ML022280129

Application for Renewed Operating License, Table 3.3-2: Summary of Aging Management Evaluations for Auxiliary Systems, Pages 131 - 252

ML022280129
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-1801, RC-02-0123
Download: ML022280129 (122)

Text

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 15 manifolds, Corrosion Crack-grouping includes compo pipe and ing (SCC) nents/component types that valves (body/

are subject to collection of bonnet only) water (moisture) in an envi ronment that is not con trolled by the Chemistry Program (Appendix B.1.4).

As such the one-time Waste Gas System Inspec tion (Appendix B.2.8) is credited for the manage ment of the identified aging effects during the period of extended operation.

16 Fire Service Cement-lined Raw Water None Identified None Required This grouping includes Fire system piping ductile iron Service Main Header piping that is exposed to raw water and is normally stag nant awaiting system actu ation. While cement is PAGE 131 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 ProgramlActivity Discussion Item Type Mechanism 16 addressed for Civil/Struc (cont.)

tural components in NUREG-1801, the use of cement lined pipe in the Fire Service System pre cludes the degradation of that piping as the cement provides a protective layer for the piping and is not

• ceptible to the extrem,..

conditions (temperature, aggressive chemicals, etc.)

which may cause degrada tion of cement.

17 Pumps, Pip-Stainless Steel Treated Water Loss of Material Chemistry Pro-This grouping includes sub ing, Tubing, (including due to Crevice gram ject components/compo

Fittings, makeup water, and Pitting Corro-nent types of auxiliary Valves (body/

secondary side sion; Cracking systems that are not closed bonnet only) blowdown, cool-due to Stress Cor-cycle cooling systems ing water) rosion (Nuclear Sampling, Reactor S

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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 17 Cracking (SCC)

Makeup Water) but whose (cont.)

process fluid is treated water. This grouping is con sistent with NUREG-1801 Engineered Safety Fea tures items with respect to material, environment, aging effect requiring man agement and credited pro gram, with the conservative addition of crevice and pit ting corrosion. As in NUREG-1 801 for the asso ciated Engineered Safety Features items, the Chem istry Program (Appendix B.1.4) manages the condi tions that could lead to the specified aging effects/

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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 Item Type Mechanism Program/Activity Discussion 17 period of extended opera (cont.)

tion.

18 Fire Service Galvanized Air-Gas (air)

None Identified None Required This grouping includes fire system noz-Steel, Carbon service system portions zles, piping Steel, Cast Iron (those not constructed of and fire stainless steel) that are nor hydrants mally in a drained down condition awaiting system actuation and therefore nor mally exposed to ambient conditions rather than raw water.

While the air is not strictly dry, the moisture content is expected to be very low.

Additionally, the compo nents are thick-walled such that the minimal resulting corrosion, if "I n - A t.IMEM U AM AfI UMCT.E Dl

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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 18 any, would result in loss of (cont.)

component function during the period of extended operation.

19 Tanks (includ-Carbon Steel Air-Gas (moist Loss of Material Chemistry Pro-The components in the ing Compo-air), Treated due to Crevice, gram, Above grouping are partially con nent Cooling Water Pitting, General, Ground Tank sistent with a NUREG-1 801 Water Surge Galvanic Corro-Inspection Closed Cycle Cooling Tank, Chilled sion and due to Water item with respect to Water Expan-the Corrosive material, environment, and sion Tanks)

Impacts of Alter-aging effect requiring man nate Wetting and agement. However, addi Drying tional aging effects require management at VCSNS for this Auxiliary grouping.

NUREG-1801 does not address the corrosive impacts of alternate wet ting and drying of vented tanks (or tanks without a i.U - AUIN MRI'NANAUMIMMIN" I t¶-VI'VW S ^

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

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 19 cover gas) that could con (cont.)

centrate contaminants above bulk fluid concentra tions and result in further degradation.

The Chemistry Program (Appendix B.1.4) will man age the conditions required for a loss of material of the components in this group ing to occur in bulk fluid (treated water) concentra tions. In addition, the one time Above Ground Tank Inspection (Appendix B.2.1) will manage a loss of material due to the corro sive impacts of alternate wetting and drying as well

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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 19 as general or galvanic cor (cont.)

rosion in the tank and attached components above the normal water level.

20 Tanks (includ-Stainless Steel Air-Gas (moist Loss of Material Chemistry Pro-The components in the ing Reactor air), Treated due to Crevice or gram, Above grouping are partially con Makeup Water Pitting Corrosion; Ground Tank sistent with a NUREG-1801 Water Stor-Cracking due to Inspection Engineered Safety Feature age Tank, Stress Corrosion item with respect to mate Nuclear Sam-Cracking (SCC);

rial, environment, aging pling Flush Corrosive Impacts effect requiring manage Water Stor-of Alternate Wet-ment and aging manage age Tank) ting and Drying ment program (Chemistry Program [Appendix B.1.4]). However, additional aging effects require man agement at VCSNS for this Auxiliary grouping.

NUREG-1801 does not MAfIC 4'17 nC'2

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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 Item Type Mechanism Program/Activity Discussion 20 address the corrosive (cont.)

impacts of alternate wet ting and drying of vented tanks (or tanks without a cover gas) that could con centrate contaminants above bulk fluid concentra 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 a a 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 /

Program/Activity Discussion Item Type Mechanism 20 (Appendix B.2.1) will man (cont.)

age the corrosive impacts of alternate wetting and dry ing to occur in stainless steel in the treated water environment.

21

Piping, Stainless Steel Liquid Waste/

Loss of Material Liquid Waste Sys-This grouping includes sub Valves (body/

Drain Water due to Crevice tem Inspection ject component types in bonnet only),

(including and Pitting Corro-systems (Liquid Waste Pro Heat borated, treated sion and/or Crack-cessing, Nuclear Plant Exchanger water) ing due to Stress Drains) that contain/trans tubes Corrosion Crack-port liquid waste or drain ing (SCC) water that has the potential for contamination. This grouping is consistent with a NUREG-1801 Engi neered Safety Feature item with respect to material, environment, and aging effect requiring 3.0 - AGING MANAGEMENT REVIEW I"AuriI 1,JI UI" Loll

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 Component Material Environment Aging Effect /

Item Type Mechanism Program/Activity Discussion 21 management with the addi (cont.)

tion of loss of material due to crevice and pitting corro sion. However, the one time Liquid Waste System Inspection (Appendix B.2.3) will provide reason able assurance that the component intended func tion(s) will be maintained under CLB conditions dur ing the period of extended operation.

22 Drain Pan Stainless Steel Treated Water Loss of Material Reactor Building This grouping includes the and Drain (condensate due to Crevice Cooling Unit loop seal drain lines on the Piping quality water with and Pitting Corro-Inspection Reactor Building Cooling traces of boric sion Units (RBCUs), Roof Drain acid)

System, and is consistent with an Engineered Safety Feature NUREG-1801 item 12 n AF-1&1J-U, Ai, iilrl PAGt14 OF25 O.V" /UllU llP%"I*%I-IIIr-I MrlV~rV PAGE 140 OF 252

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 22 with respect to material and (cont.)

environment. However, due to temperatures well below 1400 F, the drain lines are not susceptible to cracking due to SCC but are suscep tible to a loss of material due to crevice or pitting cor rosion. The one-time Reac tor Building Cooling Units Inspection (Appendix B.2.5) will provide reason able assurance that the component function of these drains will be main tained during the period of extended operation.

23 Sight glass Glass Air-Gas (includ-None Identified None Required This grouping includes the (body only) ing moist air, external and internal sur starting air), Oil faces of sight glasses and 3.0 - AGING MANAGEMENT REVIEW IPAGEI 14-1 UO" 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 I Program/Activity Discussion Item Type Mechanism 23 glass portions of pressure (cont.)

retaining instruments that is inert and not susceptible to age related degradation.

24 Motor Bear-Aluminum Air-Gas (moist Heat Exchanger Preventive Main-This grouping includes the ing Cooler air)

Fouling due to tenance Activities fins of the fin/t! 'be type Fins Particulates

- Ventilation Sys-Component Cooling Water tems Inspection Pump motor integral cool ers. Particulate fouling of the air side can occur from the accumulation and build up of dust, dirt or debris on and between the fins of air coolers. The Preventive Maintenance Activities Ventilation Systems Inspec tions (Appendix B.1.26) will manage heat exchanger fouling due to particulates for these

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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 24 aluminum components dur (cont.)

ing the period of extended operation, as well as for the other portions of the cool ers, as included in Table 3.3.1 Item 14.

25 Valves (body/

Aluminum, Air-Gas (moist None Identified None Required This grouping includes the bonnet only)

Brass, Copper air) external surface of subject and piping components/component components types that are in locations (such as the Diesel Gener ator Building) where expo sure to leaking borated water is not a possibility and the ambient conditions in those locations do not contain contaminants in sufficient quantities to result in other forms of corrosion to the materials in this

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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 Item Type Mechanism Program/Activity Discussion 25 grouping.

(cont.)

26 Flexible Hose Rubber Oil/Fuel Oil, None Identified None Required This grouping includes the and Coupling Treated Water internal surface of rubber components/component types (Diesel Generator Services System) that are not considered to be sus ceptible to degradation in fluid environments due to the lack of excessive tem peratures and to the change in material proper ties of elastomers being more closely tied to exter nal conditions such as ultra violet radiation. The external surfaces of these components are addressed as applicable in I n AftI IL IVA

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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 26 Table 3.3.1 Item 2.

(cont.)

27 Piping, tub-Brass, Copper Fuel Oil Loss of Material Chemistry Pro-This grouping includes sub ing and fit-due to Microbio-gram ject components/compo tings logically Influ-nent types exposed to fuel enced Corrosion oil in locations that are not (MIC) susceptible to water pooling (Diesel Generator Services System). Although the com ponents/component types in this grouping are not sus ceptible to water pooling, and thereby to related deg radation mechanisms, the Chemistry Program (Appendix B.1.4) is con servatively credited for the management of the condi tions that could lead to MIC in the fuel oil environment.

PAGE-145 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 D

Item Type Mechanism Program/Activity Discussion 28 Cooling unit Brass, Copper, Treated Water Loss of Material Chemistry Pro-This grouping includes sub tubes and fit-Copper Nickel due to crevice, pit-gram & Heat ject cooling components/

tings ting and/or gal-Exchanger component types with a vanic corrosion, Inspections treated water process fluid as well as ero-on one side and a non sion-corrosion, water process fluid on the and selective other (Air Handling, Local leaching; Heat Ventilation and Cooling, exchanger fouling Chilled Water, Component due to particu-Cooling, Diesel Generator lates; Cracking Services Systems). Also due to stress cor-included are brass compo rosion cracking nents exposed to closed (SCC) cycle cooling water that are susceptible to selective leaching due to their mate rial compositions. The material, environment, aging effect requiring man agement for this grouping a n a An.nIJ daPr a& nlA_.^iR la.u - M'IPlt MMFVNJ, rItFV I KC-VII-W PAGE 146 OF 252

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 28 are consistent with a (cont.)

NUREG-1801 item for heat exchangers between open cycle systems and closed cycle systems, except that the surface not exposed to treated (closed-cycle) water is not an open-cycle sys tem, as described in NUREG-1801, and there fore not within the scope of the corresponding aging management program.

At VCSNS, the Chemistry Program (Appendix B.1.4) is considered to provide adequate management of the conditions which could result in crevice, pitting or 3.0 - AGING MANAGEMENT REVIEW I"AGEl: 147 Or" 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 I Item Type Mechanism Program/Activity Discussion 28 galvanic corrosion during (cont.)

the period of extended operation. In addition to the Chemistry Program (Appendix B.1.4), the one time Heat Exchanger Inspection (Appendix B.2.12) is credited for the characterization of a loss of material due to erosion-cor rosion, heat exchanger fouling due to particulates (components in systems taking suction from the bot tom of a tank), if any, and loss of material due to selective leaching.

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3.4 REFERENCES

3.3-1 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.

3.3-2 NUREG-1801, "Generic Aging Lessons Learned Report," Volumes 1 and 2, NRC, April 2001.

3.3-3 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. 501395 FACILITY OPERATING LICENSE NO. NPF-12 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEMS 3.4.1 SYSTEM DESCRIPTION The Steam and Power Conversion Systems act as a heat sink to remove heat from the nuclear steam supply system and convert the heat generated in the reactor to the plant's electrical output.

The Steam and Power Conversion Systems include the following systems:

"* Auxiliary Boiler Steam and Feedwater System

"* Condensate System

"* Emergency Feedwater System Extraction Steam System

"* Feedwater System

"* Gland Seal Steam System

"* Main Steam System

"* Main Steam Dump System

"* Steam Generator Blowdown System 3.4.2 AGING MANAGEMENT REVIEW 3.4.2.1 Methodology Aging management review of Steam and Power Conversion Systems 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 3.4-1]. 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 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, D AS 41 A rt= o*,..

J.U - AlINU MANAhEMENT REVIEW

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 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 3.4-2] and evaluated for consistency with NUREG-1801 pro grams that are relied on for license renewal. The results are documented and discussed in Table 3.4-1 using the format suggested by the NRC Standard Review Plan for License Renewal (NUREG-1 800) [Reference 3.4-3].

3.4.2.2 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.

3.4.3 AGING MANAGEMENT PROGRAM 3.4.3.1 Aging Management Programs Evaluated In NUREG-1801 That Are Relied On For License Renewal Table 3.4-1 shows the component and commodity groups (combinations of materials and environments), and aging management programs evaluated in NUREG-1801 that are relied E A



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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 on for license renewal of the Steam and Power Conversion Systems. The table is based on Table 3.4-1 of NUREG-1800 [Reference 3.4-3] 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-1801. 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-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 compo nent/commodity groups beyond those identified in NUREG-1801.

3.4.3.2 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 3.4-1. 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 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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 1

Piping and fit-Cumulative TLAA, evaluated Yes, TLAA The TLAA is applicable to Class 2 and 3 pip tings in main fatigue damage in accordance with ing at VCSNS. See Section 4.3.2 for the feedwater 10 CFR 54.21 (c)

TLAA discussion of Class 2 and 3 piping.

line, steam line and auxil iary feedwa ter (AFW) piping (PWR only) 2 Piping and fit-Loss of material Water chemistry Yes, detection of The component /component type AMR results tings, valve due to general and one-time aging effects is to for VCSNS are consistent with NUREG-1 801 bodies and (carbon steel inspection be further evalu-in material, environment, aging effects, and

bonnets, only), pitting, and ated partially consistent in program. The attributes pump cas-crevice corrosion of the credited program/activity are not fully ings, tanks, consistent with the corresponding program

tubes, attributes as described in NUREG-1801 tubesheets, because NUREG-1801 recommends augmen channel tation of the Chemistry Program with a One head, and Time Inspection. The Chemistry Program has 3.0 - AGING MANAGEMENT REVIEW PAGE 153 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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

shell (except been in effect since initial plant startup and (cont.)

main steam has proven effective in maintaining systems system) chemistry and detecting abnormal conditions.

A review of the operating experience confirms the effectiveness of the Chemistry Program (Appendix B.1.4) for treated water to manage aging effects when continued into the period of extended operation. A one-time inspection is, therefore, not warranted for the majority of components/component types in this group.

The only exception is the Condensate Storage Tank which is inspected by the Above Ground Tank Inspections (Appendix B.2.1) activity.

This activity also inspects the interior of the tank above the water line. Consistent with NUREG-1801, the aging mechanisms for this group include general corrosion, pitting corro sion, and crevice corrosion. In addition to these aging mechanisms, galvanic corrosion, 3.0 - AGING MANA(FMFIuT RFVIAI PAGE 154 OF 252 3.0 - AGING MANAGEMENT P;:VIPW

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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

stress corrosion cracking, and corrosive (cont.)

effects of alternate wetting and drying are managed at VCSNS.

Consistent with NUREG-1 801, this group includes stainless steel and carbon steel in treated water. In addition to these materials, this group includes low alloy steel and nickel based metal at VCSNS. Consistent with NUREG-1801, this group includes piping and fittings, valve bodies, pump casings, and tanks of various systems within the steam and power conversion grouping. In addition, this group includes components/component types from the Nuclear Sampling System where these components/component types are simi lar and the above discussions apply.

3 AFW piping Loss of material Plant specific Yes, plant specific The combinations of components, materials, due to general, and environments identified in NUREG-1801 PAGE 155 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 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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 3

pitting, and crev-are not applicable to VCSNS. The AFW (cont.)

ice corrosion, (Emergency Feedwater at VCSNS) piping at MIC, and biofoul-VCSNS is not exposed to untreated water.

ing The Service Water System provides emer gency backup to the Emergency Feedwater System through automatic isolation valves that normally provide boundary isolation between the treated water of the Emergency Feedwater System and the untreated water of the Service Water System. For a description of the aging effects of carbon steel in an untreated water environment refer to Aging Management of Auxiliary Systems in Section 3.3.

4 Oil coolers in Loss of material Plant specific Yes, plant specific The component/component type AMR results AFW system due to general for VCSNS are consistent with NUREG-1 801 (lubricating oil (carbon steel in material and environment. Water and con side possibly only), pitting, and taminants will not intrude into the oil environ contaminated crevice corrosion, ments for these components/component

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect Aging Further Itm Gouponn Agnis EManagement Evaluation Discussion Item Group Mechanism Program Recommended 4

with water) and MIC types. This supported by a review of the oper (cont.)

ating experience, which reveals no aging effects for these components/component types. Therefore, no aging effects were deter mined to require management during the period of extended operations.

Consistent with NUREG-1 801, this group con tains carbon steel and stainless steel in an oil environment. In addition to these materials, this group contains cast iron at VCSNS.

Consistent with NUREG-1801, this group con tains AFW (Emergency Feedwater System at VCSNS) bearing oil system components.

5 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-1801 bon steel corrosion in material, environment, and aging effect.

components However, NUREG-1801 recommends plant flAF

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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

specific evaluation of the credited program.

(cont.)

The credited program/activity at VCSNS is Inspections for Mechanical Components (Appendix B.2.11). Consistent with NUREG 1801 this program/activity will detect and man age loss of material due to general corrosion.

In addition, this program will detect and man age loss of material due to galvanic corrosion.

An additional program, Maintenance Rule Structures Program (Appendix B.1.18), will detect and manage loss of material due to microbiologically influenced corrosion (MIC) on external surfaces at susceptible locations (in contact with groundwater).

Consistent with NUREG-1801, this group con tains carbon steel in an ambient, moist air environment. In addition to carbon steel, this group contains low alloy steel and cast iron at 2 n

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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

VCSNS. Consistent with NUREG-1801, this (cont.)

group contains external surfaces for various components/component types.

6 Carbon steel Wall thinning due Flow-accelerated No The component/component type AMR results piping and to flow-acceler-corrosion for VCSNS are consistent with NUREG-1 801 valve bodies ated corrosion in material, environment, aging effect, and program.

Consistent with NUREG-1801, this group con tains carbon steel in a treated water environ ment. In addition to carbon steel, this group contains low alloy steel at VCSNS. Consistent with NUREG-1801, this group includes valve bodies and piping and fittings of various sys tems within the steam and power conversion grouping. The Flow Accelerated Corrosion Monitoring Program (Appendix B.1.6) man ages this aging effect/mechanism at VCSNS.

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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

Carbon steel Loss of material Water chemistry No The component/component type AMR results piping and due to pitting and for VCSNS are consistent with NUREG-1 801 valve bodies crevice corrosion in material, environment, aging effect, and in main credited program. Consistent with NUREG steam system 1801, the aging mechanisms for this group are pitting corrosion and crevice corrosion. In addition to these mechanism,,

I corro sion and galvanic corrosion are...., idged at VCSNS.

Consistent with NUREG-1801, this group con tains carbon steel in a treated water environ ment. Consistent with NUREG-1 801, this group contains valve bodies and piping and fit tings. The Chemistry Program (Appendix B.1.4) manages this aging effect/mechanism at VCSNS.

8 Closure bolt-Loss of material Bolting integrity No Non-Class 1 Closure bolting is considered to ing in due to general be a piece-part of the components/component 3.U - MI.II'E

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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 8

high-pres-corrosion; crack types as a whole at VCSNS. Therefore a bolt (cont.)

sure or high-initiation and ing integrity program is not credited for aging temperature growth due to management. As a piece-part of subject com systems cyclic loading and/

ponents/component types at VCSNS, the spe or SCC.

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 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.

9 Heat Loss of material Open-cycle cool-No Open Cycle Cooling Water Systems as exchangers due to general ing water system described by NUREG-1801 are not used in and coolers/

(carbon steel any Steam and Power Conversion Systems at condensers only), pitting, and VCSNS.

serviced by crevice corrosion, 3.0 - AGING MANAGEMENT IREVIEW I"'M%.IC 1g W

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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 9

open-cycle MIC, and biofoul-Open-cycle cool-No Open Cycle Cooling Water Systems as (cont.)

cooling water ing; buildup of ing water system described by NUREG-1801 are not used in deposit due to any Steam and Power Conversion Systems at biofouling VCSNS.

10 Heat Loss of material Closed-cycle cool-No Closed Cycle Cooling Water Systems as exchangers due to general ing water syste'm described by NUREG-1801 are not used in and coolers/

(carbon steel any Steam and Power Conversion Systems at condensers only), pitting, and VCSNS.

serviced by crevice corrosion closed-cycle cooling water 11 External sur-Loss of material Above ground car-No The component/component type AMR results face of above due general (car-bon steel tanks for VCSNS are consistent with NUREG-1801 ground con-bon steel only),

in material, environment, and aging effect.

densate stor-pitting, and crev-However, rather than an above ground carbon age tank ice corrosion steel tanks program as recommended by NUREG-1801, general corrosion on external surfaces is detected and managed by

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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 11 Inspections for Mechanical Components (cont.)

(Appendix B.2.11) at VCSNS. Also, at VCSNS the ambient environment in the yard environment does not contain contaminants in sufficient quantities that could be concentrated in wetted locations to cause pitting corrosion and crevice corrosion, therefore, loss of mate rial due to pitting corrosion and crevice corro sion has not been identified as an aging effect.

Consistent with NUREG-1 801, this group con tains carbon steel in a yard environment. Con sistent with NUREG-1801, this group contains external surfaces of the above ground Con densate Storage Tank.

12 External sur-Loss of material Buried piping and No The component/component type AMR results face of bur-due to general, tanks surveillance for VCSNS are consistent with NUREG-1801 ied pitting, and crev-or in material, environment, aging effect, and condensate ice corrosion, and Buried piping and Yes, detection of credited program. The condensate storage 3.0 - AI3IN MAIb4AULMLN I KLVIW rAu is Ut- L 3.0 - AGING MANAGEIME.NT RE::VIE::W I"AurI= lbj U-z*z

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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 12 storage tank MIC tanks inspection aging effects and tank is above ground, however, there is under (cont.)

and AFW pip-operating experi-ground piping in the AFW (Emergency Feed ing ence are to be fur-water System at VCSNS).

ther evaluated Consistent with NUREG-1801, this group con tains carbon steel in an underground (buried) environment. Consistent with NUREG-1801, this group includes external surfaces of piping and fittings.

The Buried Pipe and Tanks Inspection pro gram (Appendix B.2.10) will manage these aging effects/mechanisms at VCSNS.

13 External sur-Loss of material Boric acid corro-No The component/component type AMR results face of car-due to boric acid sion for VCSNS are consistent with NUREG-1 801 bon steel corrosion in material, environment, aging effect, and components credited program.

Consistent with NUREG-1801, this group 3.0 - AGING MANAGEMENT REVIEW PAGE 164 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR THE STEAM & POWER CONVERSION 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 contains external surfaces of carbon and low (cont.)

alloy steel components/component types in an air environment where there is a potential for leaking and dripping chemically treated borated water. In addition to these metals, this group also includes cast iron at VCSNS.

The Boric Acid Corrosion Surveillances (Appendix B.1.2) will manage this aging effect/mechanism at VCSNS.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.4.3.3 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 TalV, 3.4-2. The standard six-column format has been uti lized. The discussion column pro,

• • s 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 3.4-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE STEAM & POWER CONVERSION 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

Piping and Stainless Steel Ambient, moist None Identified None Required This grouping includes piping sys-air external surfaces of stain tem compo-less steel piping system nents components exposed to a moist air environment. At VCSNS, the ambient envi ronment of the yard and sheltered environments do not contain contaminants of sufficient concentration to cause aging effects that require aging management 2

Piping and Aluminum, Brass Ambient, moist Boric Acid Corro-Boric Acid Corro-The Boric Acid Corrosion piping sys-air sion / Aggressive sion Surveillances Surveillances (Appendix tem compo-Chemical Attack B.1.;e) will manage boric nents acid corrosion on external surfaces of components that are susceptible to this aging mechanism. No other aging mechanisms were PAGE 167 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 3.4-2:

SUMMARY

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

ProgramActivity Discussion Item Type Mechanism 2

identified for this material/

(cont.)

environment combination at VCSNS.

3 Piping and Aluminum, Brass Oil None Identified None Required Water and contaminants piping com-will not intrude into the oil ponents and environments for these heat components/component exchanger types. This is supported by tubes review of the operating experience, which reveals no aging effects for these components/component types. Therefore, no aging effects were determined to require management during the period of extended operations.

4 EFWP Tur-Carbon Steel Ambient, moist General Corro-Preventive Main-The Emergency Feedwater bine (Casing air sion tenance Activities:

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE STEAM & POWER CONVERSION 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

Only), Valve Terry Turbine a standby condition (cont.)

(Body Only) whereby the internal sur EFWP Tur-faces of these components bine Gover-are exposed to an ambient, nor valve moist air environment. Pre ventive Maintenance Activi ties: Terry Turbine (Appendix B.1.25) will manage this aging effect.

5 Valves (Bod-Stainless Steel Treated Water Crevice Corro-Chemistry Pro-The Chemistry Program ies) sion, Pitting Cor-gram (Appendix B.1.4) will man rosion, Stress age crevice corrosion, pit Corrosion Crack-ting corrosion, and stress ing corrosion cracking for stain less steel valve bodies in a treated water environment during the period of extended operation.

3.0 - AGING MANAGEMENT REVIEW PAGE 169 OF 252 3.0 - AGING MANAGEMENT REVIEW PAGE 169 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.4-2:

SUMMARY

OF AGING MANAGEMENT EVALUATIONS FOR THE STEAM & POWER CONVERSION 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

Heat Brass Treated Water Crevice Corro-Chemistry Pro-The Chemistry Program Exchanger sion, Galvanic gram, Heat (Appendix B.1.4) will man EF Pump Corrosion, Pitting Exchanger age crevice corrosion, pit Turbine Lube Corrosion, Selec-Inspections ting corrosion, and galvanic Oil - Tube tive Leaching, corrosion of brass heat Stress Corrosion exchanger tubes in a Cracking treated water environment during the period of extended operation. Heat Exchanger Inspections (Appendix B.2.12) will manage selective leaching of brass heat exchanger tubes in a treated water environment during the period of extended opera tion.

- AUIrlIu MANAMENT KEVIEW PAGE 170 OF 252 3.0 - AGING MANAGEIME*NT REFVIEW PAGE 170 OF 252

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

4.4 REFERENCES

3.4-1 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.

3.4-2 NUREG-1 801, "Generic Aging Lessons Learned Report," Volumes 1 and 2, NRC, April 2001.

3.4-3 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 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES, AND COMPONENT SUPPORTS 3.5.1 CONTAINMENT, STRUCTURES, AND COMPONENT SUPPORTS DESCRIPTIONS The Containment, Structures and Component Supports applicable to License Renewal at VCSNS include the following (for plant location see Site Facilities Drawing):

"* Reactor Building (Internal Structures and Class 1 Component Supports)

"* Auxiliary Building (includes Hot Machine Shop, Refueling Water Storage Tank &

Reactor Makeup Water Storage Tank foundations and West Penetration Access Area)

"* Control Building

"* Intermediate Building (includes East Penetration Access Area)

"* Diesel Generator Building

"* Fuel Handling Building

"* Turbine Building

"* Service Water Pumphouse, Intake and Discharge Structures

"° Yard Structures (includes Fire Service Pumphouse, Condensate Storage Tank foundation, and Electrical Manhole MH-2)

"* Earthen Embankments (includes Service Water Pond North Dam, South Dam, East Dam, West Embankment and North Berm)

"* Electrical Substation and Relay House 3.5.1.1 Reactor Building The Reactor Building is a post tensioned, reinforced concrete structure with an integral steel liner. The Reactor Building consists of a cylindrical wall, a shallow dome roof and a founda tion mat with a depressed incore instrumentation pit under the reactor vessel. The founda tion mat bears on fill concrete that extends to competent rock. At the underside of the Reactor Building foundation mat a tendon access gallery is formed into the top of the fill con crete. A retaining wall, extending approximately one-quarter of the way around the Reactor Building, protects the below grade portions of the Reactor Building wall from the subgrade.

Adjacent buildings surround the remaining three-quarters of the Reactor Building. The inter nal structures of the Reactor Building consist of the primary shield wall surrounding and sup porting the reactor vessel; secondary shield walls surrounding and laterally supporting each steam generator and the pressurizer; refueling cavity and fuel transfer canal; mezzanine floor and operating floor, both consisting of concrete slabs supported by structural steel 3.U - AGING MANAGEMENT REVIEW DAt*-_"

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3.5.1.2 Auxiliary Building The Auxiliary Building superstructure is a reinforced concrete shear wall (box type) structure containing five main floor levels above the foundation and extending up to elevation 485'-0" (designated as the roof). Above this level is another story composed primarily of a metal clad structural steel braced frame, but with limited areas continuing the reinforced concrete construction employed below. The foundation is comprised of a reinforced concrete struc tural mat which is supported on fill concrete down to competent bedrock. A waterproofing membrane is provided between the structural mat concrete and fill concrete because of the depth of the foundation below the ground water table.

3.5.1.3 Control Building The Control Building superstructure is a steel frame structure with concrete exterior shear walls containing four main floor levels and a concrete roof. The foundation system for the Control Building (CB) is comprised of a reinforced concrete mat which is supported on fill concrete down to competent bedrock.

3.5.1.4 Intermediate Building The Intermediate Building superstructure is a "L" shaped reinforced concrete shear wall (box type) structure containing two main floor levels above the foundation and extending up to a low roof. Above the low roof is a partial third floor of reinforced concrete. The foundation sys tem for the Intermediate Building (IB) is comprised of a reinforced concrete basement floor slab that acts in conjunction with a series of grade beams to transfer vertical loads to rein forced concrete caissons, shear/bearing walls, and concrete piers. The shear/bearing wall foundations and reinforced concrete caissons are founded on competent bedrock. The piers are founded on fill concrete that extends beyond the Reactor Building and Auxiliary Building.

3.5.1.5 Diesel Generator Building The Diesel Generator Building superstructure is a reinforced concrete shear wall (box type) structure containing three main floor levels above the foundation mat. The operating floor is where the diesel generators are located, with their foundations extending down to the base ment floor mat. The foundation system for the Diesel Generator Building consists of a rein-3.0 - AWNI MANAI.iLMN I KLVIVV

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 forced concrete slab and grade beam system that is supported by reinforced concrete caissons drilled into competent bedrock.

3.5.1.6 Fuel Handling Building The Fuel Handling Building superstructure is a steel frame superstructure containing two main floor levels and a roof. The foundation system for the Fuel Handling Building is com prised of a reinforced concrete mat formed by the bottom of the Spent Fuel Pool and Fuel Cask Pit. The foundation mat is supported by reinforced concrete piers that extend to the fill concrete adjacent to the Reactor and Auxiliary Buildings and by reinforced concrete cais sons that extend to competent rock on the north and east sides.

3.5.1.7 Turbine Building The Turbine Building is a non Seismic Category I building. The superstructure (steel fram ing, metal siding and metal roof deck) is supported on a reinforced concrete substructure.

The foundation for the Turbine Building is mostly comprised of a reinforced concrete mat supported by Zone III fill (graded crushed stone) material. The turbine generator pedestal foundation mat is founded on fill concrete.

3.5.1.8 Service Water Structures The Service Water Pumphouse (SWPH) superstructure is a reinforced concrete building (containing three floor levels) constructed within the West Embankment of the Service Water Pond. The foundation is comprised of a reinforced concrete structural mat. The entire struc tural mat is supported on compact fill which extends from the underside of the mat. The compacted fill is supported on in-situ soils (saprolite), to decomposed rock, to competent rock. The SWPH structure is separate from the Service Water Intake Structure (SWIS) and from buried connecting pipes and electrical duct banks by flexible joints, which accommo date relative settlement and seismic movement. The SWIS is a reinforced concrete rectan gular box culvert (tunnel) with two reinforced concrete wing walls at the intake end. The foundation for the SWIS forms the floor of the tunnel and is comprised of a reinforced con crete mat. The mat is supported by compacted fill material except for a portion of the inlet end which rests on in-situ soils. The Service Water Discharge Structure (SWDS) is a rein forced concrete rectangular basin mostly buried within the West Embankment of the Service Water Pond. The foundation is comprised of a reinforced concrete mat. The base mat bears partly on decomposed rock and partly on fill concrete that extends to the decomposed rock.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.5.1.9 Yard Structures Yard Structures include the Condensate Storage Tank Foundation, Electrical Manhole EH-2, and the Fire Service Pumphouse. The Condensate Storage Tank (CST) foundation consists of a reinforced concrete mat which is supported by a Zone Ill fill (graded crushed stone) material. A reinforced concrete ring wall extends above the foundation mat which secures the CST with anchor bolts. Electrical Manhole EH-2 is a reinforced concrete structure which contains electrical duct banks for Class 1 E cables. The manhole is mostly embedded below the yard grade, with reinforced concrete walls and foundation mat. The Fire Service Pump house is a concrete block building (with composite roof) founded upon the reinforced con crete Circulating Water Intake Structure (CWlS). This non-safety structure is included within License Renewal in compliance with 1 OCFR50.48 (Fire Protection). The Electrical Substa tion yard, with the exception of the paved roadways, is covered with several inches of "crusher run" stone and is enclosed by a perimeter fence. The Electrical Substation and Transformer Area are included within License Renewal in compliance with the NRC revised staff position on the scoping of SBO equipment for license renewal dated 4/1/2002.

3.5.1.10 Earthen Embankments The Earthen Embankments (North Dam, South Dam, and East Dam and the West Embank ment) form the Service Water Pond. These earthen structures are Seismic Category I and were designed to satisfy the intent of Regulatory Guides 1.27 and 1.29. The three dams and West Embankment are homogeneous earth structures with fill material consisting of residual soil and saprolite which was excavated from local borrow sources. The shoreline along Mon ticello Reservoir north of the plant and west of the North Dam has an earthen dike (North Berm) constructed above the site grade. The North Berm is classified as a non-seismic, non nuclear safety-related structure. The primary function of the North Berm is to protect the site from the potential of external flooding from Monticello Reservoir (due to probable maximum precipitation and wave run-up).

3.5.1.11 Class I Component Supports Class 1 Component Supports are those supports for major equipment and Class 1 piping that are subject to aging management review including: Class 1 piping supports and major equipment supports (pressurizer base flange and upper lateral supports; reactor vessel sup ports; steam generator vertical, lower lateral, and upper lateral supports; and reactor coolant pump lateral and vertical support assemblies).

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.5.2 AGING MANAGEMENT REVIEW 3.5.2.1 Methodology Aging management review of Containment, Structures and Component Supports involved consideration and evaluation of the materials, environments, and stressors that are associ ated with each structure, component, or commodity grouping under review, as discussed in Section 4.2 of NEI 95-10 [Reference 3.5-1]. The VCSNS AMR methodology follows the approach recommended in NEI 95-10 and is based on generic industry guidance for deter mining aging effects for both mechanical and civil/structural components. The guidance rep resents 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 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, structures, and commodities. The results of the evaluation of materials and environment combinations, using the VCSNS methodol ogy, are aging effects; and, if the aging effects adversely affect intended functions, the results are aging effects requiring management for the applicable components and cor modities. Aging effects that require management are correlated to aging management P.

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 3.5-2] ý 'evaluated for consistency with NUREG-1801 pro grams that are relied on for licens, anewal. The results are documented and discussed in Table 3.5-1 using the format suggested by the NRC Standard Review Plan for License Renewal (NUREG-1800) [Reference 3.5-3].

3.5.2.2 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.

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

3.5.3 AGING MANAGEMENT PROGRAM 3.5.3.1 Aging Management Programs Evaluated In NUREG-1801 That Are Relied On For License Renewal Table 3.5-1 shows the aging management groups (combinations of components, materials and aging effects) and the aging management programs evaluated in NUREG-1 801 that are relied on for license renewal of the Containment, Class I Structures, and Component Sup ports at VCSNS. Note that this table only includes those components, materials and aging effects that are applicable to a PWR. The VCSNS comparison to NUREG-1801 (including clarifications and exceptions) is included in the "Discussion" column.

3.5.3.2 Further Evaluation Of Aging Management As Recommended By NUREG-1801 Further evaluation of aging management as recommended by the NUREG-1 801 has been incorporated into the "Discussion" column of Table 3.5-1.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 Comm~pon Componetsof All Types of PWR Containment 1

Penetration Cumulative TLAA evaluated in Yes, TLAA VCSNS does not evaluate fatigue for penetra sleeves, pen-fatigue damage accordance with tion sleeves, bellows or dissimilar metal welds; etration bel-(CLB fatigue anal-10 CFR 54.21(c) therefore, a TLAA evaluation is not applicable.

lows, and ysis exists) dissimilar Penetration Sleeves meet the requirements metal welds of ASME Section III, comply with GDC-51, and behave in a non-brittle manner.

Penetration Bellows are used in hot penetra tions at VCSNS but do not provide contain ment isolation since they are located within the penetration on the exterior side of contain ment. Hot penetrations are sealed on the inside of containment by a flat plate welded to both the penetration sleeve and process pipe (similar to cold penetrations), thus providing L _____________________

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 containment isolation without the use of a (cont.)

resilient or flexible seal.

Dissimilar Metal Welds are materials and not components. VCSNS penetration sleeves and process pipes use similar (SA) materials.

2 Penetration Cracking due to Containment Yes, detection of VCSNS Aging Management Programs: 10 sleeves, bel-cyclic loading; inservice inspec-aging effects is to CFR 50 Appendix J General Visual Inspection lows, and dis-crack initiation tion (ISI) and con-be evaluated (Appendix B.1.11), 10 CFR 50 Appendix J similar metal and growth due to tainment leak rate Leak Rate Testing (Appendix B.1.12) and welds SCC test Containment ISI Program - IWE/IWL (Appen dix B.1.16) are consistent with those reviewed and approved in NUREG-1801.

Stress Corrosion Cracking (SCC) requires a combination of a corrosive environment, sus ceptible materials, and high tensile stresses.

(1) VCSNS penetration sleeves are not 3.0 - AGING MANAGEMENT RIVIIEW PAGE1* -if 9~ OF" 25

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

subject to high tensile stresses or aggressive (cont.)

chemicals during normal operation, while simi lar metal welds are used between penetration sleeves and process pipes; therefore, SCC is not an applicable aging effect requiring man agement. (2) VCSNS hot penetration bellows do not perform a pressure boundary function nor incorporate a flexible seal assembly on the inboard side of containment. They do provide structural and/or functional support for pro cess piping on the outboard side of contain ment; therefore, in the unlikely event of SCC in the bellows, the intended functions are not affected.

3 Penetration Loss of material Containment ISI No VCSNS Aging Management Programs: 10 sleeves, pen-due to corrosion and Containment CFR 50 Appendix J General Visual Inspection etration bel-leak rate test (Appendix B.1.11), 10 CFR 50 Appendix J lows, and Leak Rate Testing (Appendix B.1.12) and A

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

dissimilar Containment ISI Program - IWE/IWL (Appen (cont.)

metal welds dix B.1.16) are consistent with those reviewed and approved in NUREG-1801.

4 Personnel Loss of material Containment ISI No VCSNS Aging Management Programs: 10 airlock and due to corrosion and Containment CFR 50 Appendix J General Visual Inspection equipment leak rate test (Appendix B.1.11), 10 CFR 50 Appendix J hatch Leak Rate Testing (Appendix B.1.12) and Containment ISI Program - IWE/IWL (Appen dix B.1.16) are consistent with those reviewed and approved in NUREG-1801.

5 Personnel Loss of leak tight-Containment leak No VCSNS Aging Management Programs: 10 airlock and ness in closed rate test and plant CFR 50 Appendix J General Visual Inspection equipment position due to technical specifi-(Appendix B.1.11), 10 CFR 50 Appendix J hatch mechanical wear cations Leak Rate Testing (Appendix B.1.12) and of locks, hinges, Containment ISI Program - IWE/IWL (Appen and closure dix B.1.16) are consistent with those reviewed mechanisms and approved in NUREG-1801.

3.0 - AGING MANAGEMENT REVIEW rIij

101 ur £L P'AGE 1 UO" 252 3.0 -AGING MANAGEMENT REVIEW

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 5

(cont.)

Operation of hatches is governed by VCSNS Technical Specifications. Plant operational experience has not identified any fretting or seal degradation. Locks, hinges, and closure mechanisms are active components; there fore, mechanical wear is not considered an aging effect.

6 Seals, gas-Loss of sealant Containment ISI No Loss of sealing is not considered an aging kets, and and leakage and Containment effect, but rather a consequence of elastomer moisture bar-through contain-leak rate test degradation which is managed by the pro riers ment due to dete-grams: 10 CFR 50 Appendix J General Visual rioration of joint Inspection (Appendix B.1.11), 10 CFR 50 seals, gaskets, Appendix J Leak Rate Testing (Appendix and moisture bar-B.1.12), Containment ISI Program - IWE/IWL riers (Appendix B.1.16) and Maintenance Rule Structures Program (Appendix B.1.18) which are consistent with those reviewed and I

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

approved in NUREG-1801.

(cont.)

Component types include: moisture barrier, compressible joints and seals used for seismic gaps, and fire barrier seals. These compo nents are managed by the Containment ISI, IWE and Maintenance Rule Structures Pro grams.

PWR Concrete (Reinforced and Prestressed) and Steel Containment 7

Concrete ele-Aging of accessi-Containment ISI Yes, if aging ACCESSIBLE AREAS ments: foun-ble and inaccessi-mechanism is sig dation, dome, ble concrete nificant for inac-VCSNS Aging Management Programs: 10 and wall areas due to cessible areas CFR 50 Appendix J General Visual Inspection leaching of cal-(Appendix B.1.11) and Containment ISI Pro cium hydroxide, gram - IWE/IWL (Appendix B.1.16) are con aggressive chemi-sistent with those reviewed and approved in cal attack, and NUREG-1801.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect I Aging Further Item Grv,;,p Mechanism Management Evaluation Discussion Program Recommended 7

corrosion of (cont.)

embedded steel Leaching of Calcium Hydroxide from rein forced concrete becomes significant only if the concrete is exposed to flowing water. Resis tance to leaching is enhanced by using a dense concrete with low permeability and well cured. The VCSNS containment structure is not exposed to flowing water and designed in accordance with ACI-318 and constructed in accordance with ACI-301 and ASTM Stan dards, which provides a good quality, dense, low permeability concrete. Leaching has been identified in the accessible containment Ten don Access Gallery (due to groundwater infil tration) and is managed by the programs: 10 CFR 50 Appendix J General Visual Inspection (Appendix B.1.11) and Containment ISI Pro gram - IWE/IWL (Appendix B.1.16).

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

(cont.)

Aggressive Chemical Attack becomes sig nificant to concrete exposed to an aggressive environment (Chlorides > 500 ppm, Sulfates >

1500 ppm, and pH < 5.5). Resistance to mild acid attack is enhanced by using a dense con crete with low permeability and a low water-to cement ratio of less than 0.50. The VCSNS containment structure uses a dense, low per meable concrete with a maximum water-to cement ratio of 0.48, which provides an acceptable degree of protection against aggressive chemical attack. VCSNS is not located in areas exposed to sulfate or chloride attack, nor located near industrial plants whose emissions would change environmen tal parameters and cause degradation to con crete. The water chemical 3.U - AI.INU MRNAjMN I KLVILVV r#IJ

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J.U - AUINU. MANAlaI:Mr-N I KI:VIIt:W P"AGLE 185 UIF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

analysis results confirm that the site ground (cont.)

water is mildly acidic but considered to be non-aggressive. Therefore, loss of material due to aggressive chemical attack is not an aging effect requiring management for acces sible containment concrete structures. Peri odic monitoring of the below grade water chemistry will be conducted during the period of extended operation to demonstrate that the below-grade environment is not aggressive.

Corrosion of Embedded Steel becomes sig nificant if exposed to an aggressive environ ment (Concrete pH < 11.5 and Chlorides >

500 ppm). Corrosion is not significant if the concrete has a low water-to-cement ratio, low permeability, and designed in accordance with ACI Standards (ACI-318 or ACI-349). The Sftl. AF-I"IfP UAUAf-.CICI T OtIIC-l ll 1

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• I*VlI*--Vl PAGE 186 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

design and construction of the VCSNS con (cont.)

tainment structure (in accordance with accepted ACI Standards) prevents corrosion of embedded steel from occurring; therefore, this aging effect does not require management for accessible areas.

INACCESSIBLE AREAS Inaccessible Areas at VCSNS do not require a plant-specific aging management program for leaching of calcium hydroxide, aggressive chemical attack or corrosion of embedded steel due to the following:

Containment concrete surfaces are not exposed to flowing water and the in-place concrete is constructed to design PAGIE 187 UO-252 3.0 - AGING MANAGEMENT REVIEW

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 7

requirements in accordance with ACI rec (cont.)

ommendations (at the time of construction) which produced a dense concrete with low permeability. Specific reference to ACI 201.2R-77 is not made since the plant was designed and constructed prior to 1977.

Concrete is not exposed to a below grade environment which is considered aggres sive. Refer above to "Aggressive Chemical Attack" for "Accessible Areas." Additionally, VCSNS used a concrete design mix with maximum water-cement ratio of 0.44 - 0.48 which is specified by ACI Standards to be chemically resistant and watertight. Peri odic monitoring of the below grade water chemistry will be conducted during the period of extended operation to demon strate that the below-grade environment is

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SLICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

not aggressive.

(cont.)

8 Concrete ele-Cracks, distor-Structures moni-No, if within the VCSNS Aging Management Programs: 10 ments: foun-tion, and toring scope of the appli-CFR 50 Appendix J General Visual Inspection dation increases in com-cant's structures (Appendix B.1.11), Containment ISI Program ponent stress monitoring pro-

- IWE/IWL (Appendix B.1.16) and Mainte level due to settle-gram nance Rule Structures Program (Appendix ment B.1.18) are consistent with those reviewed and approved in NUREG-1801.

The VCSNS containment foundation is con structed directly on competent bedrock and is not subject to settlement; therefore, aging management is not required.

9 Concrete ele-Reduction in foun-Structures moni-No, if within the The VCSNS containment foundation does not ments: foun-dation strength toring scope of the appli-use porous concrete and is not subject to flow dation due to erosion of cant's ing water; therefore, aging management is 3.0 - AGING MANAGEMENT REVIEW P'AGE -1189 UO" 25

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

porous concrete structures monitor-not required.

(cont.)

subfoundation ing program 10 Concrete ele-Reduction of Plant specific Yes, for any por-The VCSNS containment concrete elements ments: foun-strength and mod-tions of concrete are not exposed to temperatures which dation, dome, ulus due to ele-containment that exceed the thresholds for degradation; there and wall vated temperature exceed specified fore, reduction of strength and modulus due to temperature limits elevated temperatures are not aging effects requiring management.

11 Prestressed Loss of prestress TLAA evaluated in Yes, TLAA VCSNS Aging Management Programs: Con containment:

due to relaxation, accordance with tainment ISI Program - IWE/IWL (Appendix tendons and shrinkage, creep, 10 CFR 54.21 (c)

B.1.16) and Tendon Surveillance Program anchorage and elevated tem-(Appendix B.3.3) are consistent with those components perature reviewed and approved in NUREG-1801.

VCSNS Containment tendons have been determined to be a TLAA in accordance with 10 CFR 54.3. Refer to Section 4.5.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 Steel ele-Loss of material Containment ISI Yes, if corrosion is VCSNS Aging Management Programs: 10 ments: liner due to corrosion and containment significant for inac-CFR 50 Appendix J General Visual Inspection plate and in accessible and leak rate test cessible areas (Appendix B.1.11), 10 CFR 50 Appendix J containment inaccessible Leak Rate Testing (Appendix B.1.12), Con shell areas tainment Coating Monitoring And Maintenance Program (Appendix B.1.15) and Containment ISI Program - IWE/IWL (Appendix B.1.16) are consistent with those reviewed and approved in NUREG-1801.

Corrosion for inaccessible areas (embedded containment liner) is not significant because:

Concrete meeting the requirements of ACI 318 or ACI-349 and the guidance of ACI 201.2R was used for the containment con crete in contact with the embedded con tainment liner.

3.0 - AGING MANAGEMENT REVIEW

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 12 0 The concrete is monitored under Mainte (cont.)

nance Rule Structures Program and IWL to ensure that it is free of penetrating cracks.

"* The moisture barrier is monitored under IWE for aging degradation.

"* Borated water leakage in the containment structure is not a common occurrence and is monitored under the aging management program Boric Acid Corrosion Surveil lances (Appendix B.1.2).

13 Steel ele-Loss of material Protective coating No VCSNS Aging Management Programs: 10 ments: pro-due to corrosion monitoring and CFR 50 Appendix J General Visual Inspection tected by in accessible maintenance (Appendix B1.11), Containment Coating coating areas only Monitoring and Maintenance Program (Appendix B.1.15), Containment ISI Program

- IWE/IWL (Appendix B.1.16) and Mainte nance Rule Structures Program (Appendix B.1.18) are consistent with those 3.U - PtbINb MRNALIMN I KVIW PAGE 192 OF 252 J.,U - AUINUi MANAULML-N I KI"VIILW PAGE 192 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 13 reviewed and approved in NUREG-1801.

(cont.)

14 Prestressed Loss of material Containment ISI No VCSNS Aging Management Programs: Con containment:

due to corrosion tainment ISI Program - IWE/IWL (Appendix tendons and of prestressing B.1.16) and Tendon Surveillance Program anchorage tendons and (Appendix B.3.3) are consistent with those components anchorage com-reviewed and approved in NUREG-1801.

ponents 15 Concrete ele-Scaling, cracking, Containment ISl No ACCESSIBLE AREAS ments: foun-and spalling due dation, dome, to freeze-thaw; VCSNS Aging Management Programs: 10 and wall expansion and CFR 50 Appendix J General Visual Inspection cracking due to (Appendix B.1.11), Containment ISI Program reaction with

- IWE/IWL (Appendix B.1.16), and Mainte aggregate nance Rule Structures Program (Appendix B.1.18) are consistent with those reviewed and approved in NUREG-1801.

3.0 - AGING MANAGEMENT REVIEW PAGE 193 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 (cont.)

Freeze-thaw is not an aging effect requiring management for the containment structure at VCSNS, since it is not exposed to saturated water conditions and is designed and con structed to acceptable ACI and ASTM Stan dards.

Reaction with Aggregates for the contain ment structure at VCSNS is mitigated by care fully designed and selected concrete constituents; therefore, expansion and crack ing due to reaction with aggregates is not an aging effect requiring management.

INACCESSIBLE AREAS Inaccessible Areas at VCSNS do not require 3.U R

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 a plant-specific aging management program (cont.)

for freeze-thaw or reaction with aggregates due to the following:

" VCSNS lies within the "moderate" weather ing region of the U. S. (as defined in ASTM C33) and its containment concrete is not exposed to saturated water conditions near the ground surface which eliminates freeze-thaw considerations. Additionally, The concrete used at VCSNS is designed with entrained air content of between 4%

and 6% in conformance with ACI-301, and IWL inspections have not identified any concrete degradation related to freeze thaw.

"* Aggregates used in concrete at VCSNS were carefully selected (using local 3.0 - AGING MANAGEMENT REVIEW PAGE 195 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 15 quarries) to mitigate aggregate reactions, (cont.)

incorporating design specifications in con formance with accepted ACI and ASTM Standards.

Chass I Structures 16 All Groups All types of aging Structures moni-No, if within the ACCESSIBLE AREAS except Group effects toring scope of the appli 6: accessible cant's structures VCSNS Aging Management Programs:

interior/exte-monitoring pro-described in Containment Coating Monitoring rior concrete gram and Maintenance Program (Appendix and steel B.1.15), Containment ISI Program - IWE/IWL components (Appendix B.1.16) and Maintenance Rule Structures Program (Appendix B.1.18) are consistent with those reviewed and approved in NUREG-1801.

Freeze-thaw is not an aging effect requiring RAiIIA i

i APNA PMiN I~ IC JI~W PAGE19....

25 PAGE 196 OF 252 3.0 - AGING MANAGEME:NT IR'EIVIE'W

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 management for these groups of structures at (cont.)

VCSNS, since they are not exposed to satu rated water conditions and are designed and constructed to acceptable ACI and ASTM Standards.

Leaching of Calcium Hydroxide from rein forced concrete becomes significant only if the concrete is exposed to flowing water. Resis tance to leaching is enhanced by using a dense concrete with low permeability. These groups of structures at VCSNS are not exposed to flowing water and designed in accordance with ACI-318 and constructed in accordance with ACI-301 and ASTM Stan dards, which provides a good quality, dense, low permeability concrete.

3.0 - AGING MANAGEMENT REVIEW PAGE 197 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 Reaction with Aggregates for concrete for (cont.)

these groups of structures at VCSNS are miti gated by carefully designed and selected con crete constituents; therefore, expansion and cracking due to reaction with aggregates is not an aging effect requiring management.

Corrosion of Embedded Steel becomes sig nificant if exposed to an aggressive environ ment (Concrete pH < 11.5 and Chlorides >

500 ppm). Corrosion is not significant if the concrete has a low water-to-cement ratio, low permeability, and designed in accordance with ACI Standards (ACI-318 or ACI-349). The design and construction of these groups of structures at VCSNS prevents corrosion of embedded steel from occurring; therefore, this aging effect does not require management for p

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 accessible areas.

(cont.)

Aggressive Chemical Attack becomes sig nificant to concrete exposed to an aggressive environment (Chlorides > 500 ppm, Sulfates >

1500 ppm, and pH < 5.5). Resistance to mild acid attack is enhanced by using a dense con crete with low permeability and a low water-to cement ratio of less than 0.50. These groups of structures at VCSNS use a dense, low per meable concrete with a maximum water-to cement ratio of 0.48, which provides an acceptable degree of protection against aggressive chemical attack. VCSNS is not located in areas exposed to sulfate or chloride attack, nor located near industrial plants whose emissions would change environmen tal parameters and cause degradation to i.U - AiII'dU MRNALiMN I ?VIVV i

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199 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 concrete. The water chemical analysis results (cont.)

confirm that the site groundwater is consid ered to be non-aggressive; therefore, loss of material due to aggressive chemical attack is not an aging effect requiring management.

Periodic monitoring of the below grade water chemistry will be conducted during the period of extended operation to demonstrate that the below-grade environment is not aggressive.

Corrosion of structural steel components is managed by the Maintenance Rule Structures Program (Appendix B.1.18).

Lubrite materials are not used at VCSNS in the reactor pressure vessel supports; there fore, aging management is not required.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 INACCESSIBLE AREAS (cont.)

Inaccessible Areas at VCSNS do not require a plant-specific aging management program for freeze-thaw, leaching of calcium hydroxide, reaction with aggregates, corrosion of embed ded steel or aggressive chemical attack due to the following:

VCSNS lies within the "moderate" weather ing region of the U. S. (as defined in ASTM C33) and its concrete is not exposed to saturated water conditions near the ground surface which eliminates freeze-thaw con siderations. Additionally, the concrete used at VCSNS is designed with entrained air content of between 4% and 6% in conform ance with ACI-301, and Maintenance Rule 3.0 - AGING MANAGEMENT REVIEW PAGE1 201 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1 801 THAT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Aging Effect /

Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 16 inspections have not identified any degra (cont.)

dation related to freeze-thaw.

Concrete surfaces are not exposed to flow ing water and the in-place concrete is con structed with design requirements in accordance with ACI recommendations (at the time of construction) which produced a dense concrete with low permeability. Spe cific reference to ACI 201.2R-77 is not made since the plant was designed and constructed prior to 1977.

"* Aggregates used in concrete at VCSNS were carefully selected (using local quar ries) to mitigate aggregate reactions, incor porating design specifications in conformance with accepted ACl and ASTM Standards.

a Concrete is not exposed to a below grade A)

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 environment which is considered aggres (cont.)

sive. Additionally, VCSNS used a concrete design mix with maximum water-cement ratio of 0.44 - 0.48 which is specified by ACI Standards to be chemically resistant and watertight. Periodic monitoring of the below grade water chemistry will be con ducted during the period of extended oper ation to demonstrate that the below-grade environment is not aggressive.

17 Groups 1-3, Aging of inacces-Plant specific Yes, if an aggres-Aggressive Chemical Attack becomes sig 5, 7-9; inac-sible concrete sive below-grade nificant to concrete exposed to an aggressive cessible con-areas due to environment exists environment (Chlorides > 500 ppm, Sulfates >

crete aggressive chemi-1500 ppm, and pH < 5.5). Resistance to mild components, cal attack, and acid attack is enhanced by using a dense con such as corrosion of crete with low permeability and a low water-to cement ratio of less than 0.50. These groups of structures at VCSNS use a dense, 3.0 - AIiINI MANAMN I KLVILVV

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3.0 - AGING MANAGE*MIENT RE*VIE:W I"AGE 203* UO" 25

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 exterior walls embedded steel low permeable concrete with a maximum (cont.)

below grade water-to-cement ratio of 0.48, which provides and founda-an acceptable degree of protection against tion aggressive chemical attack. The water chemi cal analysis results confirm that the site groundwater is considered to be non-aggres sive. Therefore, loss of material due to aggressive chemical attack is not an aging effect requiring management for inaccessible concrete components. Periodic monitoring of the below grade water chemistry will be con ducted during the period of extended opera tion to demonstrate that the below-grade environment is not aggressive.

Corrosion of Embedded Steel becomes sig nificant if exposed to an aggressive environ ment (Concrete pH < 11.5 and Chlorides

)

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

> 500 ppm). Corrosion is not significant if the (cont.)

concrete has a low water-to-cement ratio, low permeability, and designed in accordance with ACI Standards (ACI-318 or ACI-349). The design and construction (in accordance with accepted ACI Standards) of these groups of structures at VCSNS prevents corrosion of embedded steel from occurring; therefore, this aging effect does not require management for inaccessible areas.

18 Group 6: all All types of aging Inspection of No ACCESSIBLE AREAS accessible/

effects, including water-control inaccessible loss of material structures or VCSNS Aging Management Programs: Main

concrete, due to abrasion, FERC/US Army tenance Rule Structures Program (Appendix steel, and cavitation, and Corp of Engineers B.1.18) and Service Water Pond Dam Inspec earthen corrosion dam inspection tion Program (Appendix B.1.21) are consis tent with those reviewed and approved in NUREG-1801. In addition, VCSNS 3.0 - AGING MANAGEMENTI REVIEW PAGE 205 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 18 components All types of aging and maintenance No incorporates other programs: Service Water (cont.)

effects, including Structures Survey Monitoring Program loss of material (Appendix B.1.22) and Underwater Inspec due to abrasion, tion Program (SWIS and SWPH) (Appendix cavitation, and B.1.23).

corrosion Freeze-thaw is an aging effect requiring man agement for these structures at VCSNS, since they are exposed to saturated water condi tions. This aging effect is minimized since these structures are designed and constructed to acceptable ACI and ASTM Standards.

Leaching of Calcium Hydroxide from rein forced concrete becomes significant only if the concrete is exposed to flowing water. Resis tance to leaching is enhanced by using a dense concrete with low permeability and well 3].UP

.'*INIJ M&A jMLN*m~k-I IVI VPA E 06OF25 JXI. - AU:lIt.U MANAI.L.t:MI:N I IKtVIt-W PAGE 206 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 18 cured. These structures at VCSNS are (cont.)

designed in accordance with ACI-318 and constructed in accordance with ACI-301 and ASTM Standards, which provides a good quality, dense, low permeability concrete.

Reaction with Aggregates for concrete for these structures at VCSNS are mitigated by carefully designed and selected concrete con stituents; therefore, expansion and cracking due to reaction with aggregates is not an aging effect requiring management.

Corrosion of Embedded Steel becomes sig nificant if exposed to an aggressive environ ment (Concrete pH < 11.5 and Chlorides >

500 ppm). Corrosion is not significant if the concrete has a low water-to-cement ratio, low 3.11 - Rl3IrItJ MPtNI3IVIN I I1VIVV VAb ZU( UP- 

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PAGE-207 OF-252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 18 permeability, and designed in accordance with (cont.)

ACI Standards (ACI-318 or ACI-349). The design and construction (in accordance with accepted ACI Standards) of these structures at VCSNS prevents corrosion of embedded steel from occurring; therefore, this aging effect does not require management for accessible areas.

Aggressive Chemical Attack becomes sig nificant to concrete exposed to an aggressive environment (Chlorides > 500 ppm, Sulfates >

1500 ppm, and pH < 5.5). Resistance to mild acid attack is enhanced by using a dense con crete with low permeability and a low water-to cement ratio of less than 0.50. These struc tures at VCSNS usp q dense, low permeable concrete with a max,,~ um water-to-cement

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 18 ratio of 0.48, which provides an acceptable (cont.)

degree of protection against aggressive chem ical attack. VCSNS is not located in areas exposed to sulfate or chloride attack, nor located near industrial plants whose emis sions would change environmental parame ters and cause degradation to concrete. The water chemical analyses results confirm that the site groundwater, pond and reservoir are considered to be non-aggressive; therefore, loss of material due to aggressive chemical attack is not an aging effect requiring manage ment. Periodic monitoring of the below grade water chemistry will be conducted during the period of extended operation to demonstrate that the below-grade environment is not aggressive.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL a n

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I IVIVV PAGE 210 OF 252 Aging Effect I Aging Further Mechanism Management Evaluation Discussion Program Recommended Settlement of these structures at VCSNS is monitored and managed by the programs:

Service Water Pond Dam Inspection Program (Appendix B.1.21) and Service Water Struc tures Survey Monitoring Program (Appendix B.1.22).

Abrasion and Cavitation due to flowing water are considered insignificant at VCSNS due to the low flow conditions designed for these structures; therefore, aging manage ment is not required.

Corrosion of structural steel components is managed by the programs: Maintenance Rule Structures Program (Appendix B.1.18) and Underwater Inspection Program (SWIS and PAGE 210 OF 252

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 18 SWPH) (Appendix B.1.23).

(cont.)

Earthen Structures are monitored and man aged by the programs: Service Water Pond Dam Inspection Program (Appendix B.1.21) and Service Water Structures Survey Monitor ing Program (Appendix B.1.22).

INACCESSIBLE AREAS Inaccessible Areas at VCSNS do not require a plant-specific aging management program for freeze-thaw, leaching of calcium hydroxide, reaction with aggregates, corrosion of embed ded steel or aggressive chemical attack due to the following:

0 VCSNS lies within the "moderate" 3.0 - AGING MANAGEMENT REVIEW PAGE 211 OF 252 3.0 - AGING MANAGEMENT REVIEW PAGE 211 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 18 weathering region of the U. S. (as defined (cont.)

in ASTM C33). These concrete structures are exposed to saturated water conditions near the ground surface; however, the con crete used at VCSNS is designed with entrained air content of between 4% and 6% in conformance with ACI-301, and Maintenance Rule inspections have not identified any degradation related to freeze-thaw.

Portions of concrete surfaces for these structures are exposed to flowing water; however, the in-place concrete was con structed with design requirements in accor dance with ACI recommendations at the time of construction which produce a dense concrete with low permeability. Spe cific reference to ACl 201.2R-77 is not J.U m mIN I~V~WP GE21 F

5 3.0. - AGING~ MANAG:MIN I RE-VIE:W PAGE 212 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 18 made since the plant was designed and (cont.)

constructed prior to 1977.

Aggregates used in concrete at VCSNS were carefully selected (using local quar ries) to mitigate aggregate reactions, incor porating design specifications in conformance with accepted ACI and ASTM Standards.

Concrete is not exposed to a below grade environment which is considered aggres sive. Additionally, VCSNS used a concrete design mix with maximum water-cement ratio of 0.44 - 0.48 which is specified by ACI Standards to be chemically resistant and watertight. Periodic monitoring of the below grade water chemistry will be con ducted during the period of extended oper ation to demonstrate that the below-grade 3.U - pIjIr4I., 

I E¶VIVV r#ij L13 yr ii 3.0 - AGING* MPA I*I ERRE-MI I REVIEWV B

P"AGEt: 213 UO" 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 18 environment is not aggressive.

',.;ont.)

19 Group 5: lin-Crack initiation Water chemistry No VCSNS Aging Management Programs:

ers and growth due to and monitoring of Chemistry Program (Appendix B.1.4) and SCC; loss of spent fuel pool Maintenance Rule Structures Program material due to water level (Appendix B.1.18) are consistent with those crevice corrosion reviewed and approved in NUREG-1801.

20 Groups 1-3, Cracking due to Masonry wall No Masonry walls at VCSNS are inspected in 5, 6: all restraint, shrink-accordance with the Maintenance Rule Struc masonry age, creep, and tures Program (Appendix B.1.18).

block walls aggressive envi ronment No masonry walls are used in nuclear safety related structures at VCSNS.

21 Groups 1-3, Cracks, distor-Structures moni-No, if within the VCSNS Aging Management Program: Mainte 5, 7-9: foun-tion, and toring scope of the appli-nance Rule Structures Program (Appendix dation increases in com-cant's structures B.1.18) is consistent with those reviewed and ponent stress monitoring approved in NUREG-1801.

3.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 21 level due to settle-program (cont.)

ment Concrete Tanks are not used at VCSNS; therefore, aging management is not required.

22 Groups 1-3, Reduction in foun-Structures moni-No, if within the The VCSNS structure foundations do not use 5-9: founda-dation strength toring scope of the appli-porous concrete; therefore, aging manage tion due to erosion of cant's structures ment is not required.

porous concrete monitoring pro subfoundation gram Concrete Tanks are not used at VCSNS; therefore, aging management is not required.

23 Groups 1-5:

Reduction in Plant specific Yes, for any por-The VCSNS structural concrete elements are concrete strength and mod-tions of concrete not exposed to temperatures which exceed ulus due to ele-that exceed speci-the thresholds for degradation; therefore, vated temperature fled temperature reduction of strength and modulus due to ele limits vated temperatures are not aging effects requiring management.

24 Group 7, 8:

Crack initiation Plant specific Yes Group 7 (Concrete Tanks) are not used at liners and growth due to VCSNS; therefore, aging management is not

3.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 SCC; loss of required.

(cont.)

material due to crevice corrosion Note that the combinations of romponents, materials, and environments ied in NUREG-1801 for Group 8 (Steel ranks) are not applicable to VCSNS; therefore, aging management is not required.

25 All Groups:

Aging of compo-Structures moni-No, if within the VCSNS Aging Management Programs: 10 support mem-nent supports toring scope of the appli-CFR 50 Appendix J General Visual Inspection bers: anchor cant's structures (Appendix B.1.11) and Maintenance Rule bolts, con-monitoring pro-Structures Program (Appendix B.1.18) are crete sur-gram consistent with those reviewed and approved rounding in NUREG-1801.

anchor bolts, welds, grout Concrete structures and concrete components pad, bolted can be subjected to cyclic loading and

- AIN

MANALiMN I KVIW PAGE 216 OF 252 J.g

- AUINU MANAU,:E:ME"NT IRE:VIE-W 8

PAGE 216 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 connections, therefore, can be subjected to fatigue degra (cont.)

etc.

dation. However, concrete components have good fatigue strength properties for hundreds or thousands or cycles of below yield load application (high cycle low-level loads). For components that may be subjected to vibra tory or cyclic loading, proper design eliminates or compensates for vibration and cyclic load ing. In addition, vibration characteristically leads to cracking in a short period of time, on the order of hours to days of operation. For example, a component with 1 Hertz vibratory load will be subjected to 107 cycles in four months of service, so that failure, should it occur, is probable early in life for vibratory stresses above the endurance limit. Because this time period is short when compared to the overall plant operational life, any cracking 3.0 - AIN MANALMN I KVIW rAI. i i UP-LL 3.0 - AGING MANAGE1ME:NT RE*IVIE:W rAUIL Z1f UP-ZOZ

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 25 would be identified and corrected to prevent (cont.)

recurrence long before the period of extended operation. This type of degradation is limited to a small set of components and is corrected as discovered with inspections of similar loca tions and configurations to ensure the event is location specific or a one-time event.

The potential for cracking induced by other cyclic loads, such as thermal cycling of the supported system, is implicitly considered in structural steel design through the specifica tion of conservative design allowable stresses that account for a minimum of 105 load cycles.

VCSNS concrete components are designed in accordance with accepted ACI Standards and have good low cycle fatigue properties. Plant

3.

AI3N M.ANAI RVI.W.PAGE218.OF.25 3.0 - AGING MANAGEMENT REVIEW PAGE 218 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 experience did not identify any concrete deg (cont.)

radation due to service-induced loads. There fore, cracking due to fatigue is not an aging effect requiring management for concrete components.

26 Groups B1.1, Cumulative TLAA evaluated in Yes, TLAA TLAA is not applicable since a CLB fatigue B1.2, and fatigue damage accordance with analyses does not exist for these component B1.3: sup-(CLB fatigue anal-10 CFR 54.21(c) types at VCSNS.

port mem-ysis exists) bers: anchor bolts, and welds 27 All Groups:

Loss of material Boric acid corro-No VCSNS Aging Management Programs: Boric support mem-due to boric acid sion Acid Corrosion Surveillances (Appendix bers: anchor corrosion B.1.2), 10 CFR 50 Appendix J General Visual bolts and Inspection (Appendix B.1.11) and Mainte welds nance Rule Structures Program J.U - ALA*NU. MANIM*:UMI::M I IKI:VIr:;W I"AtuI: Liu* U" z*)z

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 27 (Appendix B.1.18) are consistent with those (cont.)

reviewed and approved in NUREG-1801.

28 Groups B1.1, Loss of material ISl No VCSNS Aging Management Programs: 10 B1.2, and due to environ-CFR 50 Appendix J General Visual Inspection B1.3: sup-mental corrosion; (Appendix B.1.11) and Maintenance Rule port mem-loss of mechani-Structures Program (Appendix B.1.18) are bers: anchor cal function due to consistent with those reviewed and approved bolts, welds, corrosion, distor-in NUREG-1801.

spring hang-tion, dirt, over ers, guides, load, etc.

Loss of mechanical function, distortion, dirt, stops, and overload, fatigue due to vibratory and cyclic vibration iso-thermal loads; and elastomer hardening are lators not considered as aging effects but rather design issues.

29 Groups B1.1:

Crack initiation Bolting integrity No Bolting integrity at VCSNS is inspected in high strength and growth due to accordance with the ISI Program (IWF):

low-alloy SCC ASME Section Xl ISI Program - IWF 3.U - I4IIIlmlA' ikl ml R 'I.~i"IL I' KlVIliVPA E

20OF25 al.U - AWMI7,, MANAUIMMMN I iKl:Vlr-VV PAGE 220 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 29 bolts (Appendix B.1.13).

(cont.)

Industry experience has shown that high strength bolts (bolts with tensile strength greater than 150 ksi) installed in Class 1 com ponent supports could be susceptible to SCC in humid environments like the Reactor Build ing. The key factors necessary for SCC include high-strength materials, moist environ ments, and a high level of sustained tensile stress. Operating experience also shows that improperly heat-treated anchor bolts have been susceptible to SCC, especially when under a high preload (full preload of 70% of ultimate strength). Anchor bolts are also exposed to concrete where chlorides can leach-out and attack the intergranular struc ture of the bolts over time. Therefore based on 3.0 - AGING MANAGEMENT REVIEW PAGE 221 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 29 industry experience, stress corrosion cracking (cont.)

is a potential aging effect for the ASTM A490 high strength anchor bolts used in the Class 1 component supports at VCSNS.

However, SCC of high strength anchor bolts should also be considered as a negligible aging effect at VCSNS since the following conditions apply:

"* ASTM A490 anchor bolt material is prop erly heat-treated by conforming to ASTM Specification A490 through a certified mill test report.

"* Anchor bolts are tightened snug-tight as defined by AISC; therefore, for bolts greater than 1" in diameter, a significant preload (in the order of 70% of ultimate S

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-1:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 29 strength) is not practical to develop.

(cont.)

Anchor bolts do not have a high level of sustained tensile stress as evidenced by lower faulted condition design loads due to elimination of dynamic effects subsequent to postulated High Energy Line Break (HELB) of the Reactor Coolant System pri mary coolant piping.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.5.3.3 Aging Management Evaluations That Are Different From Or Not Addressed In NUREG-1801 Table 3.5-2 contains Containment, Structures and Component Supports aging management review results that are not specifically addressed in NUREG-1801. This table includes com ponent types, materials, environments and aging effects requiring management, along with the programs and activities for managing aging.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-2:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1 801 BUT ARE RELIED ON FOR LICENSE RENEWAL AMR Component Material Environment Aging Effect /

Program Activity Discussion Item Type Mechanism 1

Battery Carbon Steel Internal Loss of Material Battery Rack Battery Racks are not Racks (General Corro-Inspection Pro-explicitly identified in GALL sion) gram as a structural component type. VCSNS uses a Bat tery Rack Inspection Pro gram (Appendix B.1.14) to inspect for corrosion or other physical damage to ensure integrity, thus pro viding acceptable aging management. This is a plant specific program which is not addressed in the GALL.

2 Caissons Concrete Below Grade None Not Applicable Reinforced Concrete Cais (Founda-sons are used to support tions) the foundations of the Inter mediate, Diesel Generator, and Fuel Handling 3.U - ALiINLi MANAbMLN I NVIW PA3E 225 OF 252 3.0 - AGIlNG MANAGE:ME:NT! RE:VIE:W PAGE 225 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-2:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

Buildings at VCSNS. Con (cont.)

crete Caissons are inacces sible since they are completely surrounded by backfill (beneath the struc ture foundations) and embedded in underlying bedrock. Aging manage ment programs are not required since the below grade environment is con sidered to be non-aggres sive. Periodic monitoring of the below grade water chemistry will be conducted during the period of extended operation to dem onstrate that the below grade environment is not

,..U - RUI!,=NU MANA~i-MI-N I IKtVIL'W PAGE 226 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-2:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

aggressive. Settlement is (cont.)

not considered significant since the caissons are structurally embedded within the underlying bed rock.

3 Flood Barri-Elastomers Internal, Exter-Cracking, Change Fire Protection The VCSNS Flood Barrier ers nal (Below in Material Prop-Program, Mainte-Inspection Program Grade) erty nance Rule Struc-(Appendix B.1.17) is not tures Program evaluated in the GALL and is plant specific. Flood bar rier inspections are per formed as part of the Fire Protection Program (Appendix B.1.5) and Maintenance Rule Struc tures Program (Appendix B.1.18).

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- ALiNj MANAItMIN I ICIVIlVV P"AGE1: 227 OF 25*2

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-2:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

Lubrite Plates Lubricant Internal None Not Applicable Lubrite plates have been (Class 1 Pipe used in a few Class 1 pipe Hanger Sup-hanger supports at VCSNS.

ports)

Lubrite plates are not used in the reactor pressure ves sel support shoes as described in the GALL.

Lubrite materials for nuclear applications are designed to resist deforma tion, have a low coefficient of friction, resist softening at elevated temperatures, resist corrosion, withstand high intensities of radiation, and will not score or mar; therefore, they are not sus ceptible to aging effects requiring management.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-2:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

Pressure Carbon Steel Internal, External Loss of Material Pressure Door The VCSNS Pressure Door Doors (General Corro-Inspection Pro-Inspection Program sion) gram, Fire Protec-(Appendix B.1.20) is not tion Program evaluated in the GALL and is plant specific. Pressure door inspections are per formed as part of the Pres sure Door Inspection and Fire Protection Programs.

6 RHR and Carbon Steel Below Grade Loss of Material Containment ISI VCSNS has identified MIC Spray Isola-(Microbiologically Program - IWE/

as an aging effect requiring tion Cham-Induced Corro-IWL management for these ber Valve sion [MIC])

component types. MIC has Guard Pipes not been evaluated within the GALL. The Contain ment ISI Program (IWE) was effective in identifica tion of this aging effect and 3.U - AIiINU MANALMLN I ICVILW PAGE Z29 OF Z2 3.0 - AGING MANAGE=ME=NT REVIE=W PAGE 229 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-2:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

will be used in the future to (cont.)

provide acceptable aging management.

7 Service Concrete Raw Water Loss of Material Underwater Underwater inspections are Water Intake (Flowing)

(Abrasion, Cavita-Inspection Pro-not evaluated in the GALL.

Structure tion) gram (SWIS &

VCSNS has a plant specific (SWIS)

SWPH)

Underwater Inspection Pro gram (SWIS and SWPH)

(Appendix B.1.23) as part of the CLB which monitors the SWIS for settlement cracking, abrasion and cav itation. These underwater visual inspections are con ducted every 5 years and provide for acceptable aging management.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-2:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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

Service Carbon Steel Raw Water Loss of Material Maintenance Rule For Water-Control Struc Water Pump-(General Corro-Structures Pro-tures, the GALL only identi house sion, Pitting, MIC) gram, Underwater fies corrosion as an aging (SWPH)

Inspection Pro-mechanism and identifies gram (SWIS &

RG 1.127 (XI.S7) as the SWPH) acceptable AMP. VCSNS has identified additional aging effects for this com ponent type and material, and uses the Maintenance Rule Structures Program (Appendix B.1.18) and Underwater Inspection Pro gram (SWIS and SWPH)

(Appendix B.1.23) as the primary AMPs for accept able aging management.

VCSNS uses the RG 1.127 Service Water Pond Dam L

3.0 - AGIlNG MANAGEiME=NT REVIE=W PAGE 231 OF 252

LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 501395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-2:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS THAT ARE DIFFERENT FROM OR NOT ADDRESSED IN NUREG-1801 BUT ARE RELIED ON FOR LICENSE RENEWAL Service Water Pump house (SWPH), Ser vice Water Intake Struc ture (SWIS)

Material Environment Aging Effect I Mechanism Program Activity Discussion Inspection Program (Appendix B.1.21) inspec tions only for supplemen tary review.

Concrete Raw Water Earthen Backfill Cracking (Settle ment)

Maintenance Rule Structures Pro gram, Underwater Inspection Pro gram (SWIS &

SWPH), Service Water Structures Survey Monitoring Program.

For Water-Control Struc tures, the GALL identifies RG 1.127 (XI.S7) as the acceptable AMP. VCSNS uses the Maintennr,-e Rule Structures P, (Appendix B. i.,,

Under water Inspection Program (SWIS and SWPH)

(Appendix B.1.23) and Service Water Structures Survey Monitoring Pro gram (Appendix B.1.22) as the primary AMPs for acceptable aging U

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C LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 Table 3.5-2:

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STATION CONTAINMENT, OTHER STRUCTURES AND COMPONENT SUPPORTS 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 9

management. VCSNS uses (cont.)

the RG 1.127 Service Water Pond Dam Inspec tion Program (Appendix B.1.21) inspections only for supplementary review.

10 Service Earthen External Loss of Material Service Water For Water-Control Struc Water Pond (Erosion, seep-Pond Dam Inspec-tures, the GALL identifies Dams, North age, piping);

tion Program (RG RG 1.127 (XI.S7) as the Berm Cracking (Settle-1.127), Mainte-acceptable AMP. VCSNS ment) nance Rule Struc-uses the Maintenance Rule tures Program Structures Program (Appendix B.1.18) to sup plement the RG 1.127 Ser vice Water Pond Dam Inspection Program (Appendix B.1.21) inspec tions for acceptable aging management.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.

5.4 REFERENCES

.0 - AUNI.

INGMANAGMEINT REVIEW 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.

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

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. 501395 FACILITY OPERATING LICENSE NO. NPF-12 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS 3.6.1 ELECTRIC DESCRIPTION VCSNS has performed an aging management review on the following electrical/l&C com modity groups:

• Non-EQ Insulated Cables

• Non-EQ Connectors

• Non-EQ Splices

• Non-EQ Electrical Penetration Assemblies

• Non-EQ Terminal Blocks High Voltage Electrical Switchyard Bus High Voltage Transmission Conductors and Connections High Voltage Insulators 3.6.1.1 Non-EQ Insulated Cables Non-EQ insulated cables include power cables, control cables, and instrument cables. For VCSNS, these applications are defined to be at the following voltage levels:

Low Voltage Cables: 480 VAC, 240/120 VAC, 125 VDC (and less)

Medium Voltage Cables: 7.2 kV High Voltage Cables: Greater Than 7.2 kV (none in scope)

In order to facilitate the review of the cables at VCSNS, the cables are placed into two cate gories: (1) power cable and (2) I&C cable. The power cable category includes all 7.2 kV cables and the 480 VAC power cables. The I&C category includes the 480 VAC control cable, all 240/120 VAC cable, and all DC cables (125 VDC and less). Depending upon their application, cables utilized as switchboard wire are placed into one of these two categories, typically as I&C cable. It should be noted at this time that VCSNS purchased nearly all of its electric power cable, control cable, and instrument cable (with the exception of certain com munication cables, cables ordered for specific non-safety applications, and special cables ordered subsequently for specific modifications) to 1 OCFR50.49 Harsh EQ standards.

The worst case cable insulation possible in application used in license renewal is polyethyl ene with a 60 year service limiting temperature of 131'F. The non-EQ insulated cables will be subject to an aging management program as described in Table 3.6.1.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.6.1.2 Non-EQ Electrical Connectors Cable connections are used to connect the cable conductors with other cables or with a vari ety of electrical devices (e.g., instruments, motors, etc.). The various types of insulated cable connections (or terminations) are identified in the Cable Aging Management Guideline (AMG) [Section 3.3.2 of Reference 3.6-1]. The Cable AMG describes the cable termination grouping as follows:

"* Compression connectors

"* Fusion connectors

"* Plug-in / Multi-pin connectors A variety of plant documents were reviewed to identify electrical connectors in use at VCSNS, including procurement records, plant drawings, EQ binders, and plant maintenance documents. This review provided strong reasonable assurance that all types of connectors have been identified and that the bounding materials for the connectors at VCSNS have also been identified. Connectors are included in the Non-EQ Insulated Cables and Connections Inspection Program.

3.6.1.3 Non-EQ Electrical Splices Many of the splices at VCSNS are delineated in a calculation which identifies all safety related (Class 1 E) 7.2 kV and 480V splices in the plant. The BOM table for the electric cables lists common splice and tape materials ordered for VCSNS during plant construction.

The identification of VCSNS splices included a review of EQ documentation, procurement records, and design basis documents. This review provided strong reasonable assurance that all splice types and materials applicable to VCSNS (which may be subject to aging man agement review) have been identified. Non-EQ splices are included in the Non-EQ Insulated Cables and Connections Inspection Program.

3.6.1.4 Non-EQ Electrical Penetration Assemblies Electrical penetration assemblies are utilized to carry electrical circuits through the Reactor Building containment wall while maintaining pressure-tight integrity. They provide the electri cal continuity of the circuit and the pressure boundary for containment integrity. The scope of the review in this report applies only to the electrical function of the penetration assemblies.

The pressure-retaining function of the penetration assemblies is addressed in Section 2.4 of this application for the Reactor Building.

All the electrical penetrations at VCSNS have been listed in the VCSNS EQ program, whether or not they carry Class 1 E circuits. The non-Class 1 E electrical penetrations are classified as category "B1, B2" components with respect to EQ (i.e., they must not fail and DAI.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 prevent the accomplishment of a NSR function) and are administratively included in the EQ program in order to credit the portion of the EQ testing which justifies the pressure-retaining function of the penetrations. VCSNS utilizes D.G. O'Brien electrical penetration for its non Class 1E applications.

The D.G. O'Brien electrical penetration assemblies are subject to aging management review.

This review provides for their identification and also for the listing of the organic materials found during the review. Because there are D.G. O'Brien electrical penetration assemblies that are part of the VCSNS EQ program and have been evaluated in detail for that purpose, there is reasonable assurance that all their organic materials have been identified and prop erly evaluated with respect to aging for the non-EQ installations. An additional review has shown Non-EQ Electrical Penetrations at VCSNS to be located in areas inside and outside of the RB which have less severe environments, that are clearly enveloped by material prop erties and aging testing and evaluation done through the manufacturer. The Non-EQ Electri cal Penetrations at VCSNS are not included in the Non-EQ Insulated Cables and Connections Inspection Program. The evaluation of the Non-EQ Electrical Penetrations at VCSNS is further documented in Table 3.6-2 Item 2.

3.6.1.5 Non-EQ Terminal Blocks A terminal block consists of an insulating base with fixed metallic points for landing wires (conductors) or for connecting terminal rings (lugs). Terminal blocks are typically installed in an enclosure such as a control board, MCC, motor, terminal box, or a panel.

A complete list of the specific terminal blocks used at VCSNS does not exist in one file or location; however, a review of the Bills of Material and other plant documents (EQ files, etc.)

for general electrical equipment revealed that the following suppliers have terminal blocks in use at VCSNS: GE, Kulka, Marathon, States, and Weidmuller.

From the Cable AMG [Reference 3.6-1], the most common materials used in the insulating base are phenolic, melamine resin, and nylon. The material with the least thermal and radia tion resistance is nylon. Because there is no single document that lists all terminal block manufacturers, materials, and locations for VCSNS, nylon was chosen as the bounding material for the evaluation of the terminal blocks, due to its limited radiation resistance. By choosing nylon as the limiting material with respect to the plant environmental conditions, there is reasonable assurance that the terminal blocks at VCSNS are properly evaluated with respect to aging. Non-EQ terminal blocks are included, as appropriate, in the Non-EQ Insulated Cables and Connections Inspection Program.

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LICENSE RENEWAL APPLICATION VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 FACILITY OPERATING LICENSE NO. NPF-12 3.6.1.6 High Voltage Electrical Switchyard Bus High Voltage (HV) electrical switchyard bus is uninsulated, unenclosed, rigid electrical con ductor used in switchyards and switching stations to connect two or more elements of an electrical power circuit such as active disconnect switches and passive transmission con ductors. The review of switchyard bus included the bus itself as well as the hardware used to secure the bus to high-voltage insulators.The in scope switchyard bus at VCSNS is con structed of aluminum tubing or copper rods, and supported on station post insulators with aluminum cast fastening hardware.

For the ambient environmental conditions at VCSNS, no significant aging effects have been identified that would cause a loss of function for the extended period of operation. The potential effects of surface oxidation and vibration are not considered significant for the VCSNS installation. No aging management program for HV electrical switchyard bus is required.

3.6.1.7 High Voltage Transmission Conductors and Connections Transmission conductors are uninsulated, stranded electrical cables used in switchyards, switching stations and transmission lines to connect two or more elements of an electrical power circuit such as active disconnect switches, power circuit breakers and transformers to passive switchyard bus. The review of transmission conductors included the transmission conductors and the hardware used to secure the conductors to a high-voltage insulator or to switchyard bus. Transmission conductors are supported by passive high-voltage strain or suspension insulators. Transmission conductors and connection hardware at VCSNS are made of aluminum reinforced with galvanized steel.

For the ambient environmental conditions at VCSNS, no significant aging effects related to conductor corrosion or wind loading vibration or sway on connections have been identified that would cause a loss of function for the extended period of operation. No aging manage ment program for HV transmission conductors and connections is required.

3.6.1.8 High Voltage Insulators HV switchyard post insulators and strain or suspension insulators as typically used on trans mission towers are insulating materials in a form designed to (a) support a conductor physi cally and (b) separate the conductor electrically from another conductor or object. The insulators evaluated for license renewal are those used to support and insulate high voltage electrical components in switchyards, switching stations and transmissions such as trans mission conductors and switchyard bus. HV insulators serve as an intermediate support between a supporting structure (such as a transmission tower or support pedestal) and the an r

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For the ambient environmental conditions at VCSNS, no significant aging effects related to airborne contaminants or mechanical wear have been identified that would cause a loss of function for the extended period of operation. No aging management program for HV insula tors is required.

3.6.2 AGING MANAGEMENT REVIEW 3.6.2.1 Methodology The AMR methodology for the electrical discipline for VCSNS is summarized in the following points:

Evaluation of the electrical component commodity groups (subject to AMR) to identify the organic materials subject to age-related degradation Identification and evaluation of the 60-year service-limiting environmental param eters for these organic materials Identification and evaluation of the aging mechanisms and effects to determine which require review Identification and evaluation of the service conditions (i.e., the operating environ ments and locations) for the electrical component commodity groups Evaluation of the industry and plant-specific operating experience for the electrical component commodity groups

• Aging management program evaluation (following NUREG-1 801)

Demonstration of aging management The review of the VCSNS electrical component commodity groups with respect to aging mechanisms and effects was performed based upon the guidance of various industry docu ments, primarily SAND96-0344, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Cable and Terminations [Reference 3.6-1]. This document pro vides detailed materials analysis for cable and termination materials exposed to nuclear power plant environments. It also provides guidance for performing aging management reviews pursuant to 10 CFR 54.

The methodology used for the aging management review of the electrical commodity groups employs the "Plant Spaces" approach in which the plant is segregated into areas (or spaces) where common bounding environmental parameters can be assigned. The VCSNS plant operating environments are delineated as "Environmental Zones." Each bounding environ-i~

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The intended functions of the electrical component commodity groups under review are as follows:

To electrically connect or insulate two sections of an electrical circuit and/or to pro vide for continuity or insulation of electrical circuits.

The electrical penetration assemblies also have a structural function to provide a leak-tight barrier for containment isolation; this is evaluated in Section 2.4.1.3 of this application.

3.6.2.2 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) interviews with Systems Engi neers. No additional aging effects requiring management were identi fied 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 Section 3.6.2.1.

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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3.6.3.2 Further Evaluation Of Aging Management As Recommended By NUREG-1801 Further evaluation of aging management as recommended by the NUREG-1 801 has been incorporated into the "Discussion" column of Table 3.6-1.

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Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended Electrical Degradation due Environmental Yes, TLAA The TLAA for electrical equipment in the EQ equipment to various aging Qualification of Program is discussed in Section 4.4 of this subject to 10 mechanisms Electrical equip-application.

CFR 50.49 ment environmen tal qualifica tion (EQ) requirements 2

Electrical Embrittlement, Aging manage-No VCSNS applies the Non-EQ Insulated Cables cables and cracking, melting, ment program for and Connections Inspection Program (Appen connections discoloration, electrical cables dix B.2.9) to these cables and connections not subject to swelling, or loss of and connections even though the environmental conditions 10 CFR dielectric strength not subject to 10 within the plant are not severe enough to 50.49 EQ leading to CFR 50.49 EQ show that the aging effects associated with requirements reduced insulation requirements elevated temperature are significant for the resistance (IR);

cable and connector/termination insulation electrical failure materials.

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ELECTRICAL AND INSTRUMENTATION AND CONTROL COMPONENTS 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 2

thermal/thermoxi (cont.)

dative degrada tion of organics; radiolysis and photolysis (ultravi olet [UV] sensi tive materials only) of organics; radiation-induced oxidation; mois ture intrusion 3

Electrical Embrittlement, Aging manage-No VCSNS applies the Non-EQ Insulated Cables cables used cracking, melting, ment program for and Connections Inspection Program (Appen in instrumen-discoloration, Electrical Cables dix B.2.9) to these cables and connections tation circuits swelling, or loss of and Connections even though the environmental conditions not subject to dielectric strength not subject to 10 within the plant are not severe enough to 10 CFR leading to CFR 50.49 EQ show that the aging effects associated with 50.49 EQ reduced IR; requirements elevated temperature are significant for the J.U -.MANiN M.NRIJtIVIIIN I Ei'VIIVY

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Aging Further Item Group Mechanism Management Evaluation Discussion Program Recommended 3

requirements electrical failure insulation materials.

(cont.)

that are sen-caused by ther sitive to mal/ thermoxida-Additional information is provided in Table 3.6 reduction in tive degradation 2 Item 1.

conductor of organics; radia insulation tion-induced oxi resistance dation; moisture intrusion 4

Inaccessible Formation of Aging manage-No The aging management review for medium medium-volt-water trees; local-ment program for voltage cables exposed to moisture and volt age (2kV to ized damage inaccessible age stressors concluded that aging manage 15kV) cables leading to electri-medium-voltage ment at VCSNS is not required. No instances (e.g.,

cal failure (break-cables not subject of power cable failure at VCSNS due to mois installed in down of to 10 CFR 50.49 ture intrusion were found.

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50.49 EQ (cont.)

requirements 5

Electrical Corrosion of con-Boric acid corro-No With regard to NUREG-1 801 Chapter VI item connectors nector contact sion A.2.1, the aging management for electrical not subject to surfaces caused connectors which may experience boric acid 10 CFR by intrusion of corrosion will be addressed by the Boric Acid 50.49 EQ borated water Corrosion Surveillance (Appendix B.1.2) pro requirements gram at VCSNS. A separate electrical pro that are gram will not be developed. The procedures exposed to which comprise the VCSNS Boric Acid Corro borated water sion Surveillance program are sufficient to leakage address the NUREG-1 801 standard.

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Program Activity Discussion Item Type Mechanism 1

Electrical Various organic Maximum ambi-Embrittlement, Non-EQ Insulated NUREG-1801 recom cables used insulating materi-ent temperature cracking, melting, Cables and Con-mends an aging manage in instrumen-als.

potential is 131°F discoloration, nections Inspec-ment program specifically tation circuits swelling, or loss of tion Program for cables with sensitive, not subject to Maximum 60 dielectric strength low-level signals. VCSNS 10 CFR year gamma leading to applies the Non-EQ Insu 50.49 EQ radiation poten-reduced IR; elec-lated Cables and Connec requirements tial is 1.95E10 trical failure tions Inspection Program that are sen-Rads caused by ther-(Appendix B.2.9) (Table sitive to mal/thermoxida-3.6-1 Item 2). The visual reduction in tive degradation inspection of instrument as conductor of organics; radia-well as power and control insulation tion induced oxi-cables is considered a bet resistance dation; moisture ter means to identify age intrusion, related degradation due to localized ambient thermally and radiologically induced stress prior to significant a a a nh...

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loss of insulation resis (cont.)

tance.

2 Non-EQ Elec-Polysulfone insu-Maximum ambi-Embrittlement, None required.

Non-EQ Electrical Penetra trical Pene-lation, Silicon ent temperature cracking, melting, tions at VCSNS are located tration Rubber o-rings, is 121 *F for a discoloration, in areas inside and outside Assemblies Fiberglass short time in Env.

swelling, or loss of of the RB in environments epoxy, Neo-Zones PAA-03 dielectric strength which are clearly enveloped prene gaskets, and PAI-02.

leading to by material properties and Molycote thread reduced insulation aging testing and evalua sealant, Polycar-Maximum 60 resistance; electri-tion done through the man bonate view port.

year gamma cal failure caused ufacturer. Cable that utilize radiation is by thermal/Ther-these penetrations are 3.0E06 Rads in moxidative degra-addressed in Table 3.6-1 Env. Zone RB-dation of organics; Item 2.

05.

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organics; radia (cont.)

tion-induced oxi dation; moisture intrusion 3

Electrical Aluminum, cop-Outdoor environ-Change in mate-None For the ambient environ Switchyard per ment in air and rial properties mental conditions at Bus rainwater leading to VCSNS, no aging effects increased resis-have been identified that tance and heat-could cause a loss of func ing due to tion. No aging management oxidation. Also is required.

cracking due to vibration.

4 High Voltage Aluminum, Steel Outdoor environ-Loss of conductor None For the ambient environ Transmis-ment in air and strength due to mental condition at VCSNS, sion Conduc-rainwater corrosion. Also no significant aging effects tors and wear or fatigue related to corrosion or wind 3.0 - AIN

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SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ELECTRICAL AND INSTRUMENTATION AND CONTROL COMPONENTS 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 4

Connections Aluminum, Steel Outdoor environ-due to wind load-loading vibration or sway (cont.)

ment in air and ing vibration or for conductors or connec rainwater sway.

tions have been identified that could cause a loss of function. No aging manage ment program is required.

5 High Voltage Porcelain, metal Outdoor environ-Surface contami-None For the ambient environ Insulators cap or pin, ment in air and nation or cracking mental conditions at cement rainwater due to airborne VCSNS, no significant contaminants.

aging effects related to air Also loss of mate-borne contaminants or rial due to mechanical wear have mechanical wear.

been identified that could cause a loss of function. No aging management pro gram is required.

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6.4 REFERENCES

3.6-1 U. S. Department of Energy Report SAND 96-0344, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Cable and Termi nations, September 1996.

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