.3.3.1 Aging Management Programs Evaluated In NUREG-1801 That Are Relied On For License Renewal Table 3.3-1 shows the component and commodity groups (combinations of materials and environments), and aging management programs evaluated in NUREG-1801 that are relied on for license renewal of the Auxiliary Systems. The table is based on Table 3.3-1 of NUREG-1800 [Reference 3.3-3] and provides a discussion of the applicability of the compo nent commodity group and details regarding the degree to which VCSNS aging manage ment programs are consistent with those recommended in NUREG-1 801. The discussion section includes (1) information regarding the applicability of NUREG-1801 component/com modity group to VCSNS, (2) any issues recommended in NUREG-1801 that require further evaluation, (3) details regarding VCSNS components to be included in the component/com modity group, and (4) any additional materials to be added to the component/commodity groups beyond those identified in NUREG-1801.

3.3.3.2 Further Evaluation Of Aging Management As Recommended By NUREG-1 801 Further evaluation of aging management as recommended by NUREG-1801 has been incorporated into the "Discussion" column of Table 3.3-1. A cross-reference is provided to the section of the application where TLAAs are discussed.

- A9iIN MANAGEMENT REVIEW PAGE 71 OF 22 PAGE 71 OF 252 3.0 - AGING MANAGEMENT I EVIEW

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended Components Loss of material Water chemistry Yes, detection of The combinations of components, materials, in spent fuel due to general, and one time aging effects is to and environments identified in NUREG-1801 pool cooling pitting, and crev-inspection be further evalu-are not applicable to VCSNS. There are no and cleanup ice corrosion ated carbon steel components with elastomer lin ings in the Spent Fuel Cooling System that are used to perform a license renewal intended function.

2 Linings in Hardening, crack-Plant specific Yes, pl,'

,cific The component/component type AMR results spent fuel ing and loss of for VCSNS are consistent with NUREG-1 801 pool cooling strength due to in material, environment, and partially consis and cleanup elastomer degra-tent in aging effects. The VCSNS plant spe system; seals dation; loss of cifir program for managing aging is and collars in material due to Inspections for Mechanical Components ventilation wear (Appendix B.2.11). This program inspects systems external surfaces. It is expected that the aging effects for these components/component types will be exhibited on external surfaces before being exhibited on internal surfaces, therefore an aging management program that fl12 L

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 2

detects and manages only aging effects of the (cont.)

external surfaces is sufficient. Also, loss of material due to wear is not considered an aging effect requiring management at VCSNS because mechanical components must per form their License Renewal intended functions without moving parts. Wear that occurs on non-moving components is considered to be caused by improper design and should be cor rected by normal maintenance activities.

Consistent with NUREG-1 801, this group includes elastomers in an air environment.

Consistent with NUREG-1 801, this group includes flexible collars between ducts and fans.

In addition to the Air Handling System, this group includes components/component types

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 2

from the Diesel Generator System, where (cont.)

these components/component types are simi lar and the above discussions apply.

3 Components Cumulative TLAA, evaluated Yes, TLAA The TLAA on fatigue is applicable to Class 2 in load han-fatigue damage in accordance with and 3 piping systems, which includes the dling, chemi-10 CFR 54.21(c)

Chemical and Volume Control System at cal and VCSNS. Refer to Section 4.3.2 of this appli volume con-cation for the discussion of fatigue of Class 2 trol system and 3 piping systems. The VCSNS fuel han (PWR), and dling cranes are adequately analyzed and reactor water designed for fatigue through the term of cleanup and extended operation. Refer to Section 4.7.3.3 shutdown of this application.

cooling sys tems (older BWR) 4 Heat Crack initiation Plant specific Yes, plant specific The component/component type AMR results exchangers and growth due to for VCSNS are consistent with NUREG-1801 "A n

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 4

in reactor SCC or cracking Plant specific Yes, plant specific in material, environment, and aging effects.

(cont.)

water The VCSNS plant specific program for man cleanup sys-aging aging is the Chemistry Program tern (BWR);

(Appendix B.1.4). Consistent with NUREG high pres-1801, the aging mechanism for this group is sure pumps stress corrosion cracking. In addition, crevice in chemical corrosion and pitting corrosion are also man and volume aged for this group at VCSNS.

control sys tem (PWR)

Non-Class 1 Closure bolting is considered to be a piece-part of the components/component types as a whole at VCSNS. Therefore a bolt ing integrity program is not credited for aging management. As a piece-part of subject com ponents/component types at VCSNS, the spe cific bolting/fastener materials were not itemized as a separate Non-Class 1 compo nent or component type. Additionally, for car bon and alloy steel components, the aging n a . r wE

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 4

management program credited for managing (cont.)

external general corrosion of the applicable components/component types (e.g. Inspec tions for Mechanical Components [Appendix B.2.11]) will also inherently address their fas teners, thus requiring no separate action.

Consistent with NUREG-1 801, this group includes stainless steel in a chemically treated borated water environment. Consistent with NUREG-1801, this group includes pump cas ings.

5 Components Loss of material Plant specific Yes, plant specific The component/component type AMR results in ventilation due to general, for VCSNS are consistent with NUREG-1801 systems, die-pitting, and crev-in material, environment, and partially consis sel fuel oil ice corrosion, and tent in aging effects. The VCSNS plant spe system, and MIC cific programs/activities for managing aging emergency are: Inspections for Mechanical Components diesel (Appendix B.2.11), Maintenance Rule 3U RiLIN Ij M R

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C LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 5

generator Structures Program (Appendix B.1.18), Boric (cont.)

systems; Acid Corrosion Surveillances (Appendix external sur-B.1.2), Preventive Maintenance Activities faces of car-Ventilation Systems Inspections (Appendix bon steel B.1.26), and Diesel Generator Inspections components (Appendix B.2.2). Consistent with NUREG 1801, the aging mechanisms for this group include general corrosion, pitting corrosion, and external MIC. In addition to these aging mechanisms, boric acid corrosion, galvanic corrosion, heat exchanger fouling due to par ticulates, and alternate wetting and drying are managed for this group at VCSNS. For sur faces in contact with air or gas, crevice corro sion is not considered to be an aging mechanism at VSCNS because contaminants are not of sufficient concentration in the air or gas environments to initiate the mechanism.

For carbon steel, thick-walled components

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 5

(>3/8 inch) in the dry air-gas environments of (cont.)

the diesel generator system, general corrosion is conservatively estimated to reduce wall thickness by only 39 mils over the 60 year life of the plant, therefore, this aging mechanism will not affect the ability of these components to perform their intended functions and no pro gram is needed to manage general corrosion of these components. At VCSNS, MIC is not considered to be an airborne contaminant, therefore, internal MIC in ventilation systems is not considered to be an aging mechanism.

Consistent with NUREG-1801, this group includes carbon steel, galvanized steel, and copper-nickel in air or gas environments. In addition to these materials, this group includes copper, iron, cast iron, and ductile iron at VCSNS.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 5

(cont.)

Consistent with NUREG-1 801, this group includes components in ventilation systems, diesel fuel oil systems, emergency diesel gen erator systems, and external surfaces of car bon steel components. In addition, this group includes components/component types from other systems where these components/com ponent types are similar and the above dis cussions apply. These systems are the Fire Service System and the Component Cooling System.

6 Components Loss of material One-time inspec-Yes, detection of Whereas NUREG-1801 concerns reactor in reactor due to galvanic, tion aging effects is to coolant pump oil collection system compo coolant pump general, pitting, be further evalu-nents/component types that are composed of oil collect and crevice corro-ated carbon steel, copper, and brass, the reactor system of fire sion coolant pump oil collection system compo protection nents/component types at VCSNS are com posed of stainless steel.

PAGE= 79 OF 252Z 3.0 - AGING MANAGE::MENT REVIEW

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 6

(cont.)

None of the components/component types of the reactor coolant pump oil collection will col lect water in low spots since all are subject to high ambient conditions which would cause evaporation of any moisture. This fact is sup ported by a review of the operating experi ence, which reveals no aging effects for these components/component types. Therefore, no aging effects were determined to require man agement during the period of extended opera tion.

7 Diesel fuel oil Loss of material Fuel oil chemistry Yes, detection of The component /component type AMR results tanks in die-due to general, and one-time aging effects is to for VCSNS are consistent with NUREG-1801 sel fuel oil pitting, and crev-inspection be further evalu-in material, environment, and partially consis system and ice corrosion, ated.

tent in aging effects and credited program/

emergency MIC, and biofoul-activity. The attributes of the credited program/

diesel gener-ing activity are not fully consistent with the corre ator system sponding program attributes as described in n

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 7

NUREG-1801 because NUREG-1801 recom (cont.)

mends augmentation of the Chemistry Pro gram with a One-Time Inspection. The Chemistry Program (Appendix B.1.4) has been in effect since initial plant startup and has proven effective in maintaining systems chemistry and detecting abnormal conditions.

A review of the operating experience confirms the effectiveness of the Chemistry Program (Appendix B.1.4) for fuel oil to manage aging effects when continued into the period of extended operation. A one-time inspection is, therefore, not warranted for these compo nents/component types in this group. Consis tent with NUREG-1801, the aging mechanisms for this group include general corrosion, pitting corrosion, crevice corrosion, and MIC. These aging mechanisms are caused by water pooling in tanks. Component/

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 7

component type AMR results for VCSNS show (cont.)

that water will not pool in the piping and other piping components, therefore, these aging mechanisms, with the exception of MIC, will not occur in these components. Only trace amounts of water are needed to promote MIC in fuel oil environments, so it is conservatively assumed to occur in piping and other piping components. In addition to these aging mech anisms, galvanic corrosion is managed for this group at VCSNS. These aging mechanisms will continue to be adequately managed through the period of extended operation. Bio fouling is considered to be an aging mecha nism for raw water environments only.

Operating experience does not support bio fouling in oil environments.

Consistent with NUREG-1 801, this group

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 7

contains carbon steel in a fuel oil environment.

(cont.)

In addition to this material, this group contains stainless steel and copper at VCSNS. Consis tent with NUREG-1 801, this group includes diesel fuel oil tanks in the diesel fuel oil system and emergency diesel generator system. In addition, this group includes piping and other piping components from these systems. This group also includes tanks and piping and other piping components from the Fire Service System where these components/component types are similar and the above discussions apply.

8 Heat Crack initiation Water chemistry Yes, plant specific The component /component type AMR results exchangers and growth due to and a plant-spe-for VCSNS are consistent with NUREG-1 801 in chemical SCC and cyclic cific verification in material and environment, and partially con and volume loading program sistent in aging effects and credited program/

control sys-activity. Consistent with NUREG-1 801, the tem aging mechanisms for this group include 3.0 AGING.MANAG.MENT.REVIEW I J I A

AmA PAGE 83 OF 252 3.0 - AGING MANAGEMENT REVIEW

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 8

stress corrosion cracking. In addition to this (cont.)

aging mechanism, crevice corrosion, pitting corrosion, and heat exchanger fouling due to particulates are managed for this group at VCSNS. Cracking due to cyclic loading is not an aging effect requiring management during the period of extended operation at VCSNS.

The Chemical and Volume Control System is operated continuously at steady state per design in a water-solid condition thereby pre cluding water hammer events; hence, there is no cyclic loading of the regenerative or let down heat exchangers. The VCSNS plant specific program for managing aging is the Chemistry Program (Appendix B.1.4) which has been in effect since initial plant startup and has proven effective in maintaining sys tems chemistry and detecting abnormal condi tions. A review of the operating experience

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 8

confirms its effectiveness in managing aging (cont.)

effects. A verification program is, therefore, not warranted for these components/compo nent types in this group.

Consistent with NUREG-1801, this group con tains stainless steel in borated water and treated water environments. Consistent with NUREG-1 801, this group contains the letdown and regenerative heat exchangers of the Chemical and Volume Control System.

9 Neutron Reduction of neu-Plant specific Yes, plant specific At VCSNS, the Boraflex neutron absorbing absorbing tron absorbing sheets will be replaced with Boral neutron sheets in capacity and loss absorbing sheets prior to the Refueling Out spent fuel of material due to age 14 (September 2003). Boral does not storage racks general corrosion degrade as a result of long-term exposure to (Boral, boron radiation, and Boral is stable, durable, and steel) corrosion resistant, therefore, there are no aging affects applicable to the Boral neutron l

!i 3.0 - AGING MANAGEMENT REVIEW PAGE 85 OF; 252

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 9

absorbing sheets in the spent fuel storage (cont.)

racks at VCSNS.

10 New fuel rack Loss of material Structures moni-No The New Fuel Rack Assembly at VCSNS assembly due to general, toring does not perform an intended function and is pitting, and crev-not within scope of license renewal.

ice corrosion 11 Spent fuel Crack initiation Water chemistry No The AMR results for the spent fuel storage storage racks and giowth due to racks at VCSNS are consistent with NUREG and valves in stress corrosion 1801 in material, environment, aging effects, spent fuel cracking and credited programs/activities. Consistent pool cooling with NUREG-1801, cracking due stress corro and cleanup sion cracking is managed by the Chemistry Program (Appendix B.1.4). In addition, loss of material due to crevice corrosion and pitting corrosion are also managed by the Chemistry Program. However, the combinations of com ponents, materials, and environments for car bon steel valves clad with stainless steel a i

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 11 identified in NUREG-1801 are not applicable (cont.)

to VCSNS. There are no carbon steel valves clad with stainless steel in the Spent Fuel Cooling System that are used to perform a license renewal intended function.

12 Neutron Reduction of neu-Boraflex monitor-No At VCSNS, the Boraflex neutron absorbing absorbing tron absorbing ing sheets will be replaced with Boral neutron sheets in capacity due to absorbing sheets prior to Refueling Outage 14 spent fuel Boraflex degrada-(September 2003), therefore, this item is not storage racks tion applicable to VCSNS.

13 Closure bolt-Loss of material Boric acid corro-No The component/component type AMR results ing and exter-due to boric acid sion for VCSNS are consistent with NUREG-1 801 nal surfaces corrosion in material, environment, aging effect, and of carbon credited program/activity.

steel and low alloy steel Consistent with NUREG-1 801, this group con components tains carbon and low alloy steel in an air J.U - ALINL MANAIJMN I KVIW EMUE 01 'Jr £S "PAWE o O!

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 13 environment. Also included in this group are (cont.)

aluminum, galvanized steel, brass, bronze, copper, and cast iron. Consistent with NUREG-1801, this group contains external surfaces of components. Boric Acid Corrosion Surveillances (Appendix B.1.2) will continue to manage boric acid corrosion of external sur faces through the period of extended opera tion. Loss of mechanical closure integrity is not considered to be an aging effect requiring evaluation for Non-Class 1 component bolted closures within the scope for license renewal at VCSNS. As such. the specific bolting/fas tener materials of subject components/compo nent types within the scope of license renewal were not itemized as a separate Non-Class 1 component/component type. Rather, bolting was treated as a "piece-part" (or sub-compo nent/sub-part) of Non-Class 1 components/

J.. U -/zAliINI MANIAUiMI-N I KI-VII-WV PAGE 88 OF 252

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 13 component types.

(cont.)

14 Components Loss of material Closed-cycle cool-No The component/component type AMR results in or serviced due to general, ing water system in this group for VCSNS are consistent with by closed-pitting, and crev-NUREG-1 801, in material, environment and cycle cooling ice corrosion, and aging effects (mechanisms) requiring man water system MIC agement, as clarified. However, the Chemistry Program (Appendix B.1.4) is considered to provide adequate management in lieu of the Closed-Cycle Cooling Water System program that is recommended for this group by NUREG-1801. The Chemistry Program has been in effect since initial plant startup and has proven effective in maintaining systems chemistry and detecting abnormal conditions.

A review of the operating experience confirms the effectiveness of this program to manage the conditions that could result in degradation during the period of extended operation.

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 14 Consistent with Generic Letter 89-13, Service (cont.)

Water Problems Affecting Safety-Related Equipment evaluations, activities in addition to the existing chemistry controls are not war ranted.

Consistent with NUREG-1 801, the compo nent/component type AMR results in this group for VCSNS include components/compo nent types in or serviced by closed-cycle cool ing water systems. In addition, this group includes components/component types from systems that are not part of or not directly ser viced by closed-cycle cooling water where the components/component types are similar and the same discussions apply. As such, the group includes components/component types from the Nuclear Sampling System, Radiation Monitoring System, Gaseous Waste 3.U

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 14 Processing System, and Reactor Coolant Sys (cont.)

tem (Non-Class 1 RCP thermal barrier flange and piping/tubing that are connected to the Component Cooling system).

Consistent with NUREG-1801, this group includes carbon steel and stainless steel exposed to treated (non-borated) water at VCSNS, although NUREG-1 801 indicates that heat exchanger components in this group are carbon steel, some stainless steel is in the heat exchangers in this group at VCSNS.

Consistent with NUREG-1 801, the aging effects (mechanisms) requiring management for this group include loss of material due to general (carbon steel only), crevice, and pit ting corrosion. In addition to the NUREG-1 801 aging effects, the following aging effects 3.0 - AGING MANAGIEMENT REVIEW PAGE 91 OF* 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 14 (mechanisms) require management for appli (cont.)

cable components/component types within this group at VCSNS:

a Cracking due to stress corrosion cracking (SCC) of stainless steel in locations that conservatively have the potential to experi ence temperatures above 140°F during normal operation, Cracking due to stress corrosion cracking (SCC) of carbon steel due to the presence of nitrite based corrosion inhibitors in the Chilled Water and Diesel Generator Cool ing Water Systems, Loss of material due to galvanic corrosion of carbon steel in contact with a more cathodic material, and 0 Heat exchanger tube fouling due to partic ulates in systems taking suction from the

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 14 bottom of a tank or reservoir.

(cont.)

15 Cranes Loss of material Overhead heavy No The VCSNS Aging Management Programs for including due to general load and light load this group are consistent with those reviewed bridge and corrosion and handling systems and approved in NUREG-1801. The Material trolleys and wear Handling System Inspection Program rail system in (Appendix B.1.19) is credited with managing load han-loss of material for the steel rails and girders dling system within the scope of license renewal, while the Maintenance Rule Structures Program (Appendix B.1.18) is responsible for manag ing the attributes associated with the aging of structures and structural components. These aging effects include loss of material due to corrosion, cracking and change in material properties, and they are detected by visual inspection of external surfaces.

Wear is the result of movement of a material in

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PAGE 93 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 15 relation to another material in contact with the (cont.)

first. Wear can occur during the performance of active functions. According to the License Renewal Rule [10 CFR 54.21 (a)(1)(i)], struc tures and components subject to an aging management review must perform their intended functions without moving parts or without a change in configuration or proper ties. As such, loss of material due to wear is not an aging effect requiring further evaluation for license renewal, and is only considered a consequence of frequent or rough usage.

16 Components Loss of material Open-cycle cool-No The component/component type AMR results in or serviced due to general, ing water system for VCSNS are consistent with this NUREG byopen-cycle pitting, crevice, 1801 group in material and environment and cooling water and galvanic cor-are partially consistent with respect to aging systems rosion, MIC, and effects and credited aging management pro biofouling; buildup gram, as clarified below.

of deposit due to

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 16 biofouling Consistent with NUREG-1801, this group (cont.)

includes brass (not aluminum brass), copper, carbon steel and stainless steel at VCSNS.

Brass and copper components/component types are also addressed later in this table for selective leaching of open and/or closed cycle cooling system components.

Consistent with NUREG-1801, this group includes various components/component types in systems, or components serviced by, an open-cycle cooling water system, the Ser vice Water System at VCSNS.

Consistent with NUREG-1801, copper, brass and stainless steel components/component types within this group at VCSNS are not sus ceptible to a loss of material due to general corrosion and no management of that effect is J.U - RLIII

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 16 required for those components/component (cont.)

types.

In addition to the aging effects specified in NUREG-1801, for this group, the credited aging management program at VCSNS also manages particulate fouling and loss of mate rial due to erosion of susceptible components/

component types. Furthermore, biofouling as is referenced in NUREG-1801, has been labeled as fouling due to biological materials at VCSNS. NUREG-1 801 specifies an Open Cycle Cooling Water System program. The VCSNS component/component type AMR results, for this group, credit the corresponding Service Water System Reliability and Inser vice Testing program (Appendix B.1.9) to manage the specified aging effects during the period of extended operation.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 17 Buried piping Loss of material Buried piping and No The component/component type AMR results, and fittings due to general, tanks surveillance in this group, for VCSNS are consistent with pitting, and crev-NUREG-1 801 in material, environment, aging ice corrosion, and or effects (mechanisms) requiring management MIC and credited aging management program, as Buried piping and Yes, detection of clarified below.

tanks inspection aging effects and operating experi-Consistent with NUREG-1801, the compo ence are to be fur-nent/component type AMR results for VCSNS ther evaluated include carbon steel materials that are under ground and wrapped/coated. In addition to the NUREG-1 801 materials, this group includes cast iron and ductile iron (cement-lined inter nally) at VCSNS.

In addition to the piping and fittings compo nents/component types, this group includes tanks, and hydrants (including internal valve) at VCSNS. Also, in addition to the

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PAGE 97 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 17 NUREG-1 801 aging effects (mechanisms)

(cont.)

requiring management for this group, certain components/component types in this group at VCSNS are also susceptible to a loss of mate rial due to galvanic corrosion.

Consistent with NUREG-1 801 options for this group, the Buried Piping and Tanks Inspection (Appendix B.2.10) activity is credited with the management of aging for susceptible compo nents/component types.

18 Components Loss of material Compressed air No No components/component types, that are in com-due to general monitoring subject to AMR, in compressed air systems at pressed air and pitting corro-VCSNS were matched to NUREG-1801 items system sion for this group since, by design, the com pressed air systems at VCSNS are dry and oil-free. As such, a Compressed Air Monitor ing program is not credited for aging manage ment at VCSNS.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 19 Components Loss of material Fire protection No The VCSNS Aging Management Programs for (doors and due to wear; hard-this group are generally consistent with those barrier pene-ening and shrink-reviewed and approved in NUREG-1801. The tration seals) age due to VCSNS Fire Protection Program (Appendix and concrete weathering B.1.5) contains many activities to achieve structures in defense-in-depth and minimize the impact of a fire protection potential fire.

The Fire Barrier and Fire Barrier Seal Inspec tions detect structural damage or degradation of fire barriers and fire barrier penetration sealing devices. Fire barriers include walls, ceilings and floors. The corresponding aging effects are cracking, separation from walls or components, separation of material layers, rupture or puncture of seals, shrinkage and voids.

The Fire Door Inspections detect structural

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 19 damage or degradation of fire rated doors.

(cont.)

Inspections are credited with managing loss of material of doors and door hardware for the period of extended operation. Excessive wear for door appurtenances such as latches, strike plates, hinges, sills and closing devices, and maintaining proper clearances (gaps) between the door, frame and threshold are also inspected, but these attributes are not credited for license renewal. Loss of material due to wear of the door hardware and hinges is not considered an aging effect but rather a conse quence of frequent or rough usage.

20 Components Loss of material Fire water system No The component/component type AMR results in water-due to general, in this group for VCSNS are consistent with based fire pitting, crevice, NUREG-1 801 in material and environment, protection and galvanic cor-and are partially consistent in aging effects rosion, MIC, and (mechanisms) and credited aging manage biofouling ment program, as clarified below.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 20 (cont.)

Consistent with NUREG-1801, the compo nent/component type AMR results for VCSNS include carbon steel, cast iron, bronze, and stainless steel. In addition to the NUREG 1801 materials, this group includes black steel, galvanized steel (conservatively consid ered similar to carbon/low alloy steel) and brass at VCSNS.

Consistent with NUREG-1 801, the aging effects (mechanisms) requiring management for this group includes loss of material due to general corrosion (carbon steel and cast iron only), crevice and/or pitting corrosion, galvanic corrosion, and microbilogically influenced cor rosion (MIC).

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 20 this group, is referred to as "fouling due to bio (cont.)

logical materials" at VCSNS. In addition to the NUREG-1801 aging effects/mechanisms for this group, "fouling due to particulates" is man aged by the credited aging management pro gram at VCSNS.

While not specified in NUREG-1801 for Fire Protection components in particular, certain components/component types in this group at VCSNS were also determined to be suscepti ble to a loss of material due to selective leach ing based on their materials of construction (cast iron or brass) and environment. This aging effect/mechanism is also managed by the credited aging management program at VCSNS.

The mechanical portion of the existing Fire A

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 20 Protection Program (Appendix B.1.5) at (cont.)

VCSNS, referred to in this application as "Fire Protection Program - Mechanical", is credited for management of pertinent aging effects.

21 Components Loss of material Fire protection and No Component/component type AMR results for in diesel fire due to galvanic, fuel oil chemistry the diesel fuel oil portion of the Fire Service system general, pitting, system (that is tank and fuel supply line to the and crevice corro-diesel driven fire pump) is included with the sion other diesel fuel oil supply portions in a sepa rate portion of this table based on material, environment, aging effects (mechanisms) requiring management and credited aging management program similarities. As such, the NUREG-1801 items within this group are not considered applicable to VCSNS. Further more, the inclusion of fire service fuel oil sup ply with other fuel oil supply portions is conservative with respect to aging effects requiring management.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 21 (cont.)

The pump casing of the diesel fire pump at VCSNS is not exposed to the fuel oil provided to the diesel engine, but to the fire service water. As such, the component/component type AMR results for VCSNS that include the casing of the diesel driven fire pump are included in the appropriate portion of this table.

22 Tanks in die-Loss or material Above ground car-No The component AMR results for the external sel fuel oil due to general, bon steel tanks surface of the Fire Service system Diesel Fuel system pitting, and crev-Oil Tank are consistent with this NUREG-1 801 ice corrosion group with respect to material and environ ment and partially with respect to aging effect requiring management, as clarified below.

However, an management program that includes a thickness measurement of the tank bottom surface is not required and an activity corresponding to the NUREG-1801 "Above 3.U - AUINU MANAUMN I KVIW PAGE 104 OF 252 J.U - AUING MANAGE-ME:NT REVIEW PAGE 104 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 22 Ground Tank Inspection" is not credited.

(cont.)

Due to environment differences (i.e. location underground or indoors), the component AMR results for other subject diesel fuel tanks are included in the appropriate portion of this table. Likewise, the internal surfaces of all these tanks are included in the appropriate portion of this table.

Consistent with NUREG-1 801, the carbon steel Fire Service system Diesel Fuel Oil Tank is susceptible to loss of material due to gen eral corrosion. In addition to the NUREG-1 801 aging effects requiring management, the Fire Service system Diesel Fuel Oil Tank is sus ceptible to a loss of material due to galvanic corrosion from a connection to a more cathodic material. However, the ambient 3.U - RI.II'4.i M.Mt'E I rvivv iu yr 

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICFNRE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 22 external conditions at VCSNS do not contain (cont.)

sufficient contaminants that could concentrate at wetted locations to cause localized crevice or pitting corrosion. Additionally, the VCSNS Fire Service system Diesel Fuel Oil Tank is mounted on stilts making all external surfaces accessible for inspection and the plant-spe cific Inspections for Mechanical Components (Appendix B.2.11) is credited with manage ment of the specified aging effects.

23 Closure bolt-Loss of material Bolting integrity No Non-Class 1 Closure bolting is considered to ing due to general be a piece-part of the components/component corrosion; crack types as a whole at VCSNS. Therefore a bolt initiation and ing integrity program is not credited for aging growth due to management. As a piece-part of subject com cyclic loading and ponents/component types at VCSNS, the spe SCC cific bolting/fastener materials were not itemized as a separate Non-Class 1 compo nent or component type. Additionally, for aa a

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 23 carbon and alloy steel components, the aging (cont.)

management program credited for managing external general corrosion of the applicable components/component types (e.g. Inspec tions for Mechanical Components [Appendix B.2.11]) will also inherently address their fas teners, thus requiring no separate action.

24 Components Loss of material Selective leaching No No component/component type AMR results (aluminum due to selective of materials at VCSNS are consistent with a NUREG-1 801

bronze, leaching item within this group. As such, a selective brass, cast leaching of materials inspection activity is not iron, cast credited for aging management.

steel) in open-cycle The component/component type AMR results and closed-for components in or directly serviced by the cycle cooling Service Water system (open-cycle cooling/ulti water sys-mate heat sink), addressed previously in this tems, and table, indicate that selective leaching is not an ultimate heat aging effect to which they are susceptible due 3.0 - AINU MANAUMN I KVIVV rMi.

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3.0 - AGING MANAGiEMENT REIIVIE"W PAGEII¢ 107 UOF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 24 sink to the actual material of construction (e.g. no (cont.)

alloying copper, inhibiting elements, etc.). Fur thermore, although a NUREG-1801 item in this group indicates that cast steel pump cas ings in closed-cycle cooling systems are sus ceptible to selective leaching, available technical documentation and operating experi ence, as well as corresponding NUREG-1801 aging management program description, sup ports that cast steel actually refers to cast iron.

VCSNS component/component type AMR results which were determined to have a sus ceptibility to selective leaching are addressed elsewhere in this table (brass, copper and cast iron Fire Service components/component types) and in Table 3.3-2 Item 28 of this appli cation section (closed-cycle cooling compo nents).

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Management Evaluation Discussion Item Group Mechanism Program Recommended 25 Fire barriers, Concrete crack-Fire protection and No The VCSNS Aging Management Programs for walls, ceil-ing and spalling structures moni-this group are generally consistent with those ings, and due to freeze-toring reviewed and approved in NUREG-1801. The floors in fire thaw, aggressive VCSNS Fire Protection Program (Appendix protection chemical attack, B.1.5) contains many activities to achieve and reaction with defense-in-depth and minimize the impact of a aggregates; loss potential fire.

of material due to corrosion of The Fire Barrier Inspections detect structural embedded steel damage or degradation of fire barriers. Fire barriers include walls, ceilings and floors. The corresponding aging effects are cracking (excluding hairline cracks), spalling and loss of material.

The Maintenance Rule Structures Program (Appendix B.1.18) is responsible for manag ing the attributes associated with the aging of structures and structural components, 3.0 - AGING MANAGEMENT REVIEW l"AGEl

-10 OF U2"52

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 25 including those in this grouping. These aging (cont.)

effects include loss of material due to corro sion, cracking and change in material proper ties, and are detected by visual inspection of external surfaces.

Section 3.5 of the Application provides the primary discussions concerning structural monitoring.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 3.3.3.3 Aging Management Evaluations That Are Different From Or Not Addressed In NUREG-1801 Aging Management Evaluations that are different from or not addressed in NUREG-1 801 are identified and discussed in Table 3.3-2. The standard six-column format has been uti lized. The discussion column provides additional details regarding the aging management conclusions reached by VCSNS for the component type.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I ProgramActivity Discussion Item Type Mechanism 1

Piping, tub-Stainless Steel Air-Gas (moist None Identified None Required This grouping includes the ing, valves air) external surface of stain (body/bonnet less steel subject compo only), heat nents/component types that exchangers are exposed to ambient and associ-conditions. These ambient ated compo-conditions include the heat, nents cold, humidity and various forms of precipitation out doors as well as the lesser heat, cold and humidity indoors (inside the Reactor Building and other in-scope plant buildings). Addition ally, this grouping includes the internal surfaces of sub ject components/compo nent types that are either open to the ambient condi tions in the building/room in

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PAGE 112 OF 252

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Program/Activity Discussion Item Type Mechanism 1

which they are located or (cont.)

have been closed off from the process stream at ambi ent conditions.

However, the ambient con ditions in the indoor or out door environments at VCSNS do not contain con taminants in sufficient quantities to concentrate in wetted locations and cause corrosion/degradation of stainless steel.

2 Ductwork and Stainless Steel Air-Gas (moist None Identified None Required This grouping includes the HVAC pres-air) internal and external sur sure bound-faces of stainless steel ven ary tilation system (Air components Handling and Local Ventila (including tion & Cooling)

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect/

Program/Activity Discussion Item Type Mechanism 2

housings, components/component (cont.)

pipe, tubing types that are exposed to and valves moist air (both ambient (body/bonnet externally and conditioned only) internally). Stainless steel is not susceptible to corro sion/degradation in the absence of sufficient con taminant quantities, which are not found in the ambi ent building environments or outside environments at VCSNS.

3 Ductworkand Galvanized Air-Gas (moist None Identified None Required This grouping includes the HVAC pres-Steel, Carbon air) internal surface of carbon sure bound-Steel and galvanized steel venti ary lation system (Air Handling components and Local Ventilation &

(including Cooling) components/com

housings, ponent types that are 3.U - AijiNli MANAUMI'1 I ICVIVY PAGE 114 OF 252 4.0 - AGING MANAGEI:ME=NT RE*VIE:W PAGE 114 OF 252 i,

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Program/Activity Discussion Item Type Mechanism 3

valves (body/

exposed to moist air as well (cont.)

bonnet only) as the external surface of the exhaust air relief heads that are exposed to the heat, cold, humidity, and various forms of precipita tion outdoors. Otherwise, the external surfaces of subject components/com ponent types in this group ing are addressed in Table 3.3-1 Item 5.

While the AMR results for subject components/com ponent types in this group ing at VCSNS are consistent with NUREG 1801 with respect to mate rial and environment, no 3.U - RbINb MRV4RIJIVII

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Item Type Mechanism Program/Activity Discussion 3

aging effects were deter (cont.)

mined to require manage ment at VCSNS. This determination was made due to the lack of sufficient contaminants in the moist air environment to promote crevice, pitting, or microbio logically influenced corro sion in wetted locations, the resistance of galvanized steel to general corrosion in (non-wetted) air, and to the subject carbon steel com ponents/component types being considered thick walled such that any mois ture related general corro sion will not result in loss of function during the period of extended operation.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Program/Activity Discussion Item Type Mechanism 4

Components/

Black Steel, Air-Gas (dry)

None Identified None Required The material/environment component Brass, Bronze, combination for this group types in com-Carbon Steel, ing is not addressed for any pressed gas Cast Iron, Cop-item in GALL Chapters IV, service (CO 2 per, Stainless V, VII or VIII. Also, no aging fire service Steel effects were determined to extinguishing require management during and HVAC the period of extended Chillers operation. This grouping refrigerant includes the internal sur addition/

faces of subject compo purge) nents/component types in the Fire Service System (carbon dioxide extinguish ing portion) and Chilled Water System (refrigerant addition and purge portion).

At VCSNS, the process environment inside these portions is by design a dry A a

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SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect/

Program/Activity Discussion Item Type Mechanism 4

gas, free of moisture or (cont.)

contaminants, which could cause corrosion/degrada tion.

5 Pumps, pip-Brass, Carbon Oil None Identified None Required This grouping includes oil ing, valves Steel, Cast Iron, coated surfaces of subject (body/bonnet Copper, Copper-components/component only), and Nickel, Ductile types exposed to lubricat associated Iron, Stainless ing oil that are not subject lubrication Steel to wetting.

components (not includ ing RCP Oil Collection) 6 Pumps, Pipe, Stainless Steel Treated Water Loss of Material Chemistry Pro-This grouping includes sub Tube, Fit-(specifically due to Crevice gram ject component/component tings, Valves chemically Corrosion, Pitting types in systems (Boron (Body/Bon-treated borated Corrosion; Crack-Recycle, Nuclear Sampling, net only) and water) ing due to Stress Radiation Monitoring, Spent

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Program/Activity Discussion Item Type Mechanism 6

associated Corrosion Crack-Fuel Cooling, Thermal (cont.)

components ing (SCC)

Regeneration) whose pro cess environment is borated water and that are either not closed-cycle cooling water systems as described in NUREG-1801, or if directly serviced by a closed-cycle cooling water system are the surface exposed to the medium being cooled.

This grouping is consistent with NUREG-1801 Engi-.

neered Safety Feature items with respect to mate rial, environment, aging effect requiring manage ment, and credited program 3.U - RI.III.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Program/Activity Discussion Item Type Mechanism 6

(with the conservative addi (cont.)

tion of loss of material due to crevice and pitting corro sion).

Only subject components/

component types in this grouping with process fluid temperatures above 140OF are susceptible to cracking due to SCC. As in NUREG 1801 for Engineered Safety Feature items, the Chemis try Program (Appendix B.1.4) is credited to man age the conditions that could result in the specified aging effects/mechanisms during the period of extended operation.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Program/Activity Discussion Item Type Mechanism 7

Nuclear Sam-Nickel-Based Treated Water Loss of Material Chemistry Pro-The components in this pling system Alloy (Alloy 600)

(including due to Crevice gram grouping at VCSNS are sample cool-Borated Water, Corrosion, Pitting consistent with a NUREG ing tubes secondary side Corrosion; Crack-1801 Reactor Coolant item blowdown, Coin-ing due to Stress (Table 3.1-1 Item 15) with ponent Cooling Corrosion Crack-respect to material and Water) ing (SCC); and environment and partially Heat Exchanger for aging effect requiring Fouling due to management. However, Particulates this material is not (Component addressed in NUREG Cooling water 1801, except for Reactor only)

Coolant, and VCSNS eval uations have determined that the tubes in this group ing are not susceptible to primary water stress corro sion cracking (PWSCC) that is normally considered in a high temperature PAGE 121 OF 252 3.0 - AGING MANAGEMENT REVIEW

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Item Type Mechanism ProgramlActivity Discussion 7

borated water environment.

(cont.)

The existing Chemistry Pro gram (Appendix B.1.4) is credited for managing the conditions that could result in the specified aging mechanisms during the period of extended opera tion and provides reason able assurance that the component intended func tions will be maintained for all CLB conditions.

8 Pipe and Fit-Stainless Steel, Embedded in None Identified None Required This grouping includes the tings Carbon Steel Concrete external surface of subject components/component types (Spent Fuel Cooling, Nuclear Plant Drains, and Service Water systems) 3.0 - AGING MANAGEMENT REVIEW PAGE 122 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Program/Activity Discussion Item Type Mechanism 8

that are embedded in con (cont.)

crete. The concrete forms a tight seal that pre vents exposure of the sub ject piping to aggressive chemical species that could cause corrosion.

9

Ductwork, Stainless Steel Air-Gas (moist Loss of Material Maintenance Rule At VCSNS, piping or tubing Piping, Fit-air)

Microbiologically Structures Pro-component types which tings and/or Influenced Corro-gram enter buildings or pass Tubing which sion (MIC) {Exter-between buildings that do enters or nal Surface}

not share a common wall passes below the 425' elevation between are conservatively suscepti buildings ble to the accumulation of below the external sulfate-reducing 425' Eleva-bacteria resulting from tion groundwater intrusion. With the exception of those com ponents types which pass 1.U - AWIINI" MAPiA cm" I r~-vlw-vv A

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SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I ProgramActivity Discussion Item Type Mechanism 9

through a "fire seal" pene (cont.)

tration, that are not suscep tible to groundwater intrusion, these compo nents may see a build-up of sulfate reducing bacteria at the wall/component inter face and thereby be sus ceptible to localized external MIC. The Mainte nance Rule Structures Pro gram (Appendix B.1.18) will manage a loss of mate rial due to external MIC for susceptible locations during the period of extended operation.

10 Piping, muf-Carbon Steel, Air-Gas (prima-None Identified None Required This grouping includes the fler, expan-Stainless Steel rily moist air plus exhaust piping, mufflers sion joints in periodic and expansion joints A

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Program/Activity Discussion Item Type Mechanism 10 Diesel engine exhaust gases) associated with the Diesel (cont.)

exhausts Driven Fire Service Pump (Fire Service and Emergency Diesel (FS) and Die-Generators. While this sel Genera-grouping is consistent with tor Services a NUREG-1801 item with (DG) sys-respect to material and tems) environment. However, due to these thick-walled com ponents not being continu ously exposed to hot exhaust gases, any general corrosion would be insuffi cient to cause loss of com ponent intended function during the period of extended operation.

Thin-walled carbon steel portions of these exhaust 3.0 - AGING MANAI3MNT REVIEW rALI 1L U1

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3.0 - AGING MANAGEMENT REVIEW P"AUL1 1zo) UI" 0Z{

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I ProgramActivity Discussion Item Type Mechanism 10 trains are addressed in (cont.)

Table 3.3-1 Item 5.

11 Piping, tub-Carbon Steel, Air-Gas None Identified None Required This grouping includes vari ing, valves Stainless Steel ous materials in the intake/

(body/bonnet starting air (Diesel Genera only) and tor Services System), con associated trol air (Service Air components System), and gaseous waste/effluent (Liquid and Gaseous Waste Processing Systems) that are normally exposed to an air or gas environment where mois ture is not controlled through design. However, at VCSNS, these compo nents/component types are stainless steel and not sus ceptible to strictly moisture related degradation or are

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Program/Activity Discussion Item Type Mechanism 11 thick-walled carbon steel (cont.)

and not prone to a loss of function from strictly mois ture related degradation since a protective coating is formed, slowing the corro sion rate, and the allow able minimum wall thickness would not be exceeded during the period of extended operation.

12 Piping, tub-

Aluminum, Air-Gas None Identified None Required This grouping includes vari ing, valves Brass, Copper ous materials in the intake/

(body/bonnet starting air of the Diesel only) and Generator Services Sys associated tem that are normally components exposed to a moist air envi ronment. However, mois ture alone is insufficient to cause the degradation of A iAINIA I

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Item Type Mechanism ProgramIActivity Discussion 12 the materials within this (cont.)

grouping. Furthermore, the components/component types are in locations that are not susceptible to the wetting required for degra dation.

13 Instrument

Aluminum, Air-Gas None Identified None Required This grouping includes vari Air system Brass, Carbon ous materials in the Instru piping, tub-Steel, Cast Iron, ment Air System (IA) that ing and Stainless Steel are normally exposed to valves compressed air that is, by design, dry, oil-free, and fil tered. As such, no aging effects require manage ment for the subject compo nents/component types in this grouping during the period of extended opera tion since the design 3 0 - AGING* UAPJA9A:MI:=MT DI:W..

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(i LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect I Program/Activity Discussion Item Type Mechanism 13 precludes moisture collec (cont.)

tion in these components/

component types. The AMR results for component types in this system, as well as other compressed con trol air systems where moisture related aging is a concern during the period of extended operation are addressed separately below.

14 Piping, Tub-Carbon Steel Air-Gas (com-Loss of Material Service Air Sys-This grouping includes sub ing and pressed air w/

due to General tem Inspection ject component types in Valves (body/

moisture)

Corrosion or Gal-compressed air systems bonnet only) vanic Corrosion (Service Air, Instrument Air, (components in Building Services Sys contact with more tems) where moisture is not cathodic material) controlled through system design. The Service Air J.U - AiINL MANAUMN I KVIW riu

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3.0 - AGING MANAULI:MI:N I KI:=Vlr=W PAGE.U "I29 UO" 25

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.3-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE AUXILIARY SYSTEMS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect/

Program/Activity Discussion Item Type Mechanism 14 System Inspection (Appen (cont.)

dix B.2.6) will manage loss of material due to general corrosion (oxygen and moisture) or galvanic corro sion for component types in this grouping. This pro gram is a one-time inspec tion and will provide reasonable assurance dur ing the period of extended operation that the compo nent intended function(s) will be maintained under all CLB conditions 15 Gaseous Stainless Steel Air-Gas, Treated Loss of Material Waste Gas Sys-While somewhat consis Waste Pro-Water due to Crevice tem Inspections tent with NUREG-1801 with cessing sys-and Pitting Corro-respect to material, envi tem helical sion; Cracking ronment and aging effect(s)

coils, due to Stress requiring management, this nA A#%-IE1 U

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