Text

Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction
	ML17277B519
Person / Time
Site:	Seabrook
Issue date:	10/03/2017
From:	Mccartney E; NextEra Energy Seabrook
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML17277A814	List: SBK-L-17155, Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction;
References
	SBK-L-17155
	Download: ML17277B519 (263)
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Enclosure 1 to this Letter Contains Proprietary Information Withhold Enclosure 1 from Public Disclosure in Accordance with 10 CFR 2.390 NFXTera EN ERGY ~

SEABROOK October 03, 2017 10 CFR 54 Docket No. 50-443 SBK-L-17155 U. S. Nuclear Regu latory Comm ission Attn: Document Control Desk W ash ington, DC 20555-0001 Seabrook Station Supplement 58 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Building Deformation Analyses Related To Concrete Alkali-Silica Reaction

References:

1. NextEra Energy Seabrook LLC, letter SBK-L-10077, "Seabrook Station Application for Renewed Operating License," May 25, 2010 (Accession Number ML101590099).

2. NRC, "Request for Additional Information for the Review of the Seabrook Station License Renewal Application (CAC NO. ME4028)," March 29, 2017 (Accession Number ML17088A614).

In Reference 1, NextEra Energy Seabrook , LLC (NextEra Energy Seabrook) subm itted an app lication for a renewed facility operating license for Seabrook Station Unit 1 in accordance with the Code of Federal Regulations, Title 10, Parts 50, 51, and 54.

In Reference 2, the NRC requested additional information to complete the review of the appl ication related to Alkali-Silica Reaction (ASR) and Building Deformation Monitoring Programs. provides NextEra Energy Seabrook's response to the NRC's Request for Additional Information (RAI) concerning the Alkali-Silica Reaction and Bui lding Deformation Monitoring Programs (Reference 2).

NextEra Energy Seabrook, LLC P.O. Box 300, Lafayette Road, Seabrook, NH 03874

U.S. Nuclear Regulatory Commission SBK-L- 171 55/ Page 2 provides the revised License Renewal Application, Section 3.5 , as referenced in the response to RAI 3.5-A 1-1: A MR within Enclosure 1. to this letter contains information proprietary to NextEra Energy Seabrook.

This letter is supported by an affidavit (Enclosure 4), setting forth the basis on which the information in Enclosure 1 may be withheld from public disclosure by the Comm ission and add ressing the cons iderations listed in 10 CFR 2.390(b)(4). Accordingly, it is respectfully requested that the information which is proprietary be withheld from public disclosure in accordance with 10 CFR 2.390. A non-proprietary vers ion of this letter and revised Alkali-S ilica Reaction Monitoring Prog ram Aging Management Plan A.2.1.31 .A will be subm itted under separate cover by November 3, 2017.

This letter co ntains two revi sed Comm itments (45 and 66). Enclosure 3 provides the revised LRA Appendix A - Updated Fina l Safety Analysis Report Supplement Tab le A.3, License Renewal Comm itment List.

If there are any questions or add itional information is needed , please co ntact Mr.

Edward J. Carley, Engineering Supervi sor - License Renewal, at (603) 773-7957 .

If you have any questions reg arding this correspondence, please contact Mr. Kenneth Browne, Licensing Manager, at (603) 773-7932.

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

Executed on October 3 yi-t , 201 7.

Sincerely, NextEra Energy Seabrook, LLC hem Region

U.S. Nuclear Regulatory Commission SBK-L-17155/ Page 3

Enclosures:

- Supp lement 58 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Bu ilding Deformation Analyses Re lated To Concrete Alkali-Silica Reaction (Proprietary) - Seabrook Station License Renewal Application, Section 3.5 - LRA Appendix A - Final Safety Report Supplement Tab le A.3, License Renewal Commitment List Updated to Reflect Changes to Date - NextEra Energy Seabrook, Application for Withholding Proprietary Information from Public Disclosure and Affidavit cc: D. H. Dorman NRC Region I Administrator J.C. Poole NRC Project Manager P. C. Cataldo NRC Senior Resident Inspector L. M. James NRC Project Manager, License Renewal Mr. Perry Plummer Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 perry.plummer@dos.nh.gov Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 John.Giarrusso@massmail.state .ma. us

Enclosure 2 to SBK-L-17155 Seabrook Station License Renewa l Application, Section 3.5

U.S. Nuclear Regulatory Commission SBK-L- 171 55 I Enclosure 2/ Page 2 Table 3.5. 1 Summary Of Ag ing Management Evaluations for Structures and Structural Components Item Aging Management Further Evaluation Component Aging Effect I Mechanism Discussion Number Program Recommended

PW R Concrete (Reinforced and Prestressed) and Steel Containments 3.5.1-1 Concrete elements: Aging of accessible and ISi (IWL) and for inaccessible concrete, an Yes. plant-specific, if Seabrook manages walls, dome , basemat, inaccessible concrete areas examination of representative samples of environment is aggressive accessible an d inaccessible ring girder, buttresses. due to aggressive chemical below-grade concrete and periodic monitoring concrete components due to containment (as attack, and corrosion of of groundwater if environment is non-corros ion of embedded steel app licable) embedded steel aggressive. A plant-specific program is to be with the ASME Section XI ,

evaluated if environment is aggressive.

Subsection IW L Program ,

and B.2.1. 28 .

Aggressive chemical attack is an appli cab le ag ing effect requ iring management fo r Seabrook.

Further evaluation is provided in LRA Subsection 3.5.2.2.1.1.

The Structures Mon itori ng Program . B.2.1.31, will perform concrete testi ng and reba r inspecti on to determine the effects of the ag.gressive groundwater on the concrete. The co ncrete testing and the rebar inspection will represent all concrete below grade .

SBK-L-17155 I Enclosure 2/ Page 3 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components

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Item ,Agipg Managerre!lt !: Further Evaluation Component Aging Effect I Mechanism Discussion Number

Program "* t1*1. Recommended 3.5.1-2 Concrete elements: all Cracks and distortion due to Structures Monitoring Program. If a de- Yes, if not within the Seabrook does not rely on a increased stress levels from watering system is relied upon for control of scope of the applicant's dewatering system for settlement settlement, then the licensee is to ensure structures monitoring control of settlement.

proper functioning of the de-watering system program or a de-watering through the period of extended operation . system is relied upon Cracking and distortion due to increased stress levels from settlement is not an aging effect requ iring management.

However, Seabrook structures are monitored for settlement as a part of the Structures Monitoring Program, B.2.1.31.

Further evaluation is provided in LRA Subsection 3.5.2.2. 1.2.

3.5.1-3 Concrete elements: Reduction in foundation Structures Monitoring Program. If a de- Yes, if not within the Reduction in foundation foundation , strength , cracking , differential watering system is relied upon to control scope of the applicant's strength, cracking, and subfoundation settlement due to erosion of erosion of cement from porous concrete structures monitoring differential settlement due to porous concrete subfoundations, then the licensee is to ensure program or a de-watering erosion of porous concrete subfoundation proper functioning of the de-watering system system is relied upon subfoundations is not an through the period of extended operation aging effect requiring management for the Seabrook Containment Structure.

Further evaluation is provided in LRA Subsection 3.5.2.2.1.2.

SBK-L-171 55 I Enclosure 2/ Page 4 U. S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations fo r Structures and Structural Components t*;

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"' Aging 1 iyianagemen~1 Further Evaluation Component Aging Effect I Mechanism '!!I' !Ii Discussion Number Program ,ii* *i'l 1+ . ' ~~c'~fnme'nded , '

3.5. 1-4 Concrete elements: Reduction of strength and Plant-specific Yes, plant-specific if This item is not applicable to dome, wall, basemat, modulus due to elevated temperature limits are Seabrook.

ring girder, buttresses, temperature exceeded containment, concrete No containment fill-in annulus (as components exceed the applicable) specified temperature thresholds.

Further evaluation is provided in LRA Subsection 3.5.2.2.1.3.

3.5.1-5 BWR only.

3.5.1-6 Steel elements : steel Loss of material due to ISi (IWE) and 10 CFR Part 50, Appendix J Yes, if corrosion is Consistent with NUREG-liner, liner anchors, general , pitting , and crevice significant for inaccessible 1801 .

integral attachments corrosion areas Seabrook manages loss of material with the ASME Section XI, Subsection IWE Program, B.2.1.27.

Loss of material due to corrosion is not expected to be significant for inaccessible areas.

Further evaluation is provided in LRA Subsection 3.5.2.2.1.4.

3.5 .1-7 Prestressed Loss of prestress due to TLAA evaluated in accordance with 10 CFR Yes, TLAA This item is not applicable to containment tendons relaxation , shrinkage, creep, 54.21 (c) Seabrook.

and elevated temperature The Seabrook Containment Building is not a pre-stressed concrete containment.

Further evaluation is provided in LRA Subsection 3.5.2.2 .1.5.

SBK-L-17155 I Enclosure 2/ Page 5 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components

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Aging Management Further Evaluation

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'*1 Component Aging Effect I Mechanism Discussion Number Program Recommended 1;1 I '*I' Iii .l*I I.I 3.5.1-8 BWRonly.

3.5.1 -9 Steel, stainless steel Cumulative fatigue damage TLAA evaluated in accordance with 10 CFR Yes, TLAA Consistent with NUREG-elements, dissimilar (CLB fatigue analysis exists) 54.21 (c) 1801 for Seabrook metal welds: penetration containment penetrations sleeves, penetration that experience significant bellows; suppression cyclic loading.

pool shell , unbraced down comers Further evaluation is provided in LRA Subsection 3.5.2.2.1.6.

3.5.1 -10 Stainless steel Cracking due to stress ISi (IWE) and 10 CFR Part 50, Appendix J and Yes, detection of aging is Cracking due to stress penetration sleeves, corrosion cracking additional appropriate examinations I to be evaluated corrosion cracking is not an penetration bellows, evaluations for bellows assemblies and aging effect requiring dissimilar metal welds dissimilar metal welds management for these stainless steel components .

Further evaluation is provided in LRA Subsection 3.5.2.2.1 .7.

3.5 .1 -11 BWR only.

3.5.1-12 Steel , stainless steel Cracking due to cyclic ISi (IWE) and 10 CFR Part 50, Appendix J Yes, detection of aging is This item is not applicable to elements, dissimi lar loading supplemented to detect fine cracks to be evaluated Seabrook.

metal welds: penetration sleeves , penetration Cracking due to cyclic bellows; suppression loading is not an aging pool shell, unbraced effect requiring downcomers management for the Seabrook penetration elements.

Further evaluation is provided in LRA Subsection 3.5.2.2.1 .8.

3.5.1-13 BWRonly.

SBK-L-17155 I Enclosure 2/ Page 6 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components

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3.5.1-14 Concrete elements: Loss of material (scaling, ISi (IWL) Evaluation is needed for plants that Yes, for inaccessible Loss of material due to dome, wall, basemat, cracking, and spalling) due to are located in moderate to severe weathering areas of plants located in freeze-thaw effects is not an ring girder, buttresses, freeze - thaw conditions (weathering index >100 day - moderate to severe aging effect requiring containment (as inch/yr) (NUREG-1557) weathering conditions management for Seabrook.

applicable) Seabrook concrete containment is enclosed by a containment enclosure building and therefore not exposed to severe weathering conditions.

Further evaluation is provided in LRA Subsection 3.5.2.2. 1.9.

SBK-L-17155 I Enclosure 2/ Page 7 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components

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FAaAa§eFAeAI feF !Re eeA!aiAFA6AI S!Ftie!tire at Seal:JFeelc Concrete was constructed equivalent to recommendations in AC I 201 .2R. Seabrook Station Operating Experience indicated that Alkali-Silica Reaction (ASR) is present in the site monitoring through the Period of Extended Operation (PEO).

Seabrook manages loss of material due to leaching of calcium hydroxide with the ASME Section XI, Subsection IWL Program ,

B.2.1.28.

Cracking due to expansion and reaction with aggregates is managed through the ASME Section XI , Subsection IWL

SBK-L-17155 I Enclosure 2/ Page 8 U.S . Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components Item 11

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Number Program Recommended Program , B.2.1.28, aoo Alkali-Silica Reaction (ASR)

Monitoring Program, B.2. 1.31A, and Building Deformation Monitoring Program, B.2.1 .31B.

Further evalu ation is provided in LRA Subsection 3.5.2 .2. 1. 10.

3.5.1-16 Seals, gaskets, and Loss of sealing and leakage ISi (IWE) and 10 CFR Part 50, Append ix J No Consistent with NUREG-moisture barriers through containment due to 1801.

deterioration of joint seals, gaskets, and moisture Seabrook manages loss of barriers (caulking, flashing , sea ling with the ASME and other sealants) Section XI, Subsection IWE Program , B.2. 1.27, and the 10 CFR 50 Appendix J Program, B.2.1 .30.

Seabrook Station Operating Experience indicated that building deformation can occur due to alkali-silica reaction and th erefore Seabrook manages loss of sealing due to ASR with th e Building Deformation Monitoring Program, B.2.1.31B.

SBK-L-17 155 I Enclosure 2/ Page 9 U. S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components

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'.l:.l.11:1; Item Agi.n g Management Further Evaluation Component Aging Effect I Mechanism Discussion Number Program Recommended 3.5 .1 -17 Personnel airlock, Loss of leak tightness in 10 CFR Part 50 , Appendix J and plant No Consistent with NUREG-equipment hatch and closed position due to Technical Specifications 1801.

CRD hatch locks, mechanical wear of locks, hinges , and closure hinges , and closure The 10 CFR 50 Append ix J mechanisms mechanisms Program , B.2.1.30, is used to manage loss of leak tightness.

3.5.1-18 Steel penetration Loss of material due to ISi (JWE) and 10 CFR Part 50 Ap pendix J No Consistent with NUREG-sleeves and dissimilar general , pitting , and crevice 1801.

metal welds; personnel corrosion airlock, equipment The ASME Section XI, hatch , and CRD hatch Subsection IWE, B.2. 1.27 manages loss of material due to corrosion, 10 CFR 50 Appendix J Program ,

B.2.1.30, manages loss of leak tightness.

3.5.1 -19 BWRonly.

3.5.1 -20 BWR only.

3.5.1-21 BWR only.

3.5.1-22 Prestressed Loss of material due to ISi (JWL) No Not Applicable. Seabrook containment: tendons corrosion Station does not have and anchorage prestressed tendons.

components Safety Related and Other Stru ctures; and Component Supports

SBK-L-1 7155 I Enclosure 2/ Page 10 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components

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Number Program Recommended 3.5.1-23 All Groups except Cracking, loss of bond, and Structures Monitoring Program Yes , if not within the Consistent with NUREG-Group 6: interior and loss of material (spalling, scope of the applicant's 1801 .

above grade exterior scaling) due to corrosion of Structures Monitoring concrete embedded steel Program Seabrook manages the aging effects with the Structures Monitoring Program , B.2.1.31.

Further evaluation is provided in LRA Subsection 3.5.2.2.2.1, Item 1.

3.5.1-24 All Groups except Increase in porosity and Structures Monitoring Program Yes, if not within the The Seabrook AMR results Group 6: interior and permeability, cracking , loss of scope of the applicant's conclude that the above grade exterior material (spalling , scaling) Structures Monitoring groundwater is aggressive concrete due to aggressive chemical Program and chem ical attack is attack applicable to Seabrook.

Therefore, all Seabrook structural components will be monitored by the Structures Monitoring Program, B.2.1.31.

Further evaluation is provided in LRA Subsection 3.5.2.2.2.1, Item 2.

3.5.1-25 All Groups except Loss of material due to Structures Monitoring Program If protective Yes , if not within the Consistent with NUREG-Group 6: steel corrosion coatings are relied upon to manage the effects scope of the applicant's 1801 .

components: all of aging , the structures monitoring program is Structures Monitoring structural steel to include provisions to address protective Program Seabrook manages coating monitoring and maintenance corrosion of steel components with the Structures Monitoring Program , B.2.1.31.

Further evaluation is provided in LRA Subsection 3.5 .2.2.2. 1, Item 3. I

SBK-L-17155 I Enclosure 2/ Page 11 U. S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components ti 1-1:1n1*1.,.111' 11:1 11 l'I li:h i!iii*I* 1'1.l: 11 11 j:I :f'I "", lil'.lh 1 j:I 1 1

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Item Aging Management Further Evaluation Component Aging Effect I Mechanism Discussion Number Program Recommended 3.5.1-26 All Groups except Loss of material (spalling, Structures Monitoring Program Evaluation is Yes, if not within the Consistent with NUREG-Group 6: accessible and scaling) and cracking due to needed for plants that are located in moderate scope of the applicant's 1801.

inaccessible concrete: freeze-thaw to severe weathering conditions (weathering Structures Monitoring foundation index >100 day-inch/yr) (NUREG-1557) Program or for Seabrook manages Loss of inaccessible areas of material (spalling, scali ng) plants located in and cracking due to freeze-moderate to severe thaw with the Structures weathering conditions Monitoring Program ,

B.2.1.3 1.

Further evaluation is provided in LRA Subsection 3.5.2.2.2.1 , Item 4.

SBK-L- 171 55 I Enclosure 2/ Page 12 U. S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components I 1,, ,1:1 Item " ' 'Aging Management Further Evaluati on ,,

Component Aging Effect I Mechanism 1 P' rogra~. , 1*1 Discussiop Number ' Recommended '

3.5.1-27 All Groups except Cracking due to expansion Structures Monitoring Program . None for Yes, if not within the +Ris iteFA is Aet a1313 lieas le te Group 6: accessible and due to reaction with inaccessible areas if concrete was constructed scope of the applicant' s Seas reelc inaccessible interior I aggregates in accordance with the recommendations in Structures Monitoring exterior concrete AC ! 201 .2R-77 Program or concrete was +Re Seasreel' .O.MR Fes\ollts not constructed as stated ee Ael\o!Ele !Rat Feaeti eA w i!R for inaccessible areas a§§Fe§ates is Ae! si§A ifieaA!

aA El !Re ee AoFe!e was oeAstrnete El oeAsis!eA! w i!R I The recommendations of AC ! 20 1.2R. Seabrook Station Operating Experience indicated th at A lkali-S ilica Reaction (ASR)i s present in the site monitoring through the Period of Extended Operation (PEO).

NeAe!Reless , all Seasreel' Stf1:16l1:1Fal 69FAJ39AeA!S a1313 lioas le te !Ris iteFA will se FAeA iteFe El sy ! Re S!F1:1 0!1:1Fes MeAiteFiA§ Pre§FaFA,

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Cracki ng due to expansion and reaction with aggregates is mon itored by the Structures Monitoring Program , B.2.1 .3 1, the Al kali-Si lica Reaction (ASR)

Mon itoring Program ,

B.2.1 .31A , andthe Building Deformation Further evaluation is provided in LRA Subsection 3.5.2.2 .2.1, Item 5.

SBK-L-17155 I Enclosure 2/ Page 13 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components 1.1.: ,,

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Item ., Aging Management I*'* Further Evaluation l'I 11'1 Component Aging Effect I Mechanism Discussion Number Program Recommended Monitoring Program, B.2.1.318.

Further evaluation is provided in LRA Subsection 3.5.2.2.2.1 , Item 5.

3.5.1-28 Groups 1-3, 5-9: All Cracks and distortion due to Structures Monitoring Program If a de- Yes, if not within the This item is not applicable to increased stress levels from watering system is relied upon for contro l of scope of the applicant's Seabrook.

settlement settlement, then the licensee is to ensure Structures Monitoring proper functioning of the de-watering system Program or a de-watering The Seabrook AMR results through the period of extended operation system is relied upon conclude that settlement is not significant.

Further, a dewatering system is not relied upon for control of settlement at Seabrook.

Further evaluation is provided in LRA Subsecti on 3.5.2.2.2.1 , Item 6.

3.5.1-29 Groups 1-3, 5-9: Reduction in foundation Structures Monitoring Program If a de- Yes, if not within the This item is not applicable to foundation strength , cracking , differential watering system is relied upon for control of scope of the applicant's Seabrook.

settlement due to erosion of settlement, then the licensee is to ensure Structures Monitoring porous concrete proper functioning of the de-watering system Program or a de-watering The Seabrook AMR results subfoundation through the period of extended operation system is relied upon conclude that settlement is not significant.

Further, a dewatering system is not relied upon for control of settlement at Seabrook.

Further evaluatio n is provided in LRA Subsection 3.5.2.2.2 .1, Item 7.

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11*1 3.5.1-30 Group 4: Radial beam Lock-up due to wear ISi (IWF) or Structures Monitoring Program Yes, if not within the Lubrite materia ls for seats in BWR drywell; scope of ISi of Structures nuclear applications are RPV support shoes for Monitoring Program designed to resist PWR with nozzle deformation , have a low support; Steam coefficient of friction , resist generator supports softening at elevated temperatures, resist corrosion , withstand high intensities of radiation , and will not score or mar.

Further evaluation is provided in LRA Subsection 3.5.2.2.2.1 , Item 8.

3.5 .1-31 Groups 1-3 , 5, 7-9: Increase in porosity and Structures Monitoring Program Examination of Yes, plant-specific if The Seabrook AMR results below grade concrete permeability, cracking, loss of representative samples of below grade environment is aggressive conclude that the components, such as material (spalling , scaling) I concrete, and periodic monitoring of groundwater is aggressive.

exterior walls below aggressive chemical attack; groundwater, if the environment is non-grade and foundation cracking , loss of bond , and aggressive. A plant-specific program is to be The Structures Monitoring loss of material (spalling, evaluated if the environment is aggressive Program , B.2.1.31, will scaling)/ corrosion of manage degradation of embedded steel accessible and inaccessible concrete components due to corrosion of embedded steel.

Further evaluation is provided in LRA Subsection 3.5.2.2.2.2.

The Structures Monitoring Program , B.2.1 .31 , will perform concrete testing and rebar inspection to determine the effects of the aggressive groundwater on the concrete . The concrete testing and the rebar inspection will represent all concrete below grade.

SBK-L-171 55 / Enclosure2/Page15 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Stru ctural Components 1;

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Item Aging Management Further Evaluation Component Aging Effect I Mechanism Discussion Number ' 11 Program Recommended 1 111. :I I !I!!' :1: :Ii I :1:* :1: :111:1 3.5.1 -32 Groups 1-3, 5, 7-9: Increase in porosity and Structures Monitoring Program for accessible Yes, if concrete was not Loss of material due to exterior above and permeability, loss of strength areas. None for inaccessible areas if concrete constructed as stated for leaching of calcium below grade reinforced due to leaching of calcium was constructed in accordance with the inaccessible areas hydroxide is cons idered to concrete foundations hydroxide recommendations in ACI 201.2R-77 be an aging effect requiring management for Seabrook.

There have been indication s of leaching in below grade concrete in Seabrook structures.

Further evaluation is provided in LRA Subsecti on 3.5.2 .2.2.2, Item 5.

3.5.1-33 Group 1-5: concrete Reduction in strength and Plant-specific Yes, plant specific if This item is not applicable to modulus due to elevated temperature limits are Seabrook concrete temperature exceeded components do not exceed the temperature limits specified in NUREG-1800.

Further evaluation is provided in LRA Subsecti on 3.5.2.2 .2. 3.

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I Item Aging Management Further Evaluation Component Aging Effect I Mechanism Discussion Number Program Recommended 3.5.1-34 Group 6: concrete; all Cracking, loss of bond, loss Inspection of Water Control Structures Yes, plant-specific if Concrete in inaccessible of material due to corrosion Associated with Nuclear Power Plants and for environment is aggressive areas is evaluated for of embedded steel, increase inaccessible concrete, examination of increase in Porosity and in porosity and permeability, representative samples of below grade Permeability, and Loss of cracking, loss of material due concrete, and periodic monitoring of Material (Spalling, Scaling),

to aggressive chemical attack groundwater, if environment is non-aggressive. Chemical Attack; Crackin g, Plant-specific if environment is aggressive Loss of Bond , and Loss of Material (Spalling , Scaling} ,

Corrosion of Embedded Steel is applicable to Seabrook.

Further evaluation is provided in LRA Subsection 3.5 .2.2.2.4, Item 1.

The Structures Monitoring Program, B.2.1.31, will perform concrete testing and rebar inspection to determine the effects of the aggressive groundwater on the concrete. The concrete testing and the rebar inspection will represent all concrete below grade.

3.5.1-35 Group 6: exterior above Loss of material (spalling , Inspection of Water Control Structures Yes, for inaccessible Consistent with NUREG-and below grade scaling) and cracking due to Associated with Nuclear Power Plants is areas of plants located in 1801.

concrete foundation freeze-thaw needed for plants that are located in moderate moderate to severe to severe weathering conditions (weathering weathering conditions Seabrook manages Loss of index >100 day-inch/yr) (NUEG 1557) material (spalling, scaling) and cracking due to freeze-thaw with th e Structures Monitoring Program, B.2.1 .31.

Further evaluation is provided in LRA Subsection 3.5.2.2.2.4 , Item 2.

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,,,

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Item Aging Management , Further Evaluation :1; Component Aging Effect I Mechanism Discussion Number Program Recommended 3.5. 1-36 Group 6: all accessible I Cracking due to expansion I Accessible areas: Inspection of Water Control Yes, if concrete was not GeAsisleAI wi!R N ~R~G inaccessible reinforced reaction with aggregates Structures Associated with Nuclear Power constructed as stated for ~

concrete Plants. None for inaccessible areas if concrete inaccessible areas was constructed in accordance with the The concrete was recommendation s in ACI 201 .2R77 constructed consistent with the recommendations of AC I 201.2R. Seabrook Station Operating Experience has indicated that Al kali-Silica Reaction (ASR) is present in site structures and will require monitoring through the Period of Extended Operation (PEO).

The Structures Monitoring Program, B.2. 1.31 and Alkali-Silica Reaction (ASR)

Monitoring Program ,

B.2. 1.31A, and Building Deformation Monitoring Program, B.2. 1.318, will manage degradation of accessible and inaccessible concrete components fo r cracking due to expansion I reaction with aggregates .

Further evaluation is provided in LRA Subsection 3.5.2.2.2.4, Item 3.

SBK-L-17155 I Enclosure 2/ Page 18 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components

' I ' *I*!. l'1 f'l1f,' ,,,,,,,,,: 'l",;I

'

Item Aging Management Further Evaluation Component Aging Effect I Mechanism Discussion Number Program , Recommended

,"'

3.5.1-37 Group 6: exterior above Increase i'n porosity and For accessible areas, Inspection of Water Yes, if concrete was not Consistent with NUREG-and below grade permeability, Joss of strength Control Structures Associated with Nuclear constructed as stated for 1801 .

reinforced concrete due to leaching of calcium Power Plants. None for inaccessible areas if inaccessible areas foundation interior slab hydroxide concrete was constructed in accordance with The Structures Monitoring the recommendations in ACI 201.2R77 Program, B.2.1.31 , will manage degradation of accessible and inaccessible concrete components due to Increase in porosity and permeability, loss of strength due to leaching of calcium hydroxide Further evaluation is provided in LRA Subsection 3.5.2.2.2.4, Item 3.

3.5 .1 -38 Group 7, 8: Tank liners Cracking due to stress Plant-specific Yes, plant-specific There are no components at corrosion cracking; Joss of Seabrook that are subject to material due to pitting and this aging effect.

crevice corrosion Further evaluation is provided in LRA Subsection 3.5.2.2.2.5.

3.5 .1-39 Support members; Loss of material due to Structures Monitoring Program Yes, if not within the Consistent with NUREG-welds; bolted general and pitting corrosion scope of the applicant's 1801.

connections; support Structures Monitoring anchorage to building Program The Structures Monitoring structure Program, B.2.1.31 , wi ll manage degradation for components for loss of material due to general and pitting corrosion Further evaluation is provided in LRA Subsection 3.5.2.2.2.6, ltem1.

SBK-L-17155 I Enclosure 2/ Page 19 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components

'1'11*, !:I ,, ,, !'i ,., 1:1'1 '"

,,,,, ,,.,,

Item Aging Management Further Evaluation Number Component ,, Aging Effect I 1 Mec ~anism

Prog'ram ' i ,,

Recommended l'I '!'Discussion 1*1'

"

"'

3.5.1-40 Building concrete at Reduction in concrete anchor Structures Monitoring Program Yes, if not within the Consistent with NUREG-locations of expansion capacity due to local scope of the applicant's 1801 .

and grouted anchors; concrete degradation I Structures Monitoring grout pads for support service-induced cracking or Program The Structures Monitoring base plates other concrete aging Program , B.2.1 .31, and mechanisms Alkali-Silica Reaction (ASR) Monitoring Program, B.2.1 .31A will manage degradation for the aging effects .

Further evaluation is provided in LRA Subsection 3.5.2.2.2.6, Item 2.

3.5.1-41 Vibration isolation Reduction or loss of isolation Structures Monitoring Program Yes, if not within the This item is not applicable to elements function I radiation scope of the applicant's Seabrook.

hardening , temperature, Structures Monitoring humidity, sustained vibratory Program Seabrook does not have loading any supports with vibration isolation elements which require AMR Further evaluation is provided in LRA Subsection 3.5.2 .2.2 .6, Item 3.

3.5. 1-42 Groups 81 .1, 81 .2 , and Cumulative fatigue damage TLAA evaluated in accordance with 10 CFR Yes, TLAA This item is not applicable to 81 .3: support members: (CLB fatigue analysis exists) 54.21(c) Seabrook.

anchor bolts , welds Seabrook does not have any CLB fatigue analyses for support members, anchor bolts, or welds .

Further evaluation is provided in LRA Subsection 3.5.2.2.2.7 .

SBK-L-17155 I Enclosure 2/ Page 20 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Ag ing Management Evaluations for Structures and Structural Components I 11:+1. I] IJ Item Aging Management Further Evaluation Component Aging Effeet I Mechanism Discussion Number Program Recommended 3.5.1-43 Group 1-3, 5, 6: all Cracking due to restraint Masonry Wall Program No Seabrook manages cracking masonry block walls shrinkage , creep , and of masonry block walls and aggressive environment masonry units with the Structures Monitoring Program , B.2.1.31 . In addition , masonry wall Fire Barriers, are managed with the Fire Protection Program ,

B.2.1.15.

3.5 .1-44 Group 6 elastomer Loss of sealing due to Structures Monitoring Program No Consistent with NUREG-seals, gaskets, and deterioration of seals , 1801.

moisture barriers gaskets, and moisture barriers (caulking, flashing , The Structures Monitoring and other sealants) Program , B.2.1.31 ., and Building Deformation Monitoring Program, B.2.1.318.

3.5.1-45 Group 6: exterior above Loss of material due to Inspection of Water Control Structures No Consistent with NUREG-and below ground abrasion , cavitation Associated with Nuclear Power Plants 1801.

concrete foundation; interior slab The Structures Monitoring Program , B.2. 1.31 , will confirm the absence of aging effects requiring management.

3.5.1-46 Group 5: fuel pool liners Cracking due to stress Water Chemistry and Monitoring of spent fuel No The spent fuel pool is corrosion cracking ; loss of pool water level and level of fluid in the leak normally maintained less material due to pitting and chase channel than 140°F, therefore Stress crevice corrosion Corrosion Cracking is not an aging effect that requ ires management. Crevice and pitting corrosion are managed by the Water Chemistry Program , B.2. 1.2.

SBK-L-17155 I Enclosure 2/ Page 21 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components 1*1::1:*.1:1:1'1:**, I'll! l*l l1 :'i: 11!: 11' l:l'ili! "It* '

1*:: 1*1:ll*l']::*!'I :I: ''l:i: !*I .,:1:1> ]: 1F*

Item Aging* Management Further Evaluation Component Aging Effect I Mechanism Discussion Number Program Recommended 3.5.1-47 Group 6: all metal Loss of material due to Inspection of Water Control Structures No Consistent with NU REG-structural members general (steel only), pitting , Associated with Nuclear Power Plants. If 1801.

and crevice corrosion protective coatings are relied upon to manage The Structures Monitoring aging , protective coating monitoring and Program , B.2. 1.31 , will maintenance provisions should be included confirm the absence of aging effects requiring management.

3.5. 1-48 Group 6: earthen water Loss of material, loss of form Inspection of Water Control Structures No Consistent with NUREG-control structures - due to erosion, settlement, Associated with Nuclear Power Plants 1801.

dams, embankments, sedimentation , frost action, The Structures Monitoring reservoirs , channels, waves, currents, surface Program , B.2. 1.31 will canals, and ponds runoff, seepage confirm the absence of aging effects requiring management.

3.5.1-49 BWRonly.

3.5.1 -5 0 Groups B2 and 84: Loss of material due to pitting Structures Monitoring Program No Consistent with NUREG-galvanized steel, and crevice corrosion 1801.

aluminum , stainless The Structures Monitoring steel support members; Program , B.2.1.31 , wil l welds; bolted confirm the absence of connections; support aging effects requiring anchorage to building management.

structure 3.5.1 -51 Group B1.1: high Cracking due to stress Bolting Integrity No There are no high strength strength low-al loy bolts corrosion cracking; loss of bolts at Seabrook that are material due to general subject to this aging effect.

corrosion

SBK-L-171 55 I Enclosure 2/ Page 22 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components

'

Item Aging Management Further Evaluation Component Aging Effect I Mechanism Discussion Num ber ~rogram .,. Recommended

.

Fl

. *l:i 'Fl 11~1: Ii!, 111 11 Pl 'il:I

1*1 'i:r* '"' 'i"H"1 111r1*1 l'I Jti 1:1 3.5.1-52 Groups 82 and 84: Loss of mechanical function Structures Monitoring Program No There are no slid ing support sliding support bearings due to corrosion , distortion, bearings of surfaces at and sliding support dirt , overload , fatigue due to Seabrook that are subject to surfaces vibratory and cyclic thermal this aging effect.

loads 3.5 .1-53 Groups 81.1 , 81 .2, and Loss of material due to ISl(IWF) No Consistent with NUREG-81 .3: support members: general and pitting corrosion 1801 .

welds; bolted connections; support Seabrook manages the anchorage to building aging effect with the ASME structure Section XI , Subsection IWF Program , 8 .2.1.29.

3.5.1 -54 Group 81.1 , 81 .2, and Loss of mechanical function ISl(IWF) No Consistent with NUREG-81 .3: Constant and due to corrosion , distortion, 1801.

variable load spring dirt, overload fatigue due to hangers; guides; stops vi bratory and cyclic thermal Seabrook manages the loads ag ing effect with the ASME Section XI , Subsection IWF Program, 8 .2.1 .29.

SBK-L- 171 55 I Enclosure 2/ Page 23 U. S. Nuclear Regul atory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components

..

Item

! .. , Im i 1:n' ,_l!l 1f!i. :*~ I ~:* , ::1, ,,i1::: 1:11111 .

Aging Management ,J, I,.

'

1 11

"Further Evaluation 1

II )ll !1

i;*

t1*I IF ii '

Component Aging Effect I Mechanism 1.1:1' ' Discussion Number Program Recom mended 3.5.1-55 Steel, galvanized steel, Loss of material due to boric Boric Acid Corrosion No Consistent with NUREG-and aluminum support acid corrosion 180 1.

members; welds; bolted connections; support Seabrook manages the anchorage to building aging effect of loss of structure material due to boric acid corros ion in steel, galvan ized steel, and aluminum for all types of support members (including safety and non-safety),

welds , bolted connections and support anchorage to building structure with th e Boric Acid Corrosion Prog ram , B.2 .1.4.

3.5.1-56 Groups B1.1 , B1 .2 , and Loss of material function due ISl (IWF) No There are no sliding support B1.3: Slid ing surfaces to corrosion , distortion , dirt, bearings of surfaces at overload , fatigue due to Seabrook that are subject to vibratory and cyclic thermal this aging effect.

loads 3.5.1 -57 Groups B1.1, B1 .2, and Reduction or loss of isolation ISl (IWF) No This item is not applicable to B1.3: Vibration isolation function/radiation hardening , Seabrook.

elements temperature , humidity, sustained vibratory loading The Seabrook AMR res ults do not include any supports with vibrati on isolation elements.

SBK-L-17155 I Enclosure 2/ Page 24 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components l\11:.i ,*I ;l:I ,. 'I' 'i:i 1iH *i: I

'I' Item Aging Management Further Ev aluation Component Aging Effect I Mechanism Discussion Number Program Recommended 11 3.5.1-58 Galvanized steel and Nooe Nooe N/\ Re ag iAg effect Consistent with NUREG-aluminum support Reduction in structural Structures Monitoring Program 1801.

maAagemeAt or agiAg members; welds; bolted capacity directly/ indirectly connections; support due to the expansion of maAagemeAt 13rogram Th e Structures Monitoring anchorage to building concrete Yes, if not within the Program, B.2.1.31, and structure exposed to air scope of the applicant's Building Deformation

- indoor uncontrolled Structures Monitoring Monitoring Program, Program B.2.1.31B will manage degradation for th e aging effects.

3.5.1-59 Stainless steel support members; welds; bolted Nooe Reduction in s tructural I Nooe Structures Monitoring Program W\ no ag iAg effect GoAsistent with NURE;G

~

maAagemeAt er agiAg connections; support capacity directly/ indirectly Plant Specific.

anchorage to building maAagemeAt 13rogram due to the expansion of structure concrete Yes, if not within the The Structures Monitoring scop e of th e Program, B.2.1.31, and applicant's Structures Building Deformation Monitoring Program Monitoring Program, B.2.1.31B will manage degradation for the aging effects.

3.5.1-60 Group 6 elastomer Loss of bound, I Structures Monitoring Program Yes, if not within the Plant Specific seals, gaskets, and misalignment, distortion, scope of the moisture barriers and/or reduction in applicant's Structures The Structures Monitoring s tructural capacity due to Monitoring Program Program, B.2.1.31, and expansion of concrete Building Deformation Monitoring Program, B.2.1.31B will manage degradation for th e aging effects.

SBK-L-17155 I Enclosure 2/ Page 25 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluatio ns for Stru ctures and Structural Components

I 1:I, I 1:; '*l i1:1:1:1:1:11 ,11li Ii , t1111M1 l,1:11l!:i1 1

il1/'jl1 1i'1illl' :I ~ l!j, :1:i:1:1'1::1 li1i:lily1n I'! .. 'l'I' ,

Aging Management *

1* **

1 Item ' ' Further.Evaluation '

Component Aging Effect I Mechanism Discuss ion Number Program Recommended 3.5.1-61 Steel, galvanized s teel, Reduction/loss in Structures Monitoring Program Yes, if not within the Plant Specific and aluminum support s tructural capacity due to scope of th e m embers; welds; expansion of con crete applicant's Structures The Structures Monitoring bolted connections ; Monitoring Program Program, B.2. 1.31, and s upport an chorage to Building Deformation building structure Monitoring Program, B.2.1.318 will m anage degradation for the aging effects.

SBK-L-17155 I Enclosure 2/ Page 26 U.S. Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within Li ce nse Renewal Summary of Aging Management Evaluation

,: ,,,

i: Aging Effect Aging NUREG - Table "+' '

Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function Management Program 2 Item Item Structures BSAS Carbon Steel FIRE PUM PHOUSE Air Indoor Uncontro lled lll. A3-12 3.5.1 -

Structural Support Steel Loss of Material Monitoring A Exposed to Air Indoor Uncontrolled (External) (T-1 1) 25 Program Structures BSAS Carbon Steel FIRE PUMPHOUSE lll. A3-12 3.5 .1-Structural Support Steel Air Outdoor (Externa l) Loss of Material Monitoring A, 503 Exposed to Air Outdoor (T-11) 25 Program BSAS Carbon Steel NONESSENTIAL Structures Air Indoor Uncontrolled lll.A3-12 3.5.1-SWITCHGEAR BUILDING Exposed to Structural Support Steel Loss of Material Monitoring A (External) (T-11 ) 25 Air Indoor Uncontrolled Program BSAS Carbon Steel NONESSENTIAL Structures lll.A3-12 3.5.1-SWITCHGEAR BUILDING Expo sed to Structural Support Steel Air Outdoor (External) Loss of Material Monitoring A , 503 (T-11) 25 Air Outdoor Program Structures BSAS Carbon Steel REVETMENT lll.A6-11 3.5. 1- E, 503, Flood Barrier Steel Air Outdoor (External) Loss of Material Monitoring Exposed to Air Outdoor (T-21 ) 47 51 1 Program Structures BSAS Carbon Steel REVETM ENT lll.A6-11 3.5. 1- E, 503, Support Steel Air Outdoor (Extern al) Loss of Material Monitoring Exposed to Air Outdoor (T-21) 47 511 Program

SBK-L-171 55 I Enclosure 2/ Page 27 U.S. Nuclear Regulatory Commission Table 3.5.2-1 Bui ldings, St ruct ures Within License Renewa l Summary of Aging Management Evaluation Aging Effect Aging NU REG- Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function Management Program 2 Item IV Item Structures BSAS Carbon Steel REVETMENT lll.A6-1 1 3.5.1- E, 509, Flood Barrier Steel Raw Water (Externa l) Loss of Material Monitoring Exp osed to Raw Water (T-2 1) 47 511 Program Structures BSAS Carbon Steel REVETMENT lll. A6-11 3.5.1- E, 509, Support Steel Raw Water (External) Loss of Material Monitoring Exposed to Raw Water (T-21 ) 47 511 Program Stru ctu res BSAS Carbon Steel REVETMENT lll. A6-11 3.5.1 - E, 509, Flood Barrier Steel Raw Water (External) Loss of Material Monitoring Exposed to Raw Water (T-21 ) 47 511 Program Stru ctures BSAS Carbon Steel REVETME NT lll.A6-11 3.5.1- E, 509, Support Steel Raw Water (External) Loss of Material Monitoring Expo sed to Raw Water (T-21) 47 51 1 Program Stru ctures BSAS Carbon Steel REVETMENT lll.A6-11 3.5.1 -

Flood Barrier Steel Raw Water (External) Loss of Materia l Monitoring H, 514 Exposed to Raw Water (T-21 ) 47 Program Structu res BSAS Carbon Steel REVETMENT 111.A6-11 3.5.1-Support Steel Raw Water (External) Loss of Material Monitoring H, 514 Exp osed to Raw Water (T-21 ) 47 Program

SBK-L-17155 I Enclosure 2/ Page 28 U. S. Nuclear Regulatory Commission Table 3.5.2-1 Bui ldings, Stru ctures Within License Renewa l Summary of Aging Management Evaluation cc Aging Effect Aging NU REG- Table Intended I Component Type Function Material Environment II Requ iring ,li!'I , Management ,1so1 vor.; 3.X-1 Note Managemeni 1 * ' :, Program '

1 12 1tem Item Structures BSAS Carbon Steel REVETMENT lll.A6-11 3.5.1- E, 509, Flood Barrier Steel Raw Water (External) Loss of Material Monitoring Exposed to Raw Water (T-21) 47 511 Program Structures BSAS Carbon Steel REVETMENT lll.A6-11 3.5.1- E, 509 ,

Support Steel Raw Water (External) Loss of Material Monitoring Exposed to Raw Water (T-21 ) 47 511 Program SSAS Carbon Steel STEAM Structures GENERATOR SLOWDOWN Air Indoor Uncontrolled lll.A3-12 3.5.1-Structural Support Steel Loss of Material Monitoring A RECOVERY BUILDING Exposed to Air (External) (T-11 ) 25 Program Indoor Uncontrolled SSAS Carbon Steel STEAM Stru ctures GENERATOR SLOWDOWN lll.A3-12 3.5.1 -

Structural Support Steel Air Outdoor (External) Loss of Material Monitoring A, 503 RECOVERY BUILDING Exposed to Air (T-11 ) 25 Program Outdoor Cracking , Loss of SSAS Concrete NONESSENTIAL Structures Bond , Loss of lll.A3-9 3.5. 1-SWITCHGEAR BUILDING Exposed to Structural Support Concrete Air Outdoor (External) Mon itoring A Material (Spalling , (T-04) 23 Air Outdoor Program Scal ing)

Structures Monitoring Program, SSAS Concrete NONESSE NTIAL Expansion and lll .A3-2 3.5.1- A , E, SWITCHGEAR BU ILDING Exposed to Structural Support Concrete Air Outdoor (External)

Cracking Alkali-Silica (T-03) 27 517 Air Outdoor Reaction (ASR)

Monitoring Proa ram

SBK-L-17 155 I Enclosure 2/ Page 29 U. S. Nuclear Regulatory Commission Table 3.5.2-1 Bui ldings, Structures Within License Renewa l Summary of Aging Management Evaluation Aging Effect Aging NUREG- Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3 ~ X- 1 Note Function Management Program 2 Item Item Increase In Porosity and SSAS Concrete NONESSENTIAL Structures Permeability, 111.A3-10 3.5.1-SWITCHGEAR BUILDING Exposed to Structural Support Concrete Air Outdoor (External) Monitoring A Cracking , Loss of (T-06) 24 Air Outdoor Program Material (Spalling ,

Scaling)

SSAS Concrete NONESSENTIAL Structures lll. A3-6 3.5 .1-SWITCHGEAR BUILDING Exposed to Structural Support Concrete Air Outdoor (External) Loss of Material Monitoring A (T-0 1) 26 Ai r Outdoor Program Cracking , Loss of Structures SSAS Concrete (Sump) FIRE Bond , Loss of lll. A3-4 3.5.1 -

Structural Support Concrete Raw Water (External) Monitoring A PUMPHOUSE Exposed to Raw Water Material (Spalling , (T-05) 31 Program Scaling)

Structures Monitoring Program , Alkali-BSAS Concrete (Sump) FIRE Expansion and ll l.A3-2 3.5. 1- A, E, Structural Support Concrete Raw Water (External) Silica Reaction PUMPHOUSE Exposed to Raw Water Cracking (T-03) 27 517 (ASR)

Mon itoring Program SSAS Concrete (Sump) STEAM Cracking, Loss of Structures GENERATOR SLOWDOWN Bond, Loss of lll.A3-4 3.5.1 -

Structural Support Concrete Raw Water (External) Monitoring A RECOVERY BUILDING Exposed to Material (Spalling, (T-05) 31 Program Raw Water Scaling)

SBK-L-17 155 I Enclosure 2/ Page 30 U.S. Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Ag ing Management Evaluation Aging Effect Aging NU REG - Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Nqte Function Management Program 2 Item Item Structures Monitoring SSAS Concrete (Sump) STEAM Program , Alkali-GENERATOR SLOWDOWN Expansion and lll. A3-2 3.5 .1 - A, E, Structural Support Concrete Raw Water (External) Silica Reaction RECOVERY BUILDING Exposed to Cracking (T-03) 27 517 (ASR)

Raw Water Monitoring Program Cracking , Loss of SSAS Concrete DISCHARGE Structures Air Indoor Uncontrolled Bond, Loss of lll.A6-1 3.5.1-TRANSITION STRUCTURE Exposed to Structural Support Concrete Monitoring E, 511 (External) Material (Spalling, (T-18) 34 Air Indoor Uncontrolled Program Scaling)

Structures Monitoring SSAS Concrete DISCHARGE Program, Alkali-Air Indoor Uncontrolled Expansion and lll.A6-2 3.5.1- E, 511, TRANSITION STRUCTURE Exposed to Structural Support Concrete Silica Reaction (External) Cracking (T-17) 36 517 Air Indoor Uncontrolled (ASR)

Monitorin g Program Increase In Porosity and SSAS Concrete DISCHARGE Structures Air Indoor Uncontrolled Permeability, lll.A3-10 3.5.1-TRANSITION STRUCTURE Exposed to Structural Support Concrete Monitoring A (External) Cracking , Loss of (T-06) 24 Air Indoor Uncontrolled Program Material (Spalling ,

Scaling)

SBK-L-17155 I Enclosure 2/ Page 31 U.S. Nuclear Regulatory Commission Table 3.5.2-1 Bui ldings, Structures Within License Renewa l Summary of Aging Management Evaluation

'*it' Aging Effect Aging NU REG - Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function Management Program 2 Item Item Cracking , Loss of SSAS Concrete DISCHARGE Stru ctures Bond, Loss of lll.A6- 1 3.5.1-TRANSITION STRUCTURE Exposed to Missile Barrier Concrete Air Outdoor (External) Monitoring E, 511 Material (Spalling , (T-18) 34 Air Outdoor Program Scaling)

Cracking , Loss of SSAS Concrete DISCHARGE Structures Bond , Loss of lll.A6-1 3.5.1-TRANSITION STRUCTURE Exposed to Structural Support Concrete Air Outdoor (External) Monitoring E, 511 Material (Spalling , (T-18) 34 Air Outdoor Program Scaling)

Structures Monitoring Program, Alkali-Silica Reaction SSAS Concrete DISCHARGE (ASR) E, 511 ,

Expansion and lll.A6-2 3.5.1 -

TRANSITION STRUCTURE Exposed to Missile Barrier Concrete Air Outdoor (External) Monitoring 517, Cracking (T-17) 36 Air Outd oor Program & 519 Building Deformation Monitoring Program Structures Monitoring Program , Alkali-Silica Reaction BSAS Concrete DISCHARGE (ASR) E, 511 ,

Expansion and lll.A6-2 3.5. 1-TRANS IT ION STRUCTURE Exposed to Structural Support Concrete Air Outdoor (External) Monitoring 517, Cracking (T-17) 36 Air Outdoor Program & 519 Building Deformation Monitoring Program Increase In Porosity and SSAS Concrete DISCHARGE Structures Permeabi lity, lll.A3-10 3.5.1 -

TRANSITION STRUCTURE Exposed to Missile Barrier Concrete Air Outdoor (External) Mo nito ring A Cracking , Loss of (T-06) 24 Air Outdoor Program Material (Spalling, Scaling)

SBK-L-17155 I Enclosure 2/ Page 32 U.S . Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Aging NU REG- Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function Managernent Program 2 Item Item Increase In Porosity and BSAS Concrete DISCHARGE Structures Permeability, 111.A3-10 3.5.1-TRANSITION STRUCTURE Exposed to Structural Support Concrete Air Outdoor (External) Monitoring A Cracking, Loss of (T-06) 24 Air Outdoor Program Material (Spalling, Scaling)

BSAS Concrete DISCHARGE Structures Loss of Material , lll.A6-5 3.5.1-TRANSITION STRUCTURE Exposed to Missile Barrier Concrete Air Outdoor (External) Monitoring E, 511 Cracking (T-15) 35 Air Outdoor Program BSAS Concrete DISCHARGE Structures Loss of Material, lll.A6-5 3.5 .1-TRANS ITION STRUCTURE Exposed to Structural Support Concrete Air Outdoor (External) Monitoring E, 511 Cracking (T-15) 35 Air Outdoor Program Cracking , Loss of BSAS Concrete DISCHARGE Structures Bond , Loss of lll.A3-4 3.5. 1-TRANSITION STRUCTURE Exposed to Structural Support Concrete Raw Water (External) Monitoring A Material (Spalling , (T-05) 31 Raw Water Program Scaling)

Structures Monitoring Program, Alkali-Silica Reaction BSAS Concrete DISCHARGE (ASR) E, 511 ,

Expansion and ll l.A6-2 3.5.1 -

TRANSITION STRUCTURE Exposed to Structural Support Concrete Raw Water (External ) Monitoring 517, Cracking (T-17) 36 Raw Water Program & 519 Building Deforma tion Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 33 U. S. Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewa l Summary of Aging Management Evaluation

,., .. ,

Aging Effect 'Aging NUREG- 1 1 Table Intended '

Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function Management Program 2 Item Item Increase In BSAS Concrete DISCHARGE Stru ctures Porosity and lll.A6-6 3.5.1-TRANS ITION STRUCTURE Exposed to Structural Support Concrete Raw Water (External) Monitori ng E, 511 Permeability, (T-16) 37 Raw Water Program Loss of Strength Cracking , Loss of Structures BSAS Concrete FIRE PUMPHOUSE Air Indoor Uncontrolled Bond , Loss of lll.A3-9 3.5.1-Structural Support Concrete Monitoring A Expo sed to Air Indoor Uncontrolled (External) Material (Spalling , (T-04) 23 Prog ram Scaling)

Structures Mon itoring Program , Alkali-Silica Reaction (ASR) A, BSAS Concrete FIRE PUMPHOUSE Air Indoor Uncontrolled Expansion and lll.A3-2 3.5. 1-Structural Support Concrete Monitoring 517, E, Exposed to Air Indoor Uncontrolled (External) Cracking (T-03) 27 Program & 519 Building Deformation Monitoring Program Increase In Porosity and Structures BSAS Concrete FIRE PUMPHOUSE Air Indoor Uncontrolled Permeability, lll.A3-10 3.5.1-Structural Support Concrete Monitoring A Exposed to Air Indoor Uncontrolled (External) Cracking, Loss of (T-06) 24 Program Material (Spall ing, Scaling)

Crackin g, Loss of Structures BSAS Concrete FIRE PUMPHOUSE Bond , Loss of 111.A3-9 3.5. 1-Structura l Support Concrete Air Outdoor (External) Monitoring A Exposed to Air Outd oor Material (Spalling , (T-04) 23 Program Scaling)

SBK-L-17155 I Enclosure 2/ Page 34 U.S. Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewa l Summary of Aging Management Evaluation Aging Effect Aging NU REG- Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function Management Program 2 Item Item Structures Monitori ng Program, Alkali-Silica Reaction (ASR) A, BSAS Concrete FIRE PUMPHOUSE Expansion and 111.A3-2 3.5.1-Structural Support Concrete Air Outdoor (External) Monitoring 517,E, Exposed to Air Outdoor Cracking (T-03) 27 Program & 519 B uilding Deformation Monitoring Program Increase In Porosity and Structures BSAS Concrete FIRE PUMPHOUSE Permeability, lll.A3-10 3.5.1 -

Structural Support Concrete Air Outdoor (External) Monitoring A Exposed to Air Outdoor Cracking , Loss of (T-06) 24 Program Material (Spalling, Sca ling)

Structures BSAS Concrete FIRE PUMPHOUSE Loss of Material , lll.A3-6 3.5. 1-Structural Support Concrete Air Outdoor (External) Monitoring A Exp osed to Air Outdoor Cracking (T-01 ) 26 Program Cracking , Loss of BSAS Concrete INTAKE TRANSITION Stru ctures Air Indoor Uncontrolled Bond , Loss of lll. A6-1 3.5.1-STRUCTURE Exposed to Air Indoor Structural Support Concrete Monitoring E, 511 (External) Material (Spalling , (T-18) 34 Uncontrolled Program Scaling)

Structures Monitoring Program, Alkali-Silica Reaction BSAS Concrete INTAKE TRANSITION (ASR) E, 511, Air Indoor Uncontrolled Expansion and lll.A6-2 3.5.1 -

STRUCTURE Exposed to Air Indoor Structural Support Concrete Monitoring 517 ,

(Externa l) Cracking (T-17) 36 Uncontrolled Program & 519 Building Deformation Mon ito ring Program

-----------------

SBK-L-17155 I Enclosure 2/ Page 35 U.S. Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Aging NU REG- Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function Management Prqgram 2 Item Item Increase In Porosity and SSAS Concrete INTAKE TRANSITION Structures Air Indoor Uncontrolled Permeability, lll.A3-10 3.5.1-STRUCTURE Exposed to Air Indoor Structural Support Concrete Monitoring A (External) Cracking , Loss of (T-06) 24 Uncontrolled Program Material (Spalling, Scaling)

Cracking , Loss of Structures SSAS Concrete INTAKE TRANSITION Bond , Loss of lll.A6-1 3.5.1-Missile Barrier Concrete Air Outdoor (External) Monitoring E, 511 STRUCTURE Exposed to Air Outdoor Material (Spalling, (T-18) 34 Program Scaling)

Cracking , Loss of Structures SSAS Concrete INTAKE TRANSITION Bond , Loss of lll.A6-1 3.5. 1-Structural Support Concrete Air Outdoor (External) Monitoring E, 51 1 STRUCTURE Exposed to Air Outdoor Material (Spalling, (T-18) 34 Program Scaling)

Structures Monitoring Program , Alkali-Silica Reaction (ASR) E, 511 ,

SSAS Concrete INTAKE TRANSITION Expansion and ll l.A6-2 3.5. 1-Missile Barrier Concrete Air Outdoor (External) Monitoring 517, STRUCTURE Exposed to Air Outdoor Cracking (T-17) 36 Program & 5 19 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) E, 511, SSAS Concrete INTAKE TRANSITION Expansion and lll.A6-2 3.5.1-Structural Support Concrete Air Outdoor (External) Monitoring 517 ,

STRUCTURE Exposed to Air Outdoor Cracking (T-17) 36 Program & 519 Building Deformation Monitoring Proqram

SBK-L-17155 I Enclosure 2/ Page 36 U.S. Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation 1: ' *.1 Aging Effect Aging Nl'.IREG- Table.

1

'" Intended "

Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function Management Program 2 Item Item Increase In Porosity and Structures BSAS Concrete INTAKE TRAN SITION Permeability, lll.A3-10 3.5.1-Missile Barrier Concrete Air Outdoor (External) Monitoring A STRUCTURE Exposed to Air Outdoor Cracking, Loss of (T-06) 24 Program Material (Spalling, Scaling)

Increase In Porosity and Structures BSAS Concrete INTAKE TRANSITION Permeability, 111.A3-10 3.5.1-Structural Support Concrete Air Outdoor (External) Monitoring A STRUCTURE Exposed to Air Outdoor Cracking , Loss of (T-06) 24 Program Material (Spalling ,

Scaling)

Structures BSAS Concrete INTAKE TRANSITION Loss of Material, lll.A6-5 3.5.1 -

Missile Barrier Concrete Air Outdoor (External) Monitoring A STRUCTURE Exposed to Air Outdoor Cracking (T-15) 35 Program Structures BSAS Concrete INTAKE TRAN SITION Loss of Material, lll. A6-5 3.5. 1-Structural Support Concrete Air Outdoor (External) Monitoring A STRUCTURE Exposed to Air Outdoor Cracking (T-15) 35 Program Cracking, Loss of Structures BSAS Concrete INTAKE TRAN SITION Bond , Loss of lll .A3-4 3.5. 1-Structural Support Concrete Raw Water (External) Monitoring A, 509 STRUCTURE Exposed to Raw Water Material (Spalling, (T-05) 31 Program Scaling)

Structures Monitoring Program, Alkali-Silica Reaction E, 511 ,

BSAS Concrete INTAKE TRANSITION Expansion and (ASR) 111.A6-2 3.5.1 -

Structural Support Concrete Raw Water (Externa l) 517, STRUCTURE Exposed to Raw Water Cracking Monitoring (T-17) 36 Program &

519 Building Deformation Monitorina

SBK-L-171 55 I Enclosure 2/ Page 37 U. S. Nuclear Regulatory Comm ission Table 3.5.2-1 Bui ldings, Struct ures Within Li ce nse Renewal Summary of Aging Management Evaluation

.,

Aging Effect Aging NUREG - Table I Intended Component Type Material Environment Requiring Management 1801 Vo l. 3.X-1 Note Function Management Program 2 Item Item Program Increase In Structures SSAS Concrete INTAKE TRANSITION Porosity and lll.A6-6 3.5 .1 -

Structural Support Concrete Raw Water (Extern al) Monitoring E, 51 1 STRUCTURE Exposed to Raw Water Permeability, (T-16) 37 Program Loss of Strength BSAS Concrete Masonry Units FIRE Concrete Air Indoor Uncontrolled Fire Protection lll. A3-11 3.5.1 -

PUMPHOUSE Exposed to Air Indoor Fire Barrier Cracki ng E, 513 Block (External) Program (T-12) 43 Uncontrolled BSAS Concrete Masonry Un its FIRE Struct ures Concrete Air Indoor Uncontrolled lll.A3-11 3.5. 1-PUMPHOUS E Exposed to Air Indoor Structural Support Cracking Monitoring E, 511 Block (External) (T-1 2) 43 Uncontrolled Program BSAS Concrete Masonry Units Structures NONESSE NTIAL SWITCHGEAR Concrete Air Indoor Uncontrolled lll.A3-11 3. 5.1 -

Structural Support Cracki ng Monitoring E, 51 1 BU ILDIN G Exposed to Air Indoor Block (External) (T- 12) 43 Program Uncontrolled BSAS Concrete Masonry Units Structures Concrete lll. A3-11 3.5.1-NON ESSENTIAL SWITCH GEAR Structural Support Air Outdoor (External) Cracking Monitoring E, 511 Block (T-12) 43 BUILD ING Expo sed to Air Outdoor Prog ram

SBK-L-17155 I Enclosure 2/ Page 38 U.S. Nucl ear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewa l Summary of Aging Management Evaluation

.,

I' '.

Agin'g Effect Aging '" 1'11.

NU REG- Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function Management Program 2 lt~m Item Cracking , Loss of BSAS Concrete NONESSENTIAL Structures Air Indoor Uncontrolled Bond , Loss of lll.A3-9 3.5.1-SWITCHGEAR BUILDING Exposed to Structural Support Concrete Monitoring A (External) Material (Spalling, (T-04) 23 Air Indoor Uncontrolled Program Scaling)

Structures Monitoring BSAS Concrete NONESSENTIAL Program , Alkali-Air Indoor Uncontrolled Expansion and lll.A3-2 3.5. 1- A, E, SWITCHGEAR BU ILDING Exposed to Structural Support Concrete Silica Reaction (External) Cracking (T-03) 27 517 Air Indoor Uncontrolled (ASR)

Monitoring Program Increase In Porosity and BSAS Concrete NONESSENTIAL Structures Air Indoor Uncontrolled Permeability, lll.A3-10 3.5 .1-SWITCHGEAR BUILDING Exposed to Structural Support Concrete Monitoring A (External) Cracking, Loss of (T-06) 24 Air Indoor Uncontrolled Program Material (Spalling ,

Scaling)

Cracking, Loss of Structures BSAS Concrete REVETMENT Below Bond, Loss of lll.A3-4 3.5 .1 -

Flood Barrier Concrete Soil (External) Monitoring A, 509 Grade Material (Spalling, (T-05) 31 Program Scaling)

Cracki ng , Loss of Stru ctures BSAS Concrete REVETMENT Below Bond, Loss of lll.A3-4 3.5.1 -

Support Concrete Soil (External) Monitoring A, 509 Grade Material (Spalling, (T-05) 31 Program Scaling)

Structures Monitori ng Program, Alkali-BSAS Concrete REVETMENT Below Expansion and lll.A6-2 3.5.1 - E, 511 ,

Flood Barrier Concrete Soil (External) Silica Reaction Grade Cracking (T-17) 36 517 (ASR)

Monitoring Proo ram

SBK-L-17155 I Enclosure 2/ Page 39 U. S. Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Aging NU REG - Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function I" I

Management Program 2 Item Item 1:,1 Structures Monitoring Program, Al kali-BSAS Concrete REVETMENT Below Expansion and lll.A6-2 3.5.1 - E, 511 ,

Support Concrete Soil (External) Sil ica Reaction Grade Cracking (T-17) 36 517 (ASR)

Monitoring Proqram Increase In Porosity and Structures BSAS Concrete REVETMENT Below Permeability, lll.A6-3 3.5. 1-Flood Barrier Concrete Soil (External) Monitoring E, 511 Grade Cracking, Loss of (T-19) 34 Program Material (Spalling ,

Scaling)

Increase In Porosity and Structures BSAS Concrete REVETMENT Below Permeability, lll.A6-3 3.5.1-Support Concrete Soil (External) Monitoring E, 511 Grade Cracking , Loss of (T-19) 34 Program Material (Spalling ,

Scaling)

Increase In Structures BSAS Concrete REVETMENT Below Porosity and lll. A6-6 3.5 .1 - E, 509, Flood Barrier Concrete Soil (External) Monitoring Grade Permeability, (T-16) 37 511 Program Loss of Strength Increase In Structures BSAS Concrete REVETMENT Below Porosity and ll l.A6-6 3.5.1- E, 509, Support Concrete Soil (External) Monitoring Grade Permeability, (T-16) 37 51 1 Program Loss of Strength Cracking, Loss of Structures BSAS Concrete REVETMENT Exposed Bond, Loss of lll.A6-1 3.5.1-Flood Barrier Concrete Air Outdoor (External) Monitoring E, 511 to Air Outdoor Material (Spalling , (T-18) 34 Program Scaling)

SBK-L-17 155 I Enclosure 2/ Page 40 U .S. Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewa l Summary of Aging Management Evaluation Aging Effect Aging NUREG- Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function I

Management Program 2 Item Item Cracking , Loss of Structures BSAS Concrete REVETMENT Exposed Bond, Loss of ll l.A6-1 3.5.1 -

Support Concrete Air Outdoor (External) Monitori ng E, 511 to Air Outdoor Materia l (Spalling, (T-18) 34 Program Scaling)

Structures Monitoring Program , Alk ali-BSAS Concrete REVETMENT Exposed Expansion and lll.A6-2 3.5.1 - E, 511 ,

Flood Barrier Concrete Air Outdoor (External) Silica Reaction to Air Outdoor Cracking (T- 17) 36 517 (ASR)

Monitoring Proq ra m Structures Monitori ng Program, Alkali-SSAS Concrete REVETMENT Exposed Expans ion and lll .A6-2 3.5.1 - E, 511 ,

Support Concrete Air Outdoor (External) Silica Reaction to Air Outdoor Cracking (T-17) 36 517 (ASR)

Monitoring Proqram Increase In Porosity and Structures SSAS Concrete REVETMENT Exposed Permeability, 111.A3-10 3.5. 1-Flood Barrier Concrete Air Outdoor (External) Monitoring A to Air Outdoor Cracking , Loss of (T-06) 24 Program Material (Spalling ,

Scaling)

Increase In Porosity and Structures SSAS Concrete REVETMENT Exposed Permeability, lll. A3-10 3.5.1 -

Support Concrete Air Outdoor (External) Monitoring A to Air Outdoor Cracking , Loss of (T-06) 24 Program Material (Spalling ,

Scaling)

Structures SSAS Concrete REVETMENT Exposed Loss of Material , lll.A6-5 3.5. 1-Flood Barrier Concrete Air Outdoor (External) Monitoring E, 511 to Air Outdoor Cracking (T-15) 35 Program

SBK-L-17155 I Enclosure 2/ Page 41 U. S. Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation

'I Aging Effect Aging NU REG- Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function Management Program 2 Item Item Stru ctures BSAS Concrete REVETMENT Exposed Loss of Material, lll.A6-5 3.5.1-Support Concrete Air Outdoor (External) Mo nitoring E, 511 to Air Outdoor Cracking (T-15) 35 Program Cracking, Loss of BSAS Concrete STEAM GENERATOR Structures Air Indoor Uncontrolled Bond, Loss of 11 1.A3-9 3.5.1-SLOWDOWN RECOVERY BUILDING Structural Support Concrete Monitoring A (External) Material (Spalling , (T-04) 23 Expo sed to Air Indoor Uncontrolled Program Scaling)

Structures Monitoring SSAS Concrete STEAM GENERATOR Program, Alkali-Air Indoor Uncontrolled Expansion and lll.A3-2 3.5. 1- A, E, SLOWDOWN RECOVERY BUILDING Structural Support Concrete Silica Reaction (External) Cracking (T-03) 27 517 Exposed to Air Indoor Uncontrolled (ASR)

Monitoring Proa ram Increase In Porosity and BSAS Concrete STEAM GENERATOR Stru ctures Air Indoor Uncontrolled Permeability, lll.A3-10 3.5.1 -

SLOWDOWN RECOVERY BUILDING Structural Support Concrete Monitoring A (External) Cracking , Loss of (T-06) 24 Exp osed to Air Indoor Uncontrolled Program Material (Spalling ,

Scaling)

Cracking , Loss of BSAS Concrete STEAM GENERATOR Structures Bond , Loss of lll.A3-9 3.5.1-SLOWDOWN RECOVERY BUILDING Structural Support Concrete Air Outdoor (External) Monitoring A Material (Spalling, (T-04) 23 Exposed to Air Outdoor Program Scaling )

Structures Monitoring BSAS Concrete STEAM GENERATOR Program , Alkali-Expansion and lll.A3-2 3.5. 1- A, E, SLOWDOWN RECOVERY BUILDING Structural Support Concrete Air Outdoor (External) Silica Reaction Cracking (T-03) 27 517 Exp osed to Air Outdoor (ASR)

Monitoring Proa ram

SBK-L-17155 I Enclosure 2/ Page 42 U.S. Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Aging NU REG- Table Intended Component Type Function Material Envircm~en~ II 1

, . 11 R~ql)iri~g Management . 1801 Vol. '* 3.X-1

., . ,,,.HProgram 1tl '* lli'li 2' 1tem '1'11*1'

ltEim 1:1 H Note II Management

Increase In Porosity and BSAS Concrete STEAM GENERATOR Structures Permeability, lll.A3-10 3.5.1-SLOWDOWN RECOVERY BUILDING Structural Support Concrete Air Outdoor (External) Monitoring A Cracking, Loss of (T-06) 24 Exposed to Air Outdoor Program Material (Spalling, Scal ing)

SSAS Concrete STEAM GENERATOR Structures Loss of Material, lll.A3-6 3.5.1-SLOWDOWN RECOVERY BUILDING Structural Support Concrete Air Outdoor (External) Monitoring A Cracking (T-01) 26 Exposed to Air Outdoor Program Structures SSAS Rock (Riprap) REVETMENT Loss of Material , lll.A6-9 3.5.1-Flood Barrier Rock Air Outdoor (External) Monitoring E, 511 Exposed to Air Outdoor Loss of Form (T-22) 48 Program Structures SSAS Rock (Riprap) REVETMENT Loss of Material, lll.A6-9 3.5. 1-Support Rock Air Outdoor (External) Monitoring E, 511 Exposed to Air Outdoor Loss of Form (T-22) 48 Program Separation ,

Structures SSAS Roofing For FIRE PUMPHOUSE Environmental lll.A6-12 3.5.1-Structural Support Roofing Air Outdoor (External) Monitoring H, 505 Exposed to Air Outdoor Degradation , (TP-7) 44 Program Water In-Leakage Separation, SSAS Roofing For NONESSENTIAL Structures Environmental 111.A6-12 3.5.1-SWITCHGEAR BUILDING Exposed to Structural Support Roofing Air Outdoor (External) Monitoring H, 505 Degradation, (TP-7) 44 Air Outdoor Program Water In-Leakage

SBK-L-17 155 I Enclosure 2/ Page 43 U.S . Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation I

Aging Effect Ag ing NU REG- Table Intended Component Type Material Environment Requiring Management 1801 Vol. 3.X-1 Note Function

' *I Management ,Program !!' 1.1 2 ltem:if';.1 1; Item * *.. *i BSAS Roofing For STEAM Separation ,

Structures GENERATOR SLOWDOWN Environmental lll.A6-12 3.5.1-Structural Support Roofing Air Outdoor (External) Monitoring H, 505 RECOVERY BUILDING Exposed to Air Degradation , (TP-7) 44 Program Outdoor Water In-Leakage BSAS Slide Bearing (Fluorogold)

Structures NONESSENTIAL SWITCHGEAR Air Indoor Uncontrolled Fretting Or 111. 84-2 3.5.1-BU ILDING Exposed to Air Indoor Structural Support Fluorogold (External) Lockup Monitoring (TP-1 ) 52 c

Program Uncontrolled BSAS Stainless Steel STEAM No Aging GENERATOR SLOWDOWN Stainless Air Indoor Uncontrolled Management 111.85-5 3.5.1-Structural Support None A RECOVERY BUILDING Exposed to Air Steel (Extern al) Program (TP-5) 59 Indoor Uncontrolled Required

SBK-L-17 155 I Enclosure 2/ Page 44 U. S. Nuclear Regulatory Commission Table 3.5.2-1 Buildings, Structures Within License Renewa l Summary of Aging Management Evaluation Standard Notes Note Description A Consistent with NUREG-1801 item for component, material , environment, and aging effect. AMP is consistent with NUREG-1 801 AMP.

B Consistent with NUREG-1801 item for component, material , environment, and aging effect. AMP takes some exceptions to NUREG-180 1 AMP.

C Component is different, but consistent with NUREG-1801 item for material , environment, and aging effect. AMP is consistent with NUREG-180 1 AMP.

D Component is different, but consistent with NUREG-1801 item for material , environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.

E Consistent with NUREG-1801 for material , environment and aging effect, but a different aging management program is cred ited or NUREG-1801 identifies a plant-specific aging management program.

F Material not in NUREG-1801 for this component.

G Environment not in NUREG-1801 for this component and material.

H Aging effect not in NUREG-1801 for this component, material and environment combination.

I Aging effect in NUREG-1801 for this component, material and environment combination is not applicable .

J Neither the component nor the material and environment combination is evaluated in NUREG-1801.

501 Not used .

502 Aging effect includes "Fretting or Lockup" due to wear.

503 Crevice and pitting will be included along with loss of material-corrosion due to a saltwater atmosphere environment.

504 Fatigue analysis exists and TLAA applies .

505 Built-up roofing is not in GALL; ll l.A6-12 for elastomer-material is similar, aging effect is similar, environment is same, and AMP is Structures Monitoring .

506 Component is cementitious fire proofing/insulating material and will exhibit similar aging effects as concrete.

507 Spent Fuel Pool temperature< 60°C (<140° F); water chemistry and temperature will be maintained by the Water Chemistry Program.

508 Cracking , loss of bond , and loss of material (spalling, scaling)/corrosion of embedded steel-is not listed in GALL 111 .A.6 as an ag ing effect for concrete in raw water.

Seabrook manages this effect with Structures Monitoring Program.

509 For aging management purposes, buried , below grade , soil , and ground water/ raw & treated water environments are treated the same.

51 O Reduction in concrete anchor capacity is an aging effect that is addressed in LRAM-SUPT.

51 1 At Seabrook Station , Xl. S7 "RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" an d XI. SS "Mason ry Wall Prog ram" are comb ined under Xl.S6 "Structures Monitoring Program.

512 Raw water in lined & unlined concrete sumps.

513 Seabrook Station will age manage this condition through the Fire Protection Program .

514 Seabrook Station will age manage this condition through the Structures Monitoring Program.

515 Increased hardness, shrinkage, or loss of strength of elastomer seals due to weathering is addressed by GALL only for Fire Barri er seals. Seabrook Station will manage such aging effects for non-Fire Barrier elastomer seals with the Structures Monitoring Program.

516 Seabrook Station Structures Monitoring Program wi ll perform concrete testing and rebar inspection to determine the effects of the aggressive groundwater on the concrete. The concrete testing and the rebar inspection will represent all concrete below grade .

517 A fter initial iden tification and determination of the presence of alkali-silica reactivity by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Alkali-Silica Reaction (ASR) Monitoring Program.

SBK-L-17155 I Enclosure 2/ Page 45 U.S. Nuclear Regulatory Commission 519 After initial identification of alkali-silica reaction (ASR) induced building deformation by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Alkali-Silica Reaction (ASR) Monitoring Program and the Building Deformation Monitoring Program.

SBK-L- 171 55 I Enclosure 2/ Page 46 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

+: .* ;1, Aging :i: l'j' I i!'J U1~E1 \3 1' Table Intended Aging EffectRequiring ., 1 Component Type '1:

Material :Environment ,, 1 1 1 ManagE!ment '

1801Vol.' 2 I

'3.X.1 'Nbte l'I 11

Function Management Program Item Item CNT-CE-Carbon Steel Air w/Borated Boric Acid Structural ll l.B2-11 Exposed to Air with Steel Water Leakage Loss of Material Corrosion 3.5 .1-55 A Support (T-25)

Borated Water Leakage (Externa l) Program CNT-CE-Carbon Stee l Air Indoor Structures Structural lll.A1-12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1 -25 A Support (T-11)

Uncontrolled (External) Program Structures CNT-CE-Carbon Steel Structura l Air Outdoor 111.A 1-12 Steel Loss of Material Monitoring 3.5 .1 -25 A , 503 Exposed to Air Outdoor Support (External) (T-11)

Program CNT-CE-Fire Penetration Air Indoor Increased Hardness and Shrin kage Fire Protection Vll. G-1 Seal Exposed to Air Indoor Fire Barrier Elastomer Uncontrolled 3.3.1 -6 1 A and Loss of Strength Program (A-19)

Uncontrol led (External)

Structu res CNT-CE-Re inforced Shelter, Cracking , Loss of Bond , Loss of ll l.A1-4 Concrete Soil (External) Mon itoring 3. 5.1-31 A Concrete Below Grade Protection Material (Spalling , Scaling) (T-05)

Program Stru ctures CNT-CE-Reinforced Structura l Cracking , Loss of Bond , Loss of ll l.A1-4 Concrete Soil (External) Monitoring 3.5.1 -3 1 A Concrete Below Grade Support Material (Spalling, Scaling) (T-05)

Program

SBK-L- 171 55 I Enclosure 2/ Page 47 U. S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluati on 111,1; Aging NUREG Table Intended Aging 'Effect Requiring Component Type Materi al Environment Management 1801 Vol. 2 3.X.1 Note Function Management f.

Program Item .Item Structures Mon itoring Program, Alkali-Silica Reaction (ASR)

CNT-CE-Reinforced Shelter, Monitoring lll.A1-2 A, E, Concrete Soil (External ) Expansion and Cracking 3.5. 1-27 Concrete Below Grade Protection Program & (T-03) 517, 519 Building Deform ati on Monitoring Program Structures Mon itoring Prog ram, Alkali-Silica Reaction (ASR)

CNT-CE-Reinforced Structural Monitoring lll. A1-2 A , E, Concrete Soil (Externa l) Expansion and Cracking 3.5.1 -2 7 Concrete Below Grade Support Program & (T-03) 517, 519 Building Deformation Monitoring Program Increase in Porosity and Structu res CNT-CE-Reinforced Shelter, lll.A 1-5 Concrete Soi l (External) Permeability, Cracking , Loss of Monitoring 3.5. 1-31 A Concrete Below Grade Protection (T-07)

Material (Spalling , Scaling) Program Increase in Porosity and Stru ctures CNT-C E-Reinforced Structural lll.A 1-5 Concrete Soil (External) Permeability, Cra ck ing , Loss of Mon itoring 3. 5.1-31 A Concrete Below Grade Support (T-07)

Material (Spalling, Scal ing) Prog ram

SBK-L-17155 I Enclosure 2/ Page 48 U. S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Stru ctures Summary of Aging Management Evaluation Intended Aging Effect Requiring Aging NUREG I Table Component Type Material Environment 111 1 Managef)1Emt 1801 ~ol . 2 ,' 3.X.1 I Note

,Function Managerrl'ent 1:1 Program , I lteri\ Item Structures CNT-CE-Reinforced Shelter, Increase in Porosity and lll. A1-7 Concrete Soil (External) Monitoring 3.5.1-32 A , 509 Concrete Below Grade Protection Permeability, Loss of Strength (T-02)

Program Structure s CNT-CE-Reinfo rced

Structural Increase in Porosity and lll.A1-7 Concrete Soil (External) Monitoring 3.5.1 -32 A, 509 Concrete Below Grade Support Permeability, Loss of Strength (T-02)

Prog ram Stru ctures CNT-CE-Reinforced Shelter, IJl.A1 -6 Concrete Soil (External) Loss of Material, Cracking Mo nitoring 3.5.1 -26 A Concrete Below Grade Protection (T-01)

Program Structures CNT-CE-Reinforced Structural lll.A1 -6 Concrete Soil (External) Loss of Material , Cracking Monitoring 3.5.1-2 6 A Concrete Below Grade Support (T-0 1)

Program CNT-CE-Reinforced Air Indoor Structures Shelter, Cracking , Loss of Bond , Loss of lll.A1 -9 Concrete Exposed to Air Concrete Uncontrolled Monitoring 3.5.1 -23 A Protection Material (Spalling, Scaling) (T-04)

Indoor Uncontrolled (External) Prog ram CNT-CE-Reinforced Structura l Air Indoor Structures Cracking , Loss of Bond, Loss of lll.A1 -9 Concrete Exposed to Air Pressure Concrete Uncontrolled Monitoring 3.5.1 -23 A Material (Spall ing , Scaling) (T-04)

Indoor Uncontrolled Barrier (External) Prog ram

SBK-L-17155 I Enclosure 2/ Page 49 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function Management

1. ' *I P.rogram ., .,. ltem -i:'i:i I Item CNT-CE-Reinforced Air Indoor Structures Structural Cracking, Loss of Bond, Loss of lll.A1-9 Concrete Exposed to Air Concrete Uncontrolled Monitoring 3.5.1 -23 A Support Material (Spalling, Scaling) (T-04)

Indoor Uncontrolled (External) Program Structures Monitoring Program , Alkali-Silica Reaction (ASR)

CNT-CE-Reinforced Air Indoor Shelter, Monitoring lll.A1-2 A , E 517 ,

Concrete Exposed to Air Concrete Uncontrolled Expansion and Cracking 3.5.1-27 Protection (External)

Program & (T-03) 519 Indoor Uncontrolled Building Deformation Monitoring Program Structures Monitoring Program , Alkali-Silica Reaction CNT-CE-Reinforced Structural Air Indoor (ASR) lll.A1-2 A, E, Concrete Exposed to Air Pressure Concrete Uncontrolled Expansion and Cracking Monitoring 3.5.1 -27 (T-03) 517 , 519 Indoor Uncontrolled Barrier (External) Program &

Building Deformation Monitoring Proqram Structures Monitoring Program , Alkali-CNT-CE-Reinforced Air Indoor Silica Reaction Structural lll.A1-2 A , E, Concrete Exposed to Air Concrete Uncontrolled Expansion and Cracking (ASR) 3.5.1-27 Support (T-03) 517 , 519 Indoor Uncontrolled (External) Monitoring Program &

Building Deformation

SBK-L-17155 I Enclosure 2/ Page 50 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

Aging NU REG Table Intended '" [ll Aging !=ffect Requiring II 'ii *I:

Component Type Material Environment 111 11 M anagem~nt 1801 Vol. 2 3.X.1 Note Function ** ** Management '

Program Item Item Monitoring Program CNT-CE-Reinforced Air Indoor Increase in Porosity and Structures Shelter, lll .A1- 10 Concrete Exposed to Air Concrete Uncontrolled Permeability, Cracking, Loss of Monitoring 3.5.1 -24 A Protection (T-06)

Indoor Uncontrolled (External) Material (Spalling , Scaling) Program CNT-CE-Reinforced Structural Air Indoor Increase in Porosity and Stru ctures lll.A1 -10 Concrete Exposed to Air Pressure Concrete Uncontrolled Permeability, Cracking, Loss of Monitoring 3.5.1-24 A (T-06)

Indoor Uncontrolled Barrier (External) Material (Spalling, Scaling) Program CNT-CE-Reinforced Air Indoor Increase in Porosity and Structures Structural lll.A1 -10 Concrete Exposed to Air Concrete Uncontrolled Permeability, Cracking, Loss of Monitoring 3.5.1-24 A Support (T-06)

Indoor Uncontrolled (External) Material (Spalling, Scaling) Program CNT-CE-Reinforced Structures Air Outdoor Cracking , Loss of Bond , Loss of lll. A 1-9 Concrete Exposed to Air Flood Barrier Concrete Monitoring 3.5.1-23 A (External) Material (Spalling , Scaling) (T-04)

Outdoor Program CNT-CE-Reinforced Structure s Air Outdoor Cracking , Loss of Bond , Loss of lll.A1 -9 Concrete Exposed to Air Missile Barrier Concrete Monitoring 3.5.1 -23 A (External) Material (Spalling, Scaling) (T-04)

Outdoor Program

SBK-L-17155 I Enclosure 2/ Page 5 I U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG .Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 1Vol. 2 3.X.1 Note Function Management I*

Program Item Item :1 CNT-CE-Reinforced Structures Shelter, Air Outdoor Cracking , Loss of Bond, Loss of lll.A1 -9 Concrete Exposed to Air Concrete Monitoring 3.5. 1-23 A Protection (External) Material (Spalling , Scaling) (T-04)

Outdoor Program CNT-CE-Reinforced Structural Structures Air Outdoor Cracking , Loss of Bond, Loss of ll l.A 1-9 Concrete Exposed to Air Pressure Concrete Monitoring 3.5. 1-23 A (External) Material (Spalling, Scaling) (T-04)

Outdoor Barrier Program CNT-CE-Reinforced Structures Structural Air Outdoor Cracking , Loss of Bond , Loss of 111.A1-9 Concrete Exposed to Air Concrete Monitoring 3.5. 1-2 3 A Support (External) Material (Spalling , Scaling) (T-04)

Outdoor Program Structures Monitoring Program, Alkali-Silica Reaction (ASR)

CNT-CE-Reinforced Air Outdoor Monitoring lll.A1 -2 A, E, Concrete Exposed to Air Flood Barrier Concrete Expansion and Cracking 3.5.1-27 (External) Program & (T-03) 517, 519 Outdoor Building Deformation Monitoring Program Structures Monitoring Program , Alkali-CNT-CE-Reinforced Air Outdoor Silica Reaction lll.A1 -2 A, E, Concrete Exposed to Air Missile Barrier Concrete Expansion and Cracking 3.5.1-27 (External) (ASR) (T-03) 517 , 519 Outdoor Monitoring Program &

Building

SBK-L-17155 I Enclosure 2/ Page 52 U.S . Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X. 1 Note Function Management F :1:1*1 I I Program lt~m ,.,. Item *1*,

' ' <ii

.

Deformation Monitoring Program Structures Monitoring Program , Alkali-Silica Reaction (ASR)

CNT-CE-Reinforced Shelter, Air Outdoor Monitoring lll.A1-2 A, E, Concrete Exposed to Air Concrete Expansion and Cracking 3.5.1 -27 Protection (External) Program & (T-03) 517, 519 Outdoor Building Deformation Monitoring Program Structures Monitoring Program , Alkali-Silica Reaction (ASR)

CNT-CE-Reinforced Structural Air Outdoor Monitoring lll.A1 -2 A, E, Concrete Exposed to Air Pressure Concrete Exp ansion and Cracking 3.5.1-27 (External) Program & (T-0 3) 517, 519 Outdoor Barrier Building Deformation Monitoring Program

SBK-L-171 55 I Enclosure 2/ Page 53 U. S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation 1111

' "

Intended I "Agi ri'g Effect Requiring Aging NU REG Table Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function Management Program Item Item Structu res Monitoring Program , Alkali-Silica Reaction CNT-CE-Re inforced (ASR)

Structural Air Outdoor lll.A1-2 A, E, Concrete Exposed to Air Concrete Expansion and Cracking Monito ring 3.5. 1-2 7 Support (External) (T-03) 517 , 519 Outdoor Program &

Buildin g Deformation Monitoring Program CNT-CE-Reinforced Increase in Porosity and Structures Air Outdoor lll.A1 -10 Concrete Exposed to Air Flood Barrier Concrete Permeability, Cracking , Loss of Monitoring 3.5.1-24 A (External) (T-06)

Outdoor Material (Spalling , Scal ing) Prog ram CNT-CE-Reinforced Increase in Porosity and Structures Air Outdoor 111.A1-10 Concrete Exp osed to Air Missile Barrier Concrete Permeability, Cracking , Loss of Monitoring 3.5.1 -24 A (External) (T-06)

Outdoor Material (Spalling, Scaling) Program CNT-CE-Reinforced Increase in Porosity and Structures Shelter, Air Outdoor lll.A1 -10 Concrete Exposed to Air Concrete Permeability, Cracking , Loss of Monitoring 3.5.1-24 A Protection (External) (T-06)

Outdoor Material (Spalling, Scaling) Prog ram CNT-CE-Reinforced Structural Increase in Porosity and Structures Air Outdoor 111.A1 -10 Concrete Exposed to Air Pressure Concrete Permeability, Cracking , Loss of Monitoring 3.5 .1 -24 A (External) (T-06)

Outdoor Barrier Material (Spal ling, Scaling) Program

SBK-L-17155 I Enclosure 2/ Page 54 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function Management

'

Program .. 1:1: .ltem 1 Itel"!' , 1* I CNT-CE-Reinforced Increase in Porosity and Structures Structural Air Outdoor lll.A1 -10 Concrete Exposed to Air Concrete Permeability, Cracking , Loss of Monitoring 3.5.1-24 A Support (External) (T-06)

Outdoor Material (Spalling , Scaling) Program CNT-CE-Reinforced Structures Air Outdoor lll.A1 -6 Concrete Exposed to Air Flood Barrier Concrete Loss of Material, Cracking Monitoring 3.5.1-26 A (External) (T-01 )

Outdoor Program CNT-CE-Reinforced Structures Air Outd oor lll.A1 -6 Concrete Exposed to Air Missile Barrier Concrete Loss of Material , Cracking Monitoring 3.5. 1-26 A (External) (T-01 )

Outdoor Program CNT-CE -Reinforced Structures Shelter, Air Outdoor 111.A1-6 Concrete Exposed to Air Concrete Loss of Materi al, Cracking Monitoring 3.5.1 -26 A Protection (External) (T-01 )

Outdoor Program CNT-CE-Reinforced Structural Structures Air Outdoor lll.A1-6 Concrete Exposed to Air Pressure Concrete Loss of Material, Cracking Monitoring 3.5. 1-26 A (External) (T-01)

Outdoor Barrier Program CNT-CE-Reinforced Structures Structural Air Outdoor lll.A1 -6 Concrete Exposed to Air Concrete Loss of Material, Cracking Monitoring 3.5. 1-26 A Support (External) (T-01)

Outdoor Program

- - -*- --

SBK-L-17155 I Enclosure 2/ Page 55 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

, Aging I NU REG ,,, , Tabl 1e 111

, Intended Aging Effect Requiring II 180'1' Vol:11 2 1

Management 1*11 1

Component Type Material Environment . 3.X.1 Note Function Management

, Program :r Item Item !I Structures CNT-CE-Stainless Steel Structural Stainless Air Outdoor lll. B2-7 Loss of Material Monito ring 3.5.1 -50 A Exposed to Air Outdoor Support Steel (External) (TP-6)

Prog ram Structures Monitoring Program CNT-CEVA-Built-Up Shelter, Air Outdoor Separation, Environmental 111.A6-12 505, H, Roofing Exposed to Air Roofing 3.5 .1 -44 Protection (External) Degradation, Water In-Leakage Building (TP-7) E, 520 Outdoor Deformation Monitoring Proaram CNT-CEVA-Carbon Steel Air w/Borated Boric Acid HELB lll.B2-11 Door Exposed to Air with Steel Water Leakage Loss of Material Corrosion 3.5 .1 -55 A Shielding (T-25)

Borated Water Leakage (External) Program CNT-CEVA-Carbon Steel Air w/Bo rated Boric Acid Shelter, 111. 82-11 Door Exposed to Air with Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A Protection (T-25)

Borated Water Leakage (External Program CNT-CEVA-Carbon Steel Air w/Borated Boric Acid Structural lll.B2-11 Door Exposed to Air with Steel Water Leakage Loss of Material Co rrosion 3.5.1-55 A Support (T-25)

Borated Water Leakage (External Program CNT-CEVA-Carbon Steel Air Indoor Structures HELB lll .A1-12 Door Exp osed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1 -25 A Shielding (T-11)

Uncontrolled (Externa l) Program

SBK-L-171 55 I Enclosure 2/ Page 56 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Intended Aging Effect Re,quiring Aging NU REG Table Component Type , Material Environment Management ,1sq1 vo1 ,,1 , ~ 1 , 1 , 3.X.1 Note Function Management '.I *:11 Prb9 1.'am n ,. Item Item CNT-CEVA-Carbon Steel Air Indoor Stru ctures Shelter, lll.A1 -12 Door Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1 -25 A Protection (T-1 1)

Uncontrolled (External) Program CNT-CEVA-Carbon Steel Air Indoor Structu res Structural 111.A1 -12 Door Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5. 1-25 A Support (T-11)

Uncontrolled (External) Prog ram CNT-CEVA-Carbon Steel Structural Air w/Borated Boric Acid lll. B2-1 1 Exp osed to Air with Pressure Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A (T-25)

Borated Water Leakage Barrier (External) Program CNT-CEVA-Carbon Steel Air w/Borated Boric Acid Structural lll. B2-11 Exposed to Air with Steel Water Leakage Loss of Material Corrosion 3.5.1 -55 A Support (T-25)

Borated Water Leakage (External) Program CNT-CEVA-Carbon Steel Structural Air Indoor Structures lll.A1 -12 Exposed to Air Indoor Pressure Steel Uncontrolled Loss of Material Mo nitoring 3.5.1 -2 5 A (T-1 1)

Uncontrolled Barrier (External) Program CNT-CEVA-Carbon Steel Air Indoor Structures Structural lll.A1 -12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1 -25 A Support (T-11)

Uncontrolled (External) Program

SBK-L- 171 55 I Enclosure 2/ Page 57 U .S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NUREG Tabl e Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function ' .Manag~ment Program Item ' I ' ' Item Structures CNT-CEVA-Carbon Steel Structural Air Outdoor lll. A 1-12 Steel Loss of Material Monitori ng 3. 5.1 -25 A , 503 Exposed to Air Outdoor Support (External) (T-11)

Program CNT-CEVA-Carbon Steel Ai r w/Borated Boric Acid Fire Door Exposed to Ai r lll. B2-11 Fire Barrier Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A with Borated Water (T-25)

(External) Prog ram Leakage CNT-CEVA-Carbon Steel Air w/Borated Boric Acid Fire Door Exposed to A ir Stru ctural lll. B2-11 Steel W ater Leakage Loss of Material Corrosion 3.5.1 -55 A with Borated Water Support (T-25)

(Externa l) Prog ram Leakage CNT-CEVA-Carbon Steel Air Indoor Structures lll.A 1-12 Fire Door Exposed to Air Fire Barrier Steel Uncontrolled Loss of Material Monitoring 3.5.1 -25 A (T- 11)

Indoor Uncontrolled (External) Prog ram CNT-CEVA-Carbon Steel Air Indoor Stru ctures Structural lll. A 1-12 Fire Door Exposed to Air Steel Uncontrolled Loss of Material Monitoring 3.5.1 -25 A Support (T-11)

Indoor Uncontro lled (External ) Program CNT-CEVA-Carbon Steel Air Indoor Fire Protection V ll. G-3 Fire Door Exposed to Air Fire Barrier Steel Uncontrolled Loss of Material 3.3.1-63 A Program (A-21 )

Indoo r Uncontrolled (External)

SBK-L-171 55 I Enclosure 2/ Page 58 U.S. Nuclear Regulatory Commission Tab le 3.5.2-2 Containment Structures Summary of Aging Management Evaluati o n 111,, w 1:1 :i*ill, , , :1:111:: 1'1'11 'l:l'l'il:: ' :II 1Aglng :1.* 1 jJ1 'NU R~,q 1;i' 1r:1 d~b1e 1 ' 1 I * 'I" 11 lnterided Aging Effect Req u i'ri1ng ,ll: J1j::' *. 1 : : ' :~ ': : I ' 'I I 1, ' ' '

Compon ent Type Function Material Enviro nment Management : ' '1

i,"

1 11

'1 111:**'*']I' I 1I 1l'i l:J'.*I:,*1111:Ill 1'1 18011

I Managementll 'Vo ll;12 ,

'*' 'T'l , i. ,,1 1l,11.3.f

' f t 1:lt :;1Note

',,,1:1::

, , Progrc:irn,, 4, 1, 1 ll'll*'i1l lte1T'l ]il:]I:, 1 , ',11 l em,*1,," 1i' liii:J ,,! 11:,i:1 1

CNT-CEVA-Carbon Steel Air Indoor Structural Fire Protection Vll. G-3 Fire Door Exposed to A ir Steel Uncontrolled Loss of Material 3.3. 1-63 A Support Program (A-21)

Indoor Uncontrolled (External)

CNT-CEVA-Carbon Steel Structural Air w/Borated Boric Acid Tech Spec Door Exposed lll. B2-11 Pressure Steel Water Leakage Loss of Material Co rrosio n 3.5.1-55 A to A ir with Borated Water (T-25)

Barrier (External) Program Leakage CNT-CEVA-Carbon Stee l Air w/Borated Boric Acid Tech Spec Door Exposed Structural lll. B2- 11 Steel Water Leakage Loss of Material Corrosion 3.5. 1-55 A to Air with Borated Water Support (T-25)

(External) Program Leakage CNT-CEVA-Carbon Steel Structural Air Indoor Structures lll.A 1-12 Tech Spec Door Exposed Pressure Steel Uncontrolled Loss of Material Monitoring 3.5. 1-25 A (T- 11) to Air Indoor Uncontrolled Barrier (External) Prog ram CNT-CEVA-Carbon Steel Air Indoor Structures Structural Ill.A 1-12 Tech Spec Door Exposed Steel Uncontrolled Loss of Material Monitoring 3.5. 1-25 A Support (T- 11) to Air Indoor Uncontrolled (External) Prog ram CNT-CEVA-Elastomeric Structural Air Indoor Structures Pressure Seal and Caulk Increased Hardness and Shrinkage Vll. G-1 Pressure Elastomer Uncontrolled Mon itoring 3.3 .1-61 E, 515 Exposed to Ai r Indoor and Loss of Strength (A-19)

Barrier (External) Program Uncontrolled

SBK-L-171 55 I Enclosure 2/ Page 59 U.S . Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function ~anager;ner;itl' 1 ~rogram *

Item I 1 Item ;;I Structures CNT-CEVA-Elastomers Expansion I Air Outdoor Increased Hardness and Shrinkage Vll.G-1 Elastomer Monitoring 3.3.1 -61 E, 515 Exposed to Air Outdoor Separation (External) and Loss of Strength (A-19)

Program CNT-CEVA-Fire Air Indoor Increased Hardness and Shrinkage Fire Protection Vll.G-1 Penetration Seal Exposed Fire Barrier Elastomer Uncontrolled 3.3.1 -6 1 A and Loss of Strength Program (A-19) to Air Indoor Uncontrolled (External)

CNT-CEVA-Fire Air Indoor Structures Increased Hardness and Shrinkage Vl l. G-1 Penetration Seal Exposed Fire Barrier Elastomer Uncontrolled Monitoring 3.3. 1-6 1 E,515 and Loss of Strength (A-19) to Air Indoor Uncontrolled (External) Program CNT-CEVA-Penetration Structural Air Indoor Structures Increased Hardness and Sh rinkage Vll.G-1 Seal Exposed to Air Indoor Pressure Elastomer Uncontrolled Monitoring 3.3. 1-6 1 E, 515 and Loss of Strength (A-19)

Uncontrolled Barrier (External) Program Structures CNT-CEVA-Reinforced Shelter, Cracking, Loss of Bond, Loss of lll.A1 -4 Concrete Soil (External) Monitoring 3.5.1-31 A Concrete Below Grade Protection Material (Spalling , Scaling) (T-05)

Program Structures CNT-CEVA-Reinforced Structural Cracking, Loss of Bond, Loss of lll.A1-4 Concrete Soil (External) Monitoring 3.5.1-31 A Concrete Below Grade Support Material (Spalling, Scaling) (T-05)

Program CNT-CEVA-Reinforced Shelter, Structures lll.A1 -2 A, E, Concrete Soil (External) Expansion and Cracking 3.5.1-27 Concrete Below Grade Protection MonitorinQ (T-03) 517 , 519

SBK-L-17155 I Enclosure 2/ Page 60 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function Management 1:1, 111 rl* Program *11 Item 1:1

111 *' "'Jt~rn "'

Program, Alkali-Silica Reaction (ASR)

Monitoring Program &

Building Deformation Monitorina Structures Monitoring Program , Alkal i-Silica Reaction (ASR)

CNT-CEVA-Reinforced Structural lll .A1-2 A, E, Concrete Soil (External) Expansion and Cracking Monitoring 3.5. 1-27 Concrete Below Grade Support (T-03) 517, 519 Program &

Building Deformation Monitoring Increase in Porosity and Structures CNT-CEVA-Reinforced Shelter, lll.A1-5 Concrete Soil (External) Permeability, Cracking, Loss of Monitoring 3.5. 1-31 A Concrete Below Grade Protection (T-07)

Material (Spalling, Scaling) Program Increase in Porosity and Structures CNT-CEVA-Reinforced Structural lll.A1 -5 Concrete Soil (External) Permeability, Cracking , Loss of Monitoring 3.5 .1-31 A Concrete Below Grade Support (T-07)

Material (Spalling , Scaling) Program Structures CNT-CEVA-Reinforced Shelter, Increase in Porosity and lll.A1 -7 Concrete Soil (External) Monitoring 3.5 .1-32 A, 509 Concrete Below Grade Protection Permeability, Loss of Strength (T-02)

Program

SBK-L- 171 55 I Enclosure 2/ Page 6 1 U. S. Nuclear Regulatory Comm ission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

!,I: 1:1:1 ,!:I ::1 ' ' '" .111:' Aging N UREG , Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X. 1 Note Function Management I*' :I; ~ j , ' j 1: Program ,,,, 1 ltem Item Structures CNT-CEVA-Re inforced Structural Increase in Porosity and ll l.A1-7 Concrete Soil (External) Monitoring 3.5. 1-32 A, 509 Concrete Below Grade Support Permeability, Loss of Strength (T-02)

Program Structures CNT-CEVA-Reinforced Shelter, ll l.A1-6 Concrete Soil (External) Loss of Material, Cracking Monitoring 3.5. 1-26 A Concrete Below Grade Protection (T-01 )

Program Structures CNT-CEVA-Reinforced Structural ll l.A1-6 Concrete Soil (External) Loss of Material, Cracking Monitoring 3.5.1-26 A Concrete Below Grade Support (T-01 )

Program CNT-CEVA-Reinforced Air Indoor Structures Cracking , Loss of Bond , Loss of lll.A 1-9 Concrete Exposed to Air Fire Barrier Concrete Uncontrolled Monitori ng 3.5.1-23 A Material (Spalling , Scaling) (T-04)

Indoor Uncontro lled (External) Program CNT-CEVA-Reinforced Air Indoor Structu res Shelter, Cracking, Loss of Bond, Loss of lll.A 1-9 Concrete Exposed to Air Concrete Uncontrolled Monitoring 3.5.1-23 A Protection Material (Spalling , Scaling) (T-04)

Indoor Uncontrolled (External) Program CNT-CEVA-Re inforced Structural Air Indoor Structures Cracking , Loss of Bond , Loss of 111.A 1-9 Concrete Exposed to Air Pressure Concrete Uncontrolled Monitoring 3.5 .1 -23 A Material (Spalling , Scaling) (T-04)

Indoor Uncontrolled Barrier (External) Program

SBK-L-17155 I Enclosure 2/ Page 62 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function rvianagement Program Item Item CNT-CEVA-Reinforced Air Indoor Structu res Structural Cracking , Loss of Bond , Loss of lll.A1 -9 Concrete Exposed to Air Concrete Uncontrolled Monitoring 3.5. 1-23 A Support Material (Spalling, Scaling) (T-04)

Indoor Uncontrolled (External) Program Structures Monitoring Program , Alkali-Silica Reaction (ASR)

CNT-CEVA-Re inforced Air Indoor Monitoring lll.A1 -2 A, E, Concrete Expo sed to Air Fire Barrier Concrete Uncontrolled Expansion and Cracking 3.5.1-27 Program & (T-03) 517 , 5 19 Indoor Uncontrolled (External)

Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR)

CNT-CEVA-Re inforced Air Indoor Shelter, Monitoring lll.A1 -2 A, E, Concrete Exposed to Air Concrete Uncontrolled Expansion and Cracking 3. 5.1 -27 Protection Program & (T-03) 517 , 5 19 Ind oor Uncontro lled (External)

Building Deformation Monitoring Program Structures Monitoring Program , Alkali-CNT-CEVA-Reinforced Structural Air Indoor Silica Reaction lll.A1-2 A, E, Concrete Exposed to Air Pressure Concrete Uncontrolled Expansion and Cracking 3.5 .1 -27 (ASR) (T-03) 517, 5 19 Indoor Uncontrolled Barrier (External)

Monitoring Program &

Building

SBK-L-171 SS I Enclosure 2/ Page 63 U. S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NUREG Table Intended Aging Effect Requiring Component Type Function Material Environment Management Management 1801 Vol,. 2 ':I: 3.~., 1 + Note

'i' Program Item Item Deformation Monitoring Program Structures Monitoring Program , Alkal i-Silica Reaction (ASR)

CNT-CEVA-Reinforced Air Indoor Structural Monitoring lll.A 1-2 A, E, Concrete Exposed to Air Concrete Uncontrolled Expansion and Cracking 3.5.1-27 Support Program & (T-03) 517, 519 Indoor Uncontrolled (External)

Building Deform ation Monitoring Program CNT-CEVA-Reinforced Air Indoor Increase in Porosity and Structures lll.A1 -10 Concrete Exposed to Air Fire Barrier Concrete Uncontrolled Permeability, Cracking, Loss of Monitoring 3.5.1 -24 A (T-06)

Indoor Uncontrolled (External) Material (Spalling, Scaling) Program CNT-CEVA-Reinforced Air Indoor Increase in Porosity and Structures Shelter, lll.A1-10 Concrete Exposed to Air Concrete Uncontrolled Permeability, Cracking, Loss of Monitoring 3.5. 1-24 A Protection (T-06)

Indoor Uncontrolled (External) Material (Spall ing , Scaling) Program CNT-CEVA-Reinforced Structural Air Indoor Increase in Porosity and Structures lll.A 1-10 Concrete Exposed to Air Pressure Concrete Uncontrolled Permeability, Cracking, Loss of Monitoring 3.5. 1-24 A (T-06)

Indoor Uncontrolled Barrier (External) Material (Spalling, Scaling) Program

SBK-L-17155 I Enclosure 2/ Page 64 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation 11

ii I.

~gi ng I.* :j 1-l NUREG 1

Table ' l.Jl!l1 Component Type j*I Intended Material , i'I "

Environment Aging Effect Requiring Management 1801 Vol. 2 3.X.1 Note 1

'

F'u 11ction H*

l*I Management l,i i'l I:; l'I ;: .. :*

Program Item Item CNT-CEVA-Reinforced Air Indoor Increase in Porosity and Structures Structural lll.A1 -10 Concrete Exposed to Air Concrete Uncontrolled Permeability, Cracking, Loss of Monitoring 3.5.1-24 A Support (T-06)

Indoor Uncontrolled (External) Material (Spalling, Scaling) Program CNT-CEVA-Reinforced Structures Air Outdoor Cracking , Loss of Bond, Loss of lll. A1-9 Concrete Exposed to Air Flood Barrier Concrete Monitoring 3.5.1 -23 A (External) Material (Spalling , Scaling) (T-04)

Outdoor Program CNT-CEVA-Reinforced Structures Air Outdoor Cracking, Loss of Bond, Loss of lll.A1-9 Concrete Exposed to Air Missile Barrier Concrete Monitoring 3.5.1-23 A (External) Material (Spalling, Scaling) (T-04)

Outdoor Program CNT-CEVA-Reinforced Structures Shelter, Air Outdoor Cracking , Loss of Bond, Loss of lll.A1 -9 Concrete Exposed to Air Concrete Monitoring 3.5.1-23 A Protection (External) Material (Spalling, Scaling) (T-04)

Outdoor Program CNT-CEVA-Reinforced Structural Structures Air Outdoor Cracking, Loss of Bond, Loss of lll.A1 -9 Concrete Exposed to Air Pressure Concrete Monitoring 3.5. 1-23 A (External) Material (Spalling, Scaling) (T-04)

Outdoor Barrier Program Structures Monitoring Program , Alkali-CNT-CEVA-Reinforced Air Outdoor Silica Reaction lll.A1-2 A, E, Concrete Exposed to Air Flood Barrier Concrete Expansion and Cracking 3.5.1-27 (External) (ASR) (T-03) 517, 519 Outdoor Monitoring Program &

Buildina

SBK-L-171 55 I Enclosure 2/ Page 65 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Stru ctures Summary of Aging Management Evaluation

' 1:1'] ' :lil:j: ii: :pi ,I: ,,

1: +, , . Aging . ~U REG , 111 Table "

Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X. 1 Note Function Management Program Item Item Deformation Monitoring Program Structures Monitoring Program , Alkali-Silica Reaction (ASR)

CNT-CEVA-Reinforced Air Outdoor Monitoring 111.A1 -2 A, E, Concrete Exposed to Air Missile Barrier Concrete Expansion and Cracking 3.5.1-27 (External) Program & (T-03) 517 , 519 Outdoor Building Deformation Monitoring Program Structures Monitoring Program , Alkali-Silica Reaction CNT-CEVA-Reinforced (ASR)

Shelter, Air Outdoor 111.A1-2 A, E, Concrete Exposed to Air Concrete Expansion and Cracking Monitoring 3.5. 1-27 Protection (External) (T-03) 517, 519 Outdoor Program &

Building Deformation Monitoring Proqram Structures Monitoring Program, Alkali-CNT-CEVA-Reinforced Structural Silica Reaction Air Outdoor lll .A1-2 A, E, Concrete Exposed to Air Pressure Concrete Expansion and Cracking (ASR) 3.5.1-27 (External) (T-03) 517 , 519 Outdoor Barrier Monitoring Program &

Building Deformation

SBK-L-17155 I Enclosure 2/ Page 66 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function Management Program Item Item Monitoring Program CNT-CEVA-Reinforced Increase in Porosity and Structures Air Outdoor lll.A1 -10 Concrete Exposed to Air Flood Barrier Concrete Permeability, Cracking, Loss of Monitoring 3.5 .1-24 A (External) (T-06)

Outdoor Material (Spalling , Scaling) Program CNT-CEVA-Reinforced Increase in Porosity and Structures Air Outdoor lll.A1-10 Concrete Exposed to Air Missile Barrier Concrete Permeability, Cracking , Loss of Monitoring 3.5.1 -24 A (External) (T-06)

Outdoor Material (Spalling, Scaling) Program CNT-CEVA-Reinforced Increase in Porosity and Structures Shelter, Air Outdoor lll.A1-10 Concrete Exposed to Air Concrete Permeability, Cracking, Loss of Monitoring 3.5.1 -24 A Protection (External) (T-06)

Outdoor Material (Spalling , Scaling) Program CNT-CEVA-Reinforced Structural Increase in Porosity and Structures Air Outdoor Il l.A 1-10 Concrete Exposed to Air Pressure Concrete Permeability, Cracking , Loss of Monitoring 3.5.1 -24 A (External) (T-06)

Outdoor Barrier Material (Spalling , Scaling) Program CNT-CEVA-Reinforced Structures Air Outdoor 111.A1-6 Concrete Exposed to Air Flood Barrier Concrete Loss of Material, Cracking Monitoring 3.5.1-26 A (External) (T-01)

Outdoor Program

SBK-L-17155 I Enclosure 2/ Page 67 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requ iring 'l*'l:ill Component Type Material Environment 1Management 1so,1IV 0 1. .2 3:x.1 :!. *Note Managerrteni11' . '

1 11' *1:1 Function I Program Item Item CNT-CEVA-Reinforced Structures Air Outdoor ll l.A1-6 Concrete Exposed to Air Missile Barrier Concrete Loss of Material , Cracking Monitoring 3.5. 1-26 A (External) (T-0 1)

Outdoor Program CNT-CEVA-Reinforced Structures Shelter, Air Outdoor lll.A1-6 Concrete Exposed to Air Concrete Loss of Material , Cracking Monitoring 3.5. 1-2 6 A Protection (External) (T-01 )

Outdoor Program CNT-CEVA-Reinforced Structural Structures Air Outdoor lll.A1-6 Concrete Exposed to Air Pressure Concrete Loss of Material, Cracking Mon itoring 3.5 .1-26 A (External) (T-01 )

Outdoor Barrier Program CNT-CEVA-Tech Spec Structural Air Indoor Structures Increased Hardness and Shrinkage V ll. G-1 Seal Exposed to Air Indoor Pressure Elastomer Uncontrolled Monitori ng 3.3. 1-6 1 E, 515 and Loss of Strength (A-19)

Uncontrolled Barrier (External) Program CNT-CEVA-Tech Spec Structural Structures Air Outdoor Increased Hardness and Shrinkage Vl l. G-1 Seal Exposed to Air Pressure Elastomer Monitoring 3.3. 1-6 1 E, 515 (External) and Loss of Strength (A-19)

Outdoor Barrier Program CNT-CEVA-Thermal Air w/Borated Boric Acid Insulation Aluminum Structural lll.B2-6 Aluminum Water Leakage Loss of Material Corrosion 3.5 .1-55 A Jacketing in Air with Support (TP-3)

(External) Program Borated Water Leakage

SBK-L-17155 I Enclosure 2/ Page 68 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NUREG , [I 1,,,,,Table,, ,

Intended Aging Effect Requiring 1,1 l:f: ,, ,ilfManag~ment ,,,1: ::. 1801 Vol!l 2 '

1 1 Component Type Material "" Environment 3.X.1 1 "Note Management'

'

Function Program Item Item CNT-Cl-Carbon Steel Door Air w/Borated Boric Acid Structural lll.B2-11 Exposed to Air with Steel Water Leakage Loss of Material Corrosion 3.5.1 -55 A Support (TP-25)

Borated Water Leakage (External) Program CNT-Cl-Carbon Steel Door Air Indoor Structures Shelter, lll.A4-5 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5, 1-25 A Protection (T-11)

Uncontrolled (External) Program CNT-Cl-Carbon Steel Air w/Borated Boric Acid Structural lll.B2-11 Exposed to Air with Steel Water Leakage Loss of Material Corrosion 3.5, 1-55 A Support (TP-25)

Borated Water Leakage (External) Program CNT-Cl-Carbon Steel Air Indoor Structures Structural lll.A4-5 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3,5 ,1-25 A Support (T-11 )

Uncontrolled (External) Program Nooe Nooe CNT-Cl -Conduit Fire Wrap Air Indoor Deformation/reduction in Building Stainless lll.B1 .2-7 Exposed to Air Indoor Fire Barrier Uncontrolled s tructural capacity Deformation 3.5.1 -59 A, E, 520 Steel (TP-5)

Uncontrolled (External) directly/indirectly due to the Monitoring expansion of concrete Program Nooe Nooe CNT-Cl-Conduit Fire Wrap Air w/Borated Deformation/reduction in Building Stainless lll.B2-9 Exposed to Air with Fire Barrier Water Leakag e structural capacity Deformation 3.5, 1-59 A , E, 520 Steel (TP-4)

Borated Water Leakage (External) directly/indirectly due to the Monitoring expansion of concrete Program

SBK-L- 17155 I Enclosure 2/ Page 69 U.S . Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Ag i ng Management Eva luation Intended

'*1 .: !* .' ,'11 I*/ :i: 'r 1 11*1'1'1 11, "

1 1

.,,

1ll11 A gi ng Effect 'Recjui ~i n g I'

f.Iii.

, .

Ag ing .. 1 NUREG ' . *i:,:Table /i1 111 1

'I" 3 .x.1r1:i:1,,' :1::r '

Component Type Materia l Environment

11 .I ' I LI {I ' :11 ,*1*1+1 11 '!'1 ' I ' ' Ii: ~*I ' 1'1 i:i Me1 nage rT)el 1t, 'j"1'I , 1'ao;1 ,v o 1'..12 Iii 1'I.ll',: *:1: !Note Function J 1lfl 1l:ii:l 1Management1lf 1

l 1H1111 J) :Iii;' '* 1 11 1

1::1!11' P ~ograri p111'J!l111i l'i:ilili:l 1tem ,11J.l 1!,,w. 1tem 1 * '*;i:1J: 11:1:

1

,. 1:1:1, il:'i, .1:1 1

,,,*I:

I""**' 1 * "I.*

1

.,, T Nooe Nooe CNT-C l-Heat Shield Air w/Borated Deformation/reducti on in Building Stainless lll. B2-9 Exposed to Air with Fire Barrier Water Leakage structural capacity Deformation 3.5 .1 -59 A , E, 520 Steel (TP-4)

Borated W ater Leakage (External) directly/indirectly due to the Monitoring expansion of concrete Program Nooe Nooe CNT-Cl-Radiant Heat Air Indoor Deformation/reduction in B uilding Stainless lll. B1 .2-7 Shield Exposed to Air Fire Barrier Uncontrolled structural capacity Deformation 3.5.1-59 A, E, 520 Steel (TP-5 )

Indoor Uncontrolled (External) directly/indirectly due to the Monitoring expansion of concrete Program CNT-C l-Reinforced Air Indoor Structures Cracking, Loss of Bond, Loss of lll. A4-3 Concrete Exposed to Air Fire Barrier Concrete Uncontrolled Monitori ng 3.5.1 -23 A Material (Spalling , Scaling) (T-04)

Indoor Uncontrolled (External) Program CNT-Cl-Reinforced Air Indoor Structures Cracking , Loss of Bond, Loss of lll.A4-3 Concrete Exposed to Air Flood Barrier Concrete Uncontrolled Monitoring 3.5.1 -23 A Material (Spalling, Scaling) (T-04)

Indoor Uncontrolled (External) Prog ram CNT-C l-Reinfo rced Air Indoor Structu res Cracking , Loss of Bond , Loss of 111.A 4-3 Concrete Exposed to Air Missile Barrier Concrete Uncontrolled Monitori ng 3.5 .1-23 A Material (Spalling, Scaling) (T-04)

Indoor Uncontrolled (External) Program CNT-Cl-Reinforced Air Indoor Structures Structural Cracking, Loss of Bond, Loss of 111.A4-3 Concrete Exposed to Air Concrete Uncontrolled Monitoring 3.5 .1 -23 A Support Material (Spalling, Scaling) (T-04)

Indoor Uncontrolled (External) Program

SBK-L-171 55 I Enclosure 2/ Page 70 U.S. Nuclear Regulatory Commission Tabl e 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

,,

Ag ing ,, NUREG Table Intended Aging Effect Requiring Component Type Material Environment Managell!ent 1801 Vo l. 2 3.X.1 Note Function Management Program Item Item Structures Monitoring Program , Alkal i-Silica Reaction CNT-C l-Re inforced Air Indoor (ASR) lll.A4-2 A, E, Concrete Exposed to Air Fire Barrier Concrete Un controlled Expan sion and Cracking Monitoring 3.5.1-27 (T-03) 517, 519 Indoor Uncontrolled (External) Program &

Building Deforma tion Monitoring Proaram Structures Mon itoring Prog ram, Alkali-Silica Reaction (ASR)

CNT-Cl-Reinforced Air Indoor Monitoring lll.A4-2 A , E, Concrete Exposed to Air Flood Barrier Concrete Uncontrolled Expan sion and Cra cking 3.5.1 -27 Program & (T-03) 517, 519 Indoor Uncontrolled (External)

Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR)

CNT-Cl-Reinforced Air Indoor Monitoring lll.A4-2 A, E, Concrete Exposed to Air Missile Barrier Concrete Uncontrolled Expansion and Cra cking 3.5.1-27 Program & (T-03) 517, 519 Indoor Uncontrolled (External)

Building Deformation Monitoring Program CNT-C l-Reinforced Air Indoor Structures Structural lll.A4-2 A, E, Concrete Exposed to Air Concrete Uncontrolled Expan sion and Cracking Monitoring 3.5.1 -27 Support (T-03) 517, 519 Indoor Uncontrolled (External) Program , Alkali-

SBK-L- 17155 I Enclosure 2/ Page 71 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

1 ;I t !ill! .n . , . . . . *If' 1 NU.~E~11 11,ii:.

1 l:1 Table ji;, 1:i I 1

- !** A 11'1.in... 11. Effect

{l:.1'1.ir*11:1 tl'!*i" Re '"umn

! .

11:1*1' 1111 1* * * , Aging

, * .***. :1:111~111 ~ah~'gelne~i*I

Intended Component Type Material Environment r1 :'i11'iJ1l 1I :;l,J:1' MaDagemenf 'lil 11*" t 801,:Vol1 :1 211: 1 'I u 1~.).< !' 1 1' 11*.**1 ,j1 '( ~ ote Function ,*; ,I I ' I :I:,;. 1,f I, ' j'1 p I ' *lh!*11l'l:H1 . *il1:1 1t~m'i .,1 ...j~ I1 1 1 I

Item ' 1I' 1'1 , * : ,

, , I*:; rogp\lm 1.."' *

l *f:i:.

'1'!

Silica Reaction (ASR)

Monitoring Program &

Building Deformation Monitoring Proaram CNT-Cl-Reinforced Air Indoor Increase in Porosity and Structures lll. A4-4 Concrete Exposed to Air Fire Barrier Concrete Uncontrolled Permeability, Cracking, Loss of Monitoring 3.5.1-24 A (T-06)

Indoor Uncontrolled (External) Material (Spalling, Scaling) Program CNT-Cl-Reinforced Air Indoor Increase in Porosity and Structures lll.A4-4 Concrete Exposed to Air Flood Barrier Concrete Uncontrolled Permeability, Cracking, Loss of Monitoring 3.5.1-24 A (T-06)

Indoor Uncontrolled (External) Material (Spalling, Scaling) Program CNT-Cl-Reinforced Air Indoor Increase in Porosity and Structures llJ.A4-4 Concrete Exposed to Air Missile Barrier Concrete Uncontrolled Permeability, Cracking, Loss of Monitoring 3.5.1-24 A (T-06)

Indoor Uncontrolled (External) Material (Spalling, Scaling) Program CNT-Cl-Reinforced Air Indoor Increase in Porosity and Structures Structural lll.A4-4 Concrete Exposed to Air Concrete Uncontrolled Permeability, Cracking , Loss of Monitoring 3.5 .1 -24 A Support (T-06)

Indoor Uncontrolled (Exte rnal) Material (Spalling , Scaling) Program Nooe Nooe Structures CNT-Cl-Stainless Steel Air w/Borated Reduction in s tructural capacity Structural Stainless Monitoring lll. B1 .29 Exposed to Air with Water Leakage directly. Indirectly due to 3.5 .1 -59 A, E, 520 Support Stee l Program, (TP-4)

Borated Water Leakage (External) expansion and cracking of Building con crete Deformation

SBK-L-171 55 I Enclosure 2/ Page 72 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Eva luatio n Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 VoL 2 3.X.1 Note Functi on Management Program Item Item Monitorin g Program Nooe Structures Nooe Monitoring CNT-C l-Stainless Stee l Air Indoor Reduction in s truc tural capacity Structural Stain less Program, lll. B1.2-7 Exposed to Air Indoor Uncontrolled directly. Indirectly due to 3.5.1 -5 9 A, E, 520 Support Steel Building (TP-5)

Uncontro lled (External) expansion and cracking of Deformation con crete Monitoring Proqram Structu res CNT-C l-Stainless Steel Structural Stainless Raw Water V.01-15 Loss of Material Monitoring 3.2 .1 -7 E, 514 Raw W ater Support Steel (External) (E-01)

Program CNT-CS- Reinforced Air Indoor ASME Section Cracking , Loss of Bond , Loss of ll.A1 -7 Concrete Exposed to Air Fire Barrier Concrete Uncontrol led XI , Subsection 3.5.1-1 A Material (Spalling , Scaling) (C-05)

Indoor Uncontro lled (External) IWL Program CNT-CS- Re inforced Ai r Indoor ASME Section Cracking , Loss of Bond , Loss of ll.A1 -7 Concrete Exposed to Air Flood Barrier Concrete Uncontrolled XI , Subsecti on 3. 5.1-1 A Material (Spalling , Scaling) (C-05)

Indoor Uncontro lled (External) IWL Program CNT-CS- Reinforced Air Indoor ASME Section HELB Cracking , Loss of Bond , Loss of ll.A 1-7 Concrete Exposed to Air Concrete Uncontrolled XI , Subsection 3. 5.1-1 A Shielding Material (Spalling , Scaling) (C-05)

Indoor Uncontrolled (External) IWL Program

SBK-L-171 55 I Enclosure 2/ Page 73 U. S. Nuclear Regul atory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging 'NUREG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X. 1 Note Function Management Program Item Item*

CNT-CS- Reinforced Ai r Indoor AS ME Secti on Cracking , Loss of Bond , Loss of ll.A 1-7 Concrete Exposed to Air Missile Barrier Concrete Uncontrolled XI , Subsecti on 3.5.1-1 A Material (Spalling , Scaling) (C-05)

Indoor Uncontro lled (External) IWL Program CNT-CS- Re inforced Air Indoor AS ME Sectio n Shelter, Cracking , Loss of Bond, Loss of ll.A 1-7 Concrete Exposed to Air Concrete Uncontrolled XI , Subsection 3. 5.1-1 A Protection Material (Spalling, Scaling ) (C-05)

Indoor Uncontrol led (External) IWL Prog ram CNT-CS- Reinforced Air Indoor ASME Section Cracking , Loss of Bond, Loss of 11.A1-7 Concrete Exposed to Air Shield ing Concrete Uncontrolled XI, Subsection 3.5 .1-1 A Material (Spalling , Scaling) (C-05)

Indoor Uncontro lled (External) IWL Program CNT-CS- Reinforced Structural Air Indoor ASME Section Cracking , Loss of Bond , Loss of ll.A1-7 Concrete Exposed to Ai r Pressure Concrete Uncontrolled XI , Subsecti on 3.5.1 -1 A Material (Spalling , Scaling) (C-05)

Indoor Uncontrol led Barrier (External) IWL Program CNT-CS- Reinforced Air Indoor ASME Section Structural Cracking , Loss of Bond , Loss of ll.A 1-7 Concrete Exposed to Air Concrete Uncontrolled XI, Su bsectio n 3. 5.1 -1 A Support Material (Spalling , Scaling) (C-05)

Indoor Uncontro lled (External ) IWL Program CNT-CS- Re inforced Air Indoor Fire Protection Vll. G-29 Concrete Exposed to Air Fire Barrier Concrete Uncontrolled Loss of Material 3.3.1 -67 A Program (A-9 1)

Indoor Uncontrolled (External)

SBK-L-17155 I Enclosure 2/ Page 74 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment 11 l*I Management 1801 Vol. :2 3,.X. 1 Note Function '* 'Management 11. '

Program Item

Item CNT-CS- Reinforced Air Indoor Fire Protectio n Vll.G-29 Concrete Exp osed to Air Flood Barrier Concrete Uncontrolled Loss of Material 3.3 .1 -67 A Program (A-91 )

Indoor Uncontrolled (Externa l)

CNT-CS- Reinforced Air Indoor HELB Fire Protection Vll.G-29 Concrete Exposed to Air Concrete Uncontrolled Loss of Material 3.3 .1 -67 A Shielding Program (A-91)

Ind oor Uncontrolled (External)

CNT-CS- Reinforced Air Indoor Fire Protection Vll.G-29 Concrete Exp osed to Air Missile Barrier Concrete Uncontrolled Loss of Material 3.3 .1-67 A Program (A-91 )

Indoor Uncontrolled (External)

CNT-CS- Reinforced Air Indoor Shelter, Fire Protection Vll.G-29 Concrete Exposed to Air Concrete Uncontrolled Loss of Material 3.3.1-67 A Protection Prog ram (A-91 )

Indoor Uncontro lled (External)

CNT-CS- Re inforced Air Indoor Fire Protection Vll.G-29 Concrete Exposed to Air Shielding Concrete Uncontro lled Loss of Material 3.3.1-67 A Prog ram (A-91 )

Indoor Uncontrolled (External)

CNT-CS- Reinforced Structural Air Indoor Concrete Exposed to Air Fire Protection Vl l. G-29 Pressure Concrete Uncontrolled Loss of Material 3.3.1 -67 A Program (A-9 1)

Indoor Uncontrolled Barri er (External)

SBK-L-17155 I Enclosure 2/ Page 75 U.S . Nuclear Regulatory Commission Table 3.5. 2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function ' Management Program Item Item CNT-CS- Reinforced Air Indoor Structural Fire Protection Vl l. G-29 Concrete Exposed to Air Concrete Uncontrolled Loss of Material 3.3 .1 -67 A Support Program (A-91 )

Indoor Uncontrolled (External)

ASME Section XI, Subsection IWL Program Alkali-Silica CNT-CS- Reinforced Air Indoor Reaction (ASR) ll.A1 -3 A , E, Concrete Exposed to Air Fire Barrier Concrete Uncontrolled Expansion and Cracking Monitoring 3.5. 1-15 (C-04) 517, 519 Indoor Uncontrolled (External) Program Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program Alkali-Silica CNT-CS- Reinforced Air Indoor Reaction (ASR) ll.A1-3 A, E, Concrete Exposed to Air Flood Barrier Concrete Uncontrolled Expansion and Cracking Monitoring 3.5.1-15 (C-04) 517, 519 Indoor Uncontrolled (External) Program Building Deformation Monitoring Proaram ASME Section XI, Subsection CNT-CS- Reinforced Air Indoor HELB IWL Program ll.A1-3 A , E, Concrete Exposed to Air Concrete Uncontrolled Expansion and Cracking 3.5.1 -15 Shielding (C-04) 517, 519 Indoor Uncontrolled (External)

Alkali-Silica Reaction (ASR)

SBK-L-17 155 I Enclosure 2/ Page 76 U.S. Nuclear Regulatory Commission Tabl e 3.5.2-2 Containment Struct ures Summary of Aging Management Evaluation Aging "I NUREG 'I Table 1 1 n~.ende,d Aging Effect Req 6iring ' 1 1801 Vo l. 2 1'1 1

Component Type Material Environment Management1' 3.X. 1 Note 11 ,,,.

Funct ion Management Program Item Item Monitoring Prog ram B uilding Deform ation Monitoring Proqram ASME Secti on XI , Subsecti on IW L Program Alkali-Si lica CNT-CS- Reinforced Air Indoor Reacti on (ASR)

ILA 1-3 A, E, Concrete Exposed to Air Missile Barrier Concrete Uncontrolled Expansion and Cracking Monitori ng 3.5.1-15 (C-04) 517, 519 Indoor Uncontrolled (External) Program B uilding Deformation Monitoring Proaram ASME Section XI , Subsecti on IWL Program A lkali-Silica CNT-CS- Reinforced Air Indoor Reaction (ASR)

Shelter, ILA1-3 A , E, Concrete Exposed to Air Concrete Uncontrolled Expansion and Cracking Monitoring 3.5.1-15 Protection (C-04) 517, 519 Indoor Uncontro lled (Externa l) Program B uilding Deformation Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 77 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation ti. ,I ' Aging .1 NU REG Table Intended Aging Effect Requiring Component ,J"ype Material Environment ' Management 1801 Vol. 2 3.X.1 Note 1 Function 1:1 I I Management I l'i' Program Item 11 Item*

'* '\l ASME Section XI, Subsection IWL Program Alkali-Silica CNT-CS- Reinforced Air Indoor Reaction (ASR)

ILA1 -3 A, E, Concrete Exposed to Air Shielding Concrete Uncontrolled Expansion and Cracking Monitoring 3.5.1-15 (C-04) 517, 519 Indoor Uncontrolled (External) Program Building Deformation Monitoring Program ASME Section XI, Subsection IWL Program Alkali-Silica CNT-CS- Reinforced Structural Air Indoor Reaction (ASR)

ILA1-3 A, E, Concrete Exposed to Air Pressure Concrete Uncontrolled Expansion and Cracking Monitoring 3.5.1 -15 (C-04) 517, 519 Indoor Uncontrolled Barrier (External) Program Building Deformation Monitoring Proqram ASME Section XI, Subsection IWL Program Alkali-Silica CNT-CS- Reinforced Air Indoor Structural Reaction (ASR) ll.A1-3 A, E, Concrete Exposed to Air Concrete Uncontrolled Expansion and Cracking 3.5.1-15 Support Monitoring (C-04) 517, 519 Indoor Uncontrolled (External)

Program Building Deformation Monitoring

SBK-L-17155 I Enclosure 2/ Page 78 U.S. Nuclear Regulatory Commission Tabl e 3.5.2-2 Containment Stru ctures Summary of Aging Management Evaluation

,. *u1:: ,

I I Aging NU REG Table

1 :Ii Intended Aging Effect Requiring 1 1

Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note :;

Functi on *1:1: Management

I 'l',1111 1

., :i Program Item ,Item Program Fire Protection CNT-CS- Reinforced Air Indoor Program Vll.G-28 Concrete Exposed to Air Fire Barrier Concrete Uncontrolled Concrete Cra cking and Spalling 3.3.1 -65 A (A-90)

Indoor Uncontrolled (External)

CNT-CS- Reinforced Air Indoor Fire Protection Vll.G-28 Con crete Exposed to Air Flood Barrier Concrete Uncontrolled Concrete Cracking an d Spalling 3.3.1-65 A Program (A-90)

Indoor Uncontrolled (External)

CNT-CS- Reinforced Air Indoor HELB Fire Protection Vll. G-28 Con crete Exposed to Air Concrete Uncontrol led Concrete Cracking and Spalling 3.3.1-65 A Shielding Program (A-90)

Indoor Uncontrolled (External)

CNT-CS- Rei nforced Air Indoor Fire Protection Vll.G-28 Concrete Exposed to Air Missile Barrier Concrete Uncontrolled Concrete Cracki ng and Spal ling 3.3.1 -65 A Program (A-90)

Indoor Uncontrolled (External)

CNT-CS- Reinforced Air Indoor Shelter, Fire Protection Vll. G-28 Concrete Exposed to Air Co ncrete Uncontrolled Concrete Cracking and Spalling 3.3.1 -65 A Protection Program (A-90)

Indoor Uncontrolled (Externa l)

SBK-L-17 155 I Enclosure 2/ Page 79 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

';' .. I Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vo l. 2 3.X.1 Note Function Management Program Item Item.

CNT-CS- Reinforced Air Indoor Fire Protection Vl l. G-28 Concrete Exposed to Air Shielding Concrete Uncontrolled Concrete Cracking and Spalling 3.3.1 -65 A Program (A-90)

Indoor Uncontrolled (External)

CNT-CS- Reinforced Structural Air Indoor Fire Protection Vll .G-28 Concrete Exposed to Air Pressure Concrete Uncontrolled Concrete Cracking and Spalling 3.3 .1 -65 A Prog ram (A-90)

Indoor Uncontrolled Barrier (External)

CNT-CS- Re inforced Air Indoor Structural Fire Protection Vll.G-28 Concrete Exposed to Air Concrete Uncontrolled Concrete Cracking and Spalling 3.3.1 -65 A Support Program (A-90)

Indoor Uncontrolled (External)

CNT-CS- Reinforced Air Indoor Increase in Porosity and AS ME Section Concrete Exposed to Air Fire Barrier ll.A1-4 Concrete Uncontrolled Permeability, Cracking, Loss of XI , Subsection 3.5 .1-1 A, 516 (C-03)

Indoor Uncontrolled (External) Material (Spalling , Scaling) IWL Program CNT-CS- Reinforced Air Indoor Increase in Porosity and ASME Section ll.A1-4 Concrete Exposed to Air Flood Barrier Concrete Uncontrolled Permeability, Cracking, Loss of XI, Subsection 3. 5.1 -1 A, 516 (C-03)

Indoor Uncontrolled (External) Material (Spalling , Scaling) IW L Program CNT-CS- Reinforced Air Indoor Increase in Porosity and ASME Section HELB ll.A1-4 Concrete Exposed to Air Concrete Uncontrolled Permeability, Cracking, Loss of XI, Subsection 3.5.1-1 A, 516 Shielding (C-03)

Indoor Uncontrolled (External) Material (Spalling, Scaling) IWL Program

SBK-L- 171 55 I Enclosure 2/ Page 80 U. S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

,, ,. *1:1 1 ill .. ' :1;;.j',. *r

'Intended ' '

I , '*., l1 l*lil;11'\ *11:111'1' ii lllij!l!il ',1!11111*1!1,:li

Aging ' Effect Requiring 'I 11 I 1*1 Ag,1ri g 1*:1111llil':1I ,,:i.,.I NUREG 11 j :11 1:,1:i11Tabfe.

"I '11.Fl,::1: ,,:,:,:1* ' ' 111 Component Type .Material Environment 1 ,, Nbte *,'*

' 1:1,lil PrograM ' " I u11:l:l1. 1tem.I ,' 'I' *: 1 ,,'.~i;~

11 .a, 9 1 , 1 ~0'-, 2 ,

Function

.;.I i::' .~ .:. ;' . ;*I' 1:k, .: .,,,

Manage~~nt :I '

.1 111

.I. '

. I' 111 Management 111 1

'II 1 .

1,I* 1:::1*

I I ' 1' CNT-CS- Reinforced Air Indoor Increase in Porosity and ASME Section 11.A1-4 Concrete Exposed to Air Missile Barrier Concrete Uncontrolled Permeability, Cracking, Loss of XI, Subsection 3.5. 1-1 A, 516 (C-03)

Indoor Uncontrolled (External) Material (Spalling, Scaling) IWL Program CNT-CS- Reinforced Air Indoor Increase in Porosity and ASME Section Shelter, ll.A1-4 Concrete Exposed to Air Concrete Uncontrolled Permeability, Cracking, Loss of XI, Subsection 3.5. 1-1 A, 516 Protection (C-03)

Indoor Uncontrolled (External) Material (Spalling , Scaling) IWL Program CNT-CS- Reinforced Air Indoor Increase in Porosity and ASME Section ll.A1 -4 Concrete Exposed to Air Shielding Concrete Uncontrolled Permeability, Cracking , Loss of XI, Subsection 3.5. 1-1 A, 516 (C-03)

Indoor Uncontrolled (External) Material (Spalling, Scaling) IWL Program CNT-CS- Reinforced Structural Air Indoor Increase in Porosity and ASME Section 11.A1 -4 Concrete Exposed to Air Pressure Concrete Uncontrolled Permeability, Cracking, Loss of XI, Subsection 3.5 . 1-1 A, 516 (C-03)

Indoor Uncontrolled Barrier (External) Material (Spalling, Scaling) IWL Program CNT-CS- Reinforced Air Indoor Increase in Porosity and ASME Section Structural 11.A1 -4 Concrete Exposed to Air Concrete Uncontrolled Permeability, Cracking, Loss of XI, Subsection 3.5.1-1 A, 516 Support (C-03)

Indoor Uncontrolled (External) Material (Spalling, Scaling) IWL Program CNT-CS-Airlock Hatch Structural Air Indoor V.F-6 Sight Glass Exposed to Air Pressure Glass Uncontrolled None None 3.2. 1-52 A (EP-15)

Indoor Uncontrolled Barrier (External)

SBK-L-17155 I Enclosure 2/ Page 81 U. S. Nuclear Regulatory Commission Tabl e 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

,.

. n.11 f!, 111 , JiV' ,,, *1 Aging NU REG Table

':;:11r';*1:1,YI Intended , Aging Effect Requiring +

Component Type Material Environment 1 1 1 Management 18.01 Vol. 2 3.X.1 Note Function 1 11 .. 1r ', Management

' I 11 111:-:11:, 1" 1'1:1':111:1:11: 11:1' jli , 'l*l*I' ' Program Item 11 . Item CNT-CS-Carbon Steel Structural Air w/Borated Boric Acid Electrical Penetration lll.B2-11 (T-Pressure Steel Water Leakage Los s of Material Corrosion 3.5.1 -55 A Exposed to Air with 25)

Barrier (External) Program Borated Water Leakage CNT-CS-Carbon Steel Air w/Borated Boric Acid Electrical Penetration Structural 111.B2-11 (T-Steel Water Leakage Loss of Material Corrosion 3.5 .1-55 A Exposed to Air with Support 25)

(External) Program Borated Water Leakage CNT-CS-Carbon Steel Structural Air Indoor ASME Section Electrical Penetration ll.A3-1 Pressure Steel Uncontrolled Loss of Material XI, Subsection 3.5.1-18 A Exposed to Air Indoor (C-12)

Barrier (External) IWE Program Uncontrolled CNT-CS-Carbon Steel Air Indoor ASME Section Electrical Penetration Structural ll.A3-1 Steel Uncontrolled Loss of Mate rial XI, Subsection 3.5 .1-18 A Exposed to Air Indoor Support (C-12)

(External) IWE Program Uncontrolled CNT-CS-Carbon Steel Structural Air w/Borated Boric Acid Equipment Hatch Exposed 111. B2-11 (T-Pressure Steel Water Leakage Loss of Material Corrosion 3.5.1 -55 A to Air with Borated Water 25)

Barrier (External) Program Leakage CNT-CS-Carbon Steel Air w/Borated Boric Acid Equipment Hatch Exposed Structural lll.B2-11 (T-Steel Water Leakage Loss of Material Corrosion 3.5 .1-55 A to Air with Borated Water Support 25)

(External) Program Leakage

SBK-L-17155 I Enclosure 2/ Page 82 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

' r :1: Aging NU REG *Table .

Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function Management Program Item Item CNT-CS-Carbon Steel Structural Air Indoor ASME Sectio n ll.A3-6 Equ ipment Hatch Exposed Pressure Steel Uncontrolled Loss of Material XI, Subsection 3.5.1 -18 A (C-16) to Air Indoor Uncontrolled Barrier (External) IWE Program CNT-CS-Carbon Steel Ai r Indoor ASME Sectio n Structural ll.A3-6 Equipment Hatch Exposed Stee l Uncontrolled Los s of Material XI, Subsection 3.5. 1-18 A Support (C-16) to Air Indoor Uncontrolled (External) IWE Program CNT-CS-Carbon Steel Structural Air w/Borated Boric Acid lll. B2-11 (T-Exposed to Air with Pressure Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A 25)

Borated W ater Leakage Barrier (External) Program CNT-CS-Carbon Steel Air w/Borated Bo ri c A cid Structu ral lll.B2-11 (T-Exposed to Air with Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A Support 25)

Borated W ater Leakage (External) Program CNT-CS-Carbon Steel Structura l Air w/Borated Boric Acid Exposed to Air with lll.B2-11 (T-Pressure Steel Water Leakage Loss of Material Corrosion 3.5.1 -55 A Borated Water Leakage for 25)

Barrier (External) Program HVAC Penetrations CNT-CS-Carbon Steel Air w/Borated Boric Acid Exposed to Air with Structural lll.B2-11 (T-Steel Water Leakage Loss of Material Corrosion 3.5.1 -5 5 A Borated Water Leakage for Su pport 25)

(External) Program HVAC Penetrations

SBK-L- 171 55 I Enclosure 2/ Page 83 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Function Material Environment Management ,y; Management 1801 Vol. 2 3.X.1 Note I ..

Program Item Item 1. +

CNT-CS-Carbon Steel Structural Air Indoor ASME Section ll.A1-11 Exposed to Air Indoor Pressure Steel Uncontrolled Loss of Material XI, Subsection 3.5.1 -6 A (C-09)

Uncontrolled Barrier (External) IWE Program CNT-CS-Carbon Steel Air Indoor ASME Section Structural ll.A1-11 Exposed to Air Indoor Steel Uncontrolled Loss of Material XI , Subsection 3.5.1 -6 A Support (C-09)

Uncontrolled (External) IWE Program CNT-CS-Carbon Steel Structural Air Indoor ASME Section Exposed to Air Indoor ll.A3-1 Pressure Steel Uncontrolled Loss of Material XI, Subsection 3.5.1-18 A Uncontrolled For HVAC (C-12)

Barrier (External) IWE Program Penetrations CNT-CS-Carbon Steel Air Indoor ASME Section Exposed to Air Indoor Structural ll.A3-1 Steel Uncontrolled Loss of Material XI , Subsection 3.5.1 -18 A Uncontrolled For HVAC Support (C-12)

(External) IWE Program Penetrations CNT-CS-Carbon Steel Mechanical (Piping) Structural Air w/Borated Boric Acid lll.B2-11 (T-Penetration Exposed to Air Pressure Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A 25) with Borated Water Barrier (External) Program Leakage CNT-CS-Carbon Steel Mechanical (Piping) Air w/Borated Boric Acid Structu ral lll. B2-11 (T-Penetration Exposed to Air Steel Water Leakage Loss of Material Corrosion 3.5.1 -55 A Support 25) with Borated Water (External) Program Leakage

SBK-L- 17155 I Enclosure 2/ Page 84 U. S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

+ .I ' J'I 'lili1, "' 1:1+ Hl1l;ii! *,,.1 , 1:*' . . Aging , NU REG Table Component Type Intended Function Material Environment ' 1 ** : 1:t~:l ~ g*Management 11.p::. fff~.8t.1 ~~q~i~n~111*

.1,1,11,,"," 111... "1* r ,

+, 111 Management 1801if\'ol::2j.1:I 1:1nll 3'. x. 1 11

I "' N pte

. :L 1-1.I:, *:1 i< , i: ir J ,, ,,, .. ,:,:1,. ir:1:1r , 1, , , :!11 l11:11: Pr~gr~m 1* :1::t1,:, *I* ii: :*ii 11

.':Iii, j"J!li!j1 ltem l '11 11i!l1tem **ji111 1111

* ,*1*j*I Ill I' CNT-CS-Carbon Steel Structural Air Indoor ASME Section Mechanical (Piping) ll.A3-1 Pressure Steel Uncontrolled Loss of Material XI, Subsection 3.5. 1-18 A Penetration Exposed to Air (C-12)

Barrier (External) IWE Program Indoor Uncontrolled CNT-CS-Carbon Steel Air Indoor ASME Section Mechanical (Piping) Structural ll.A3-1 Steel Uncontrolled Loss of Material XI, Subsection 3.5.1-18 A Penetration Exposed to Air Support (C-12)

(External) IWE Program Indoor Uncontrolled CNT-CS-Carbon Steel Structural Air w/Borated Boric Acid Personnel Hatch Exposed lll. B1 .1-11 Pressure Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A to Air with Borated Water (TP-25)

Barrier (External) Program Leakage CNT-CS-Carbon Steel Air w/Borated Boric Acid Personnel Hatch Exposed Structural lll.B1 .1-11 Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A to Air with Borated Water Support (TP-25)

(External) Program Leakage CNT-CS-Carbon Steel Structural Air Indoor ASME Section ll.A3-6 Personnel Hatch Exposed Pressure Steel Uncontrolled Loss of Material XI, Subsection 3.5.1-18 A (C-16) to Air Indoor Uncontrolled Barrier (External) IWE Program CNT-CS-Carbon Steel Air Indoor ASME Section Structural ll .A3-6 Personnel Hatch Exposed Steel Uncontrolled Loss of Material XI, Subsection 3.5.1-18 A Support (C-16) to Air Indoor Uncontrolled (External) !WE Program

SBK-L-17155 I Enclosure 2/ Page 85 U.S . Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

.

Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X. 1 Note Function Management II ,;: !:1: Program Item Item

'"

ASME Section XI, Subsection IWE Program ,

CNT-CS-Elastomers Structures Structural Air Indoor Electrical Penetration Loss of Sealing , Leakage Through Monitoring ll.A3-7 Pressure Elastomer Uncontrolled 3.5.1 -16 A, E, 520 Assembly Exposed to Air Containment Program & (C- 18)

Barrier (External)

Ind oor Uncontrolled Building Deformation Monitoring Proaram CNT-CS-Mechanical (Piping) Penetration Structural Air Indoor ASME Section Stainless ll .A3-2 Stainless Steel Flued Head Pressure Uncontrolled Cracking XI, Subsecti on 3.5.1 -10 A Steel (C-15)

Exp osed to Air Indoor Barrier (External) IWE Program Uncontrolled CNT-CS-Mechanical (Piping) Penetration Air Indoor ASME Section Structural Stainless ll.A3-2 Stain less Steel Flued Head Uncontrolled Cracking XI , Subsecti on 3.5.1-10 A Support Steel (C- 15)

Exposed to Air Indoor (External) IWE Program Uncontrolled Nooe Structures CNT-CS-Mechanica l Nooe Monitoring (Piping) Penetration Structu ral Air w/Borated Reduction in structural capacity Program, Stainless lll. B2-9 Stainless Steel Flued Head Pressure Water Leakage directly. Indirectly due to Building 3.5.1 -5 9 A, 520 Steel (TP-4)

Exposed to Air with Barrier (External) expansion and cracking of Deformation Borated Water Leakage concrete Monitoring Program Nooe CNT-CS-Mechanica l Nooe Structures (Piping) Penetration Air w/Borated Reduction in s tructural capacity Monitoring Structural Stainless lll. B2-9 Stainless Steel Flued Head Water Leakage directly. Indirectly due to Program, 3.5.1-59 A , 520 Support Steel (TP-4)

Exposed to Air with (External) expansion and cracking of Building Borated Water Leakage concrete Deformation Monitorina

SBK-L-17155 I Enclosure 2/ Page 86 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X. 1 Note Function Management' Program Item

Item Program ASME Section CNT-CS-Reinforced She lter, Cracking , Loss of Bond , Loss of ll.A1 -7 Concrete Soil (External) XI, Subsection 3.5.1-1 A Concrete Below Grade Protection Material (Spalling, Scaling) (C-05)

IWL Program ASME Section CNT-CS-Reinforced Structural Cracking , Loss of Bond , Loss of ll.A1 -7 Concrete Soil (External) XI, Subsection 3.5.1-1 A Concrete Below Grade Support Material (Spalling , Scaling) (C-05)

IWL Program ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR)

CNT-CS-Reinforced Shelter, ll.A1-3 A , E, Concrete Soil (External) Expansion and Cracking Monitoring 3.5.1 -15 Concrete Below Grade Protection (C-04) 517, 519 Prog ram Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program CNT-CS-Reinforced Structural ll.A1 -3 A, E, Concrete Soi l (External) Expansion and Cracking 3.5.1-15 Concrete Below Grade Support (C-04) 517 , 519 Alkali-Silica Reaction (ASR)

Mon itorinq

SBK-L-17 155 I Enclosure 21 Page 87 U. S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Struct ures Summary of Agi ng Management Evaluati on I'."

1: .I

I :1:,I i*'I I* Aging 1 NU REG Table Intended ' 'J:i Ag ing Effect Requi ring Component Ty pe Material ' Enviro nment ,,J.I: Management 1801 Vo l. 2 3.X. 1 Note

' Fu nction I *l*M I . Management

'

I*! :*1~ 1 1 '

1 I 111:1 1* 1n, 1

Program Item lt~ m .,.,.

Prog ram B uilding Deformation Monitorin g Program Increase in Porosity and ASME Section CNT-CS-Reinforced Shelter, ll.A1-4 Concrete Soil (External) Permeability, Cracking , Loss of XI, Subsectio n 3.5.1 -1 A, 516 Concrete Below Grade Protection (C-03)

Material (Spalling, Scaling) IWL Program Increase in Porosity and ASME Section CNT-CS-Reinforced Structural ll.A 1-4 Concrete Soil (External) Permeability, Cracking, Loss of XI , Subsecti on 3.5 .1-1 A, 51 6 Concrete Below Grade Support (C-03)

Material (Spalling, Scaling) IWL Program AS ME Section XI, Subsection IWL Program Alka li-S ilica Reaction (ASR) A, 509, CNT-CS-Reinforced Shelter, Increase in Porosity and ll.A1 -6 Concrete Soil (External) Mo nitoring 3.5. 1-15 516, E, Concrete Below Grade Protection Permeability, Loss of Strength (C-02)

Prog ram 517, 519 B uilding Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program A, 509, CNT-CS-Reinfo rced Structural Increase in Porosity and ll.A1 -6 Concrete Soil (External) 3. 5.1 -15 516, E, Concrete Below Grade Support Permeability, Loss of Strength (C-02)

A lkali-Silica 517, 5 19 Reacti on (ASR)

Monitorinq

SBK-L- 17155 I Enclosure 21 Page 88 U. S. Nuclear Regulatory Commission Table 3.5.2-2 Containm ent Structures Summary of Aging Management Evaluation 1.1 I'

,', 1;1:, ,, 1:l,p1 l 11,l1l*!li:;:1!v '

'!' Aging NU REG Table Intended

111

, .,, ' Aging Effect Requiring Component Type Material . Environment 11:1 1;, Management 1801 Vol. 2 3.X.1 Note I, Function ,I: ,. :I* *j}l{l'.IH *il'I ,Management ' +

,,, m1 1

'i'1it' .,,,w111:1 :11, :Iii ,,,1,1111"1 "': 111 11., Program ,1,tel'Tl

Item

' '* 1 Program Building Deformation Monitoring Program Nooe Structures Nooe CNT-CS-Stainless Steel Monitoring Reduction in structural capacity Electrical Penetration Structural Air w/Borated Program, Stainless directly. Indirectly due to lll.B2-9 Assembly Exposed to Air Pressure Water Leakage Building 3.5. 1-59 A, 520 Steel expansion and cracking of (TP-4) with Borated Water Barrier (External) Deformation concrete Leakage Monitoring Program Nooe Structures CNT-CS-Stainless Steel Nooe Monitoring Electrical Penetration Structural Air w/Borated Reduction in structural capacity Program, Stainless lll. B2-9 Assembly Exposed to Air Pressure Water Leakage directly. Indirectly due to Building 3.5. 1-59 A, 520 Steel (TP-4) with Borated Water Barrier (External) expansion and cracking of Deformation Leakage concrete Monitoring Program CNT-CS-Stainless Steel Structural Air Indoor ASME Section Electrical Penetration Stainless ll .A3-2 Pressure Uncontrolled Cracking XI, Subsection 3.5.1-10 A Assembly Exposed to Air Steel (C-15)

Barrier (External) IWE Program Indoor Uncontrolled CNT-CS-Stainless Steel Air Indoor ASME Section Electrical Penetration Structural Stainless 11.A3-2 Uncontrolled Cracking XI, Subsection 3.5.1 -10 A Assembly Exposed to Air Support Steel (C-15)

(External) IWE Program Indoor Uncontrolled

SBK-L-17155 I Enclosure 2/ Page 89 U.S . Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring ,

Component Type Material Environment Management 1801 'Vol. 2 3.X.1 Note Function Management Program Item Item

Nooe Structures Nooe Monitoring CNT-CS-Stainless Steel Air w/Borated Reduction in s tructural capacity Program, Stainless lll.B2-9 Exposed to Air with Shielding Water Leakage directly. Indirectly due to Building 3.5.1 -59 A , 520 Steel (TP-4)

Borated Water Leakage (External) expansion and cracking of Deformation concrete Monitoring Program Nooe Structures Nooe Monitoring CNT-CS-Stainless Steel Air w/Borated Reduction in s tructural capacity Program, Structural Stainless lll.B2-9 Exposed to Air with Water Leakage directly. Indirectly due to Building 3.5.1-59 A, 520 Support Steel (TP-4)

Borated Water Leakage (External) expansion and cracking of Deformation concrete Monitoring Program CNT-CS-Stainless Steel Air Indoor ASME Section Stainless 11.A3-2 Exposed to Air Indoor Shield ing Uncontrolled Cracking XI, Subsection 3.5.1 -10 A Steel (C-15)

Uncontrolled (External) IWE Program CNT-CS-Stainless Steel Air Indoor ASME Section Structural Stainless ll.A3-2 Exposed to Air Indoor Uncontrolled Cracking XI , Subsection 3.5. 1-10 A Support Steel (C-15)

Uncontrolled (External) IWE Program Nooe Structures CNT-CS-Stainless Steel Nooe Monitoring Fuel Transfer Tube Air w/Borated Reduction in s tructural capacity Expansion I Stainless Program, lll.B2-9 Bellows Exposed to Air Water Leakage directly. Indirectly due to 3.5.1 -59 A, 520 Separation Steel Building (TP-4) with Borated Water (External) expansion and cracking of Deformation Leakage concrete Monitoring Program

SBK-L- 171 55 I Enclosure 2/ Page 90 U. S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structu res Sum mary of Aging Management Evaluati on Component Type

, '" I I

,

1 l ~tend~d 1:;

I

l. w .. ::!!1:1~1:*

Material, '1!11

,1*,1,,: ,I,

. . 11:-1 Environment Aging Effect Requ iring I

Ii " '

IJ}ging

Manag~m ent l iI l II'. :l1ao' 11 I I: 11"1111' 1

1

ll'INu~EG I 'ii 1w11Tabl e 11v o 1I. 2 1

":.

, 3.~ . 1

,:,11 1 Note

,'l'I ',

i: ,1JI: ;!:*'11:1 -11111::*' :i,;

,,. Function :l:.::!11 I Management 1 1

,:

Progr,a T ' II ' Item Item' .1:1: 1'1 '111'1;:*!:1!!

"'

Nooe Structures CNT-CS-Stainless Steel Nooe Monitoring Fuel Transfer Tube Structural Air w/Borated Reduction in structural capacity Program, Stainless lll. B2-9 Bellows Exposed to Air Pressure Water Leakage directly. Indirectly due to Building 3.5 .1 -5 9 A, 520 Steel (TP-4) with Borated Water Barrier (External) expansion and cracking of Deformation Leakage concrete Monitoring Program CNT-CS-Stainless Stee l Air Indoor ASME Secti on Fuel Transfer Tube Expansion I Stainless ll.A3-2 Uncontrolled Cracking XI, Subsection 3.5 .1 -10 A Bellows Exposed to Air Separation Steel (C-15)

(External) IWE Program Indoor Uncontro lled CNT-CS-Stainless Steel Structural Air Indoor ASME Section Fue l Transfer Tube Stainless ll.A3-2 Pressure Uncontrolled Cracking XI, Subsection 3.5.1 -10 A Bellows Exposed to Air Steel (C-15)

Barrier (External) IWE Prog ram Indoor Uncontrolled Nooe Structures Nooe Monitoring CNT-CS-Stainless Steel Structural Air w/Borated Reduction in s tructural capacity Program, Fuel Transfer Tube Stainless lll. B2-9 Pressure Water Leakage directly. In directly due to Building 3.5. 1-5 9 A, 520 Exposed to Air with Steel (TP-4)

Barrier (External) expansi on and cracking of Deformation Borated W ater Leakage concrete Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 91 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation

.. ' 1'f1 1**' 1:1." Aging NU REG Table Intended Environment :11 ;j.' if, . Aging ,Effect Requiring Component Type Material 11 Management 1801 Vol. 2 3.X.1 Note Function 1 ' * ' *11 1* 11 1 1 Mariagement i:

1

, ,, 11:1 :1',I! <I; Program lt~m Item Nooe Structures Nooe Monitoring CNT-CS-Stainless Steel Air w/Borated Reduction in structural capacity Program, Fuel Transfer Tube Structural Stainless lll.B2-9 Exposed to Air with Support Steel Water Leakage directly. Indirectly due to Building (TP-4) 3.5.1-59 I A, 520 (External) expansion and cracking of Deformation Borated Water Leakage concrete Monitoring Program CNT-CS-Stainless Steel Structural Air Indoor ASME Section Fuel Transfer Tube Stainless ll.A3-2 Exposed to Air Indoor Pressure Steel Uncontrolled Cracking XI, Subsection (C-15) 3.5.1-10 IA Barrier (External) !WE Program Uncontrolled CNT-CS -Stainless Steel Air Indoor ASME Section Fuel Transfer Tube Structural Stainless ll.A3-2 Uncontrolled Cracking XI, Subsection 3.5.1-10 I A Exposed to Air Indoor Support Steel (C-15)

(External) !WE Program Uncontrolled Nooe Structures Nooe Monitoring CNT-CS-Thermal Reduction in structural capacity Program, Insulation Stainless Steel Structural Stainless Air w/Borated lll.B2-9 directly. Indirectly due to Building 3.5.1-59 A, 520 Jacketing in Air with Support Steel Water Leakage (TP-4) expansion and cracking of Deformation Borated Water Leakage concrete Monitoring Program ASME Section A XI, Subsection IWL Program CNT-CS- Reinforced Raw Water Cracking due to expansion/ ll.A1-3 Concrete Exposed to Raw Missile Barrier I Concrete 3.5.1-15 (External) reaction with aggregates Alkali-Silica (C-04)

Water Reaction (ASR) E, 517 Monitoring ProQram 519

SBK-L-17155 I Enclosure 2/ Page 92 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation i ,!:i::l!,.,liJ* I

'. Aging I*

NU REG Table I

1:i'11:1r1I Intended I I~ I' :I: ' I Aging Effect Requiring ;:1"':11::1::

Component 1T~pe Material Environment , I Management 1801 Vol. 2 3.X.1

Note :'HI Function ., Management . 1:1 ' 'i'I

'I' ill I' Program Item Item Building Deformation Monitoring Program ASME Section XI, Subsection IWL Program A

Alkali-Silica CNT-CS- Reinforced Reaction (ASR)

Shelter, Raw Water Cracking due to expansion/ ll.A1 -3 Concrete Exposed to Raw Concrete Monitoring 3.5 .1-15 E, 517 Protection (External) reaction with aggregates (C-04)

Water Program Building E, 519 Deformation Monitoring Program ASME Section XI, Subsection IWL Program A Alkali-Silica CNT-CS- Reinforced Structural Reaction (ASR)

Raw Water Cracking due to expansion/ ll .A1 -3 Concrete Exposed to Raw Pressure Concrete Monitoring 3.5.1-15 (External) reaction with aggregates (C-04)

Water Barrier Program E, 517 Building Deforma tion E, 519 Monitoring Proaram ASME Section A CNT-CS- Reinforced XI , Subsection Stru ctural Raw Water Cracking due to expansion/ IWL Program ll.A1-3 Concrete Exposed to Raw Concrete 3.5.1-15 Support (External) reaction with aggregates (C-04)

Water Alkali-Silica Reaction (ASR) E, 517

SBK-L- 17 155 I Enclosure 2/ Page 93 U.S. Nuclear Regulatory Commission Table 3.5.2-2 Containment Structures Summary of Agi ng Management Evaluation

i*i 'i*I :h

1:

Intended

1 1

11

' :ij:

I! 'i'i!ii:jtl'll 111 Aging Effect Requiring

:lllt1 :I:' l'i 'II i'!,, 1!111~

H I iii

'II 'Agi ,, 'j"H Ii', ng 11r1'1 11:II1111NUREG I .li!:11

,:1*1 ***:'(I I Ill

' *1 1' :*'*'!'I' li 111,:' i:llh1 able 1 I 1:: 111 Ill I

1 :.

Managem,ent '1,1

1801 1Yio1. 2, ., 3:x. 1 l1 II di Note .

Com ponent Type .

I:! ':i Function Material Environment Management Program 1

11 1tem

Item J, *Ir r* I ' I.

'!:.:i:'.!'.l:;;i:1:::.

'

1 1ll':.,;1:li,'I Monitoring Program E, 519 Building Deformation Monitoring Program Table 3.5.2-2 Containment Structures Summary of Ag ing Management Evaluation Standard Notes Note Description A Consistent with NUREG-1801 item for component, material , environment, and aging effect. AMP is consistent with NUREG-180 1 AMP.

B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NU REG-180 1 AMP.

C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP.

D Component is different, but consistent with NUREG-1801 item for material , environment, and aging effect. AMP takes some exceptions to NU REG-180 1 AMP.

E Consistent with NUREG-1801 for material , environment and aging effect, but a different aging management program is cred ited or NUREG-180 1 identifies a plant-specifi c aging management program .

F Material not in NUREG-1801 for this component.

G Environment not in NUREG-1801 for this component and material.

H Aging effect not in NUREG-1801 for this component, material and environment combination.

I Aging effect in NUREG-1801 for this component, material and environment combination is not applicable.

J Neither the component nor the material and environment combination is evaluated in NUREG-1801.

501 Not used.

502 Aging effect includes "Fretting or Lockup" due to wear.

503 Crevice and pitting will be included along with loss of material-corrosion due to a saltwater atmosphere environment.

SBK-L- 171 55 I Enclosure 2/ Page 94 U. S. Nuclear Regulatory Commission 504 Fatigue analysis exists and TLAA applies .

505 Built-up roofing is not in GAL; lll.A6-12 is for elastomer-material is similar, aging effect is similar, environment is same, and AMP is Structures Monitoring.

506 Component is cementitious fire proofing/insulating material and will exhibit similar aging effects as concrete.

507 Spent Fuel Pool temperature< 60°C (<140° F), water chemistry and temperature will be maintained by the Water Chemistry Program.

508 Cracking, loss of bond, and loss of material (Spalling, Scaling)/corrosion of embedded steel-is not listed in GALL 111.A.6 as an aging effect for concrete in raw water.

Seabrook manages this effect with Structures Monitoring Program .

509 For aging management purposes, buried, below grade, soil, and ground water/ raw & treated water environments are treated the same.

51 O Reduction in concrete anchor capacity is an aging effect that is addressed in LRAM-S UPT.

511 At Seabrook Station, Xl,.S7 "RG 1. 127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" and Xl,.S5 "Masonry Wall Program" are combined under Xl,.S6 "Structures Monitoring Program".

512 Raw water in lined & unlined concrete sumps.

513 Seabrook Station will age manage this condition through the Fire Protection Program .

514 Seabrook Station will age manage this condition through the Structures Monitoring Program .

515 Increased hardness, shrinkage, or loss of strength of elastomer seals due to weathering is addressed by GALL only for Fire Barrier seals. Seabrook Station will manage such aging effects for non-Fire Barrier elastomer seals with the Structures Monitoring Program.

516 Seabrook Station Structures Monitoring Program will perform concrete testing and rebar inspection to determine the effects of the aggressive groundwater on the concrete. The concrete testing and the rebar inspection will represent all concrete below grade.

517 After initial i den tification and determination of the presence of alkali-silica reactivity by the Structures Mon itoring Program, Seabrook Station will age manage this condition through th e Alkali-Silica Reacti on (ASR) Monitoring Program.

519 After initial identification of alkali-silica reaction (ASR) induced building deformation by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Alkali-Silica Reaction (ASR) Monitoring Program and the Building Deformation Monitoring Program.

520 After initial identification of alkali-silica reaction (ASR) induced building deformation affecting p lant equipment and components by th e Structures Monitoring Program, Seabrook Station will age manage this condition through the Building Deformation Monitoring Program.

SBK-L-17155 I Enclosure 2/ Page 95 U.S. Nuclear Regulatory Commission Tabl e 3.5.2-4 Miscellaneous Yard Stru ctures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function Management Program Item Item MYS -Aluminum STATION Structures Stru ctural Air Outdoor 111.82-7 BLACKOUT STRUCTURES Aluminum Crack Initiation and Growth Monitoring 3.5.1 -50 H, 514 Support (External) (Tp-6)

Exposed to Weather Program MYS - Aluminum STATION Structures Stru ctural Air Outdoor 111.82-7 BLACKOUT STRUCTURES Aluminum Loss of Material Monitoring 3.5.1-50 A Support (External) (TP-6)

Exposed to Weather Program MYS - Carbon Steel Air Indoor Structures CONTROL ROOM MAKEUP Structural lll.A3-12 Steel Uncontrolled Loss of Material Monitoring 3.5.1 -25 A AIR INTAKE STRUCTURE Support (T-11)

(External) Program Air Indoor Uncontrolled MYS - Carbon Steel Structures CONTROL ROOM MAKEUP Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A , 503 AIR INTAKE STRUCTURE Support (External) (T-11)

Program Exposed to Weather MYS - Carbon Steel Door Air Indoor Structures ENCLOSURE FOR Structural lll.A3-12 Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A CONDENSATE STORAGE Support (T-11)

(External) Program TANK Air Indoor Uncontrolled MYS - Carbon Steel Door Structures ENCLOSURE FOR Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1 -25 A, 503 CONDENSATE STORAGE Support (External) (T-11)

Program TANK Exposed to Weather

SBK-L-17155 I Enclosure 2/ Page 96 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluati on 1

1 i1 l ' 1 1 X'9l~~ , Effe~t Requiring 1~1 1

I *! :i:w * )I; Aging NU REG Table Intended :I: I Component Type Material Environment Mar.iagement . ,1801 Vol. 2 F 11 3.X.1 Note Function , :: ~ anagement ,,

11 I II *.I ,, l'i 11* ' ~rogram , 'Item*'* ' Item'

I

"I MYS - Carbon Steel Door Air Indoor Structures STATION BLACKOUT Structural lll.A3-12 Stee l Uncontrolled Loss of Material Monitoring 3.5.1-25 A STRUCTURES Ai r Indoor Support (T-11)

(External) Program Uncontrolled MYS - Carbon Steel Door Structures STATION BLACKOUT Structural Air Outdoor lll.A3- 12 Steel Loss of Material Monitoring 3.5. 1-25 A, 503 STRUCTURES Exposed to Support (External) (T-11)

Program Weather MYS - Carbon Steel Air Indoor Structures ENCLOSURE FOR Structural lll.A3-12 Steel Uncontrolled Loss of Material Monitoring 3.5.1 -25 A CONDENSATE STORAGE Support (T-11)

(External) Program TANK Air Indoor Uncontrolled MYS - Carbon Steel Stru ctures ENCLOSURE FOR Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1 -25 A, 503 CONDENSATE STORAGE Support (External) (T-11)

Program TANK Exposed to W eather MYS - Carbon Steel NON SAFETY RELATED Air Indoor Stru ctures Structural 111.A3-12 ELECTRICAL DUCT Steel Uncontrolled Loss of Material Monitoring 3.5 .1-25 A Suppo rt (T-1 1)

BANKS/MANH OLES Air (External) Program Indoor Uncontrolled MY S-Ca~onS~e lN ON Structures SAFETY RELATED Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1 -25 A , 503 ELECTR ICAL MANHOLES Support (External) (T-11)

Program Exposed to Weather

SBK-L-17155 I Enclosure 2/ Page 97 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation

'

. 1*1 ' :1: 1 1:'1 Aging NU REG Table Intended Aging Effect Requiring Note',.,

Component Type Material Environment Management 1801 Vol. 2 3.X.1 Function 1

' M'!n~gement Program *' Item Item ... ,..

"

MYS - Carbon Steel SAFETY Air Indoor Structures RELATED ELECTRICAL Structural lll.A3-12 Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A DUCT BANKS/MANHOLES Support (T-11)

(External) Program Air Indoor Uncontrolled MYS - Carbon Steel SAFETY Structures RELATED ELECTRICAL Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A, 503 DUCT BANKS/MANHOLES Support (External) (T-11)

Program Exposed to Weather MYS - Carbon Steel Air Indoor Structures SERVICE WATER ACCESS Structural lll.A3-12 Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A VAULT Air Indoor Support (T-11)

(External) Program Uncontrolled MYS - Carbon Steel Air Indoor Structures STATION BLACKOUT Structural lll.A3-12 Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A STRUCTURES Air Indoor Support (T-11)

(External) Program Uncontrolled MYS - Carbon Steel Structures STATION BLACKOUT Shelter, Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1 -25 A, 503 STRUCTURES Exposed to Protection (External) (T-11)

Program Weather MYS - Carbon Steel Structures STATION BLACKOUT Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A , 503 STRUCTURES Exposed to Support (External) (T-11)

Program Weather

SBK-L-17155 I Enclosure 2/ Page 98 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Stru ctures Summary of Aging Management Evaluation 1

/j1: :I: 1'* *, !I: 111 'J11ili . l* 1 :r

,1 Aging *. NU REG 1 Table Intended Aging Effect Requiring '11

Component Type Material Environment * 'Managen:ient 1801 Vol. 2 3:X.1 Note Function Management Program Item Item MYS - Concrete CONTROL Air Indoor Cracking , Loss of Bond, Structures ROOM MAKEUP AIR Structural lll.A3-9 Concrete Uncontrolled Loss of Material (Spalling, Monitoring 3.5.1 -23 A INTAKE STRUCTURE Air Support (T-04)

(External) Scaling) Program Indoor Uncontrolled Structures Monitoring Program, Alkali-Silica Reaction MYS - Concrete CONTROL Air Indoor (ASR)

ROOM MAKEUP AIR Structural lll.A3-2 A, E, Concrete Unco ntrolled Expansion and Cracking Monitoring 3.5 .1-27 INTAKE STRUCTURE Air Support (T-03) 517, 519 (External) Program &

Indoor Uncontrolled Building Deformation Monitoring Program MYS - Concrete CONTROL Increase in Porosity and Air Ind oor Stru ctures ROOM MAKEUP AIR Stru ctural Permeability, Cracking , Loss lll.A3-10 Concrete Uncontrolled Monitoring 3.5.1 -24 A INTAKE STRUCTURE Air Support of Material (Spa lling, (T-06)

(External) Program Ind oor Uncontrolled Scaling)

MYS - Concrete CONTROL Cracking , Loss of Bond , Structures ROOM MAKEUP AIR Structural Ground Water/Soil lll.A3-4 Concrete Loss of Material (Spalling, Monitoring 3. 5. 1-3 1 A INTAKE STRUCTURE Below Support (External) (T-05)

Scaling) Program Grade Structures Monitoring Program , Alkali-Silica Reaction MYS - Concrete CONTROL (ASR)

ROOM MAKEUP AIR Structural Ground Water/Soil lll.A3-2 A, E, Concrete Expansion and Cracking Monitoring 3.5.1-27 INTAKE STRUCTURE Below Support (Exte rnal) (T-03) 517, 519 Program &

Grade Building Deformation Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 99 U.S. Nuclear Regulatory Commission Tabl e 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Eva luati on

,i.,1:1 . n , , 1

' Aging NUREG Table '11 Environment 111 1:1 I.Ii/Aging ~f1'r 1ct ~e~uiring i'I '*'

Intended Component Type Material 1 Management 1801 Vol. 2 3.X. 1 Note ifr 11:1 l,1[Jl lllJ M~r;i~ge~e1:1t )1: 1 1 1

, :*

Function Ill. I,',,

, II '** " ,.,:1:i,1l:i, 1:1 :IJ :1:1 11' lj/l*1 Pr~grarn', 11 1111**i**111l111 il'1' lteni,ll,

1 ' . ,:

i*:I,I fil,j lteryt1,tll'i

- 1+ :11 1 Iii ,1 MYS - Concrete CONTROL Increase in Porosity and Structures ROOM MAKEUP AIR Structural Ground Water/Soil Permeability, Cracking , Loss 111.A3-5 Concrete Monitoring 3.5.1-31 A INTAKE STRUCTURE Below Support (External) of Material (Spalling , (T-07)

Program Grade Scaling)

MYS - Concrete CONTROL Increase in Porosity and Structures ROOM MAKEUP AIR Structural Ground Water/Soil lll.A3-7 Concrete Permeability, Loss of Monitoring 3,5.1-32 A, 509 INTAKE STRUCTURE Below Support (External) (T-02)

Strength Program Grade MYS - Concrete CONTROL Structures ROOM MAKEUP AIR Structural Ground Water/Soil 111.A3-6 Concrete Los s of Material, Cracking Monitoring 3.5.1 -26 A INTAKE STRUCTURE Below Support (External) (T-01)

Program Grade MYS - Concrete CONTROL Cracking , Loss of Bond , Structures ROOM MAKEUP AIR Air Outdoor lll.A3-9 Missile Barrier Concrete Loss of Material (Spalling, Monitoring 3.5.1-23 A INTAKE STRUCTURE (External) (T-04)

Scaling) Program Exp osed to Weather MYS - Concrete CONTROL Cracking , Loss of Bond , Structures ROOM MAKEUP AIR Structural Air Outdoor lll.A3-9 Concrete Loss of Material (Spalling, Monitoring 3.5.1-2 3 A INTAKE STRUCTURE Support (External) (T-04)

Scaling) Program Exposed to Weather Structures Monitoring Program , Alkali-MYS - Concrete CONTROL Silica Reaction ROOM MAKEUP AIR Air Outdoor (ASR) lll.A3-2 A, E, Missile Barrier Concrete Expansion and Cracking 3.5.1-27 INTAKE STRUCTURE (External) Monitoring (T-03) 517 , 519 Exp osed to Weather Program &

Building Deformation Monitorinq

SBK-L-17155 I Enclosure 2/ Page 100 U. S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation

.,

i'l":I

'

l:i i'),1 '1:1 I Aging '* NU REG Table ' ' l'!J l:!!:!,1 1 1.i.*:*:f::

Intended Ir Aging Effect Requiring Component Type Function Material ' Environment Management Management 1801 Vol. 2 3.X. 1 Noteill

,,

1 11:1 1il1iil 1!1'1.: 11:1J!:i:' "' I

, Program Item I.tern

"'"' lil'*!I' *

Program Structures Monitoring Program , Alkali-Silica Reaction MYS - Concrete CONTROL (ASR)

ROOM MAKEUP AIR Structural Air Outdoor Monitoring lll.A3-2 A, E, Concrete Expansion and Cracking 3.5.1-27 INTAKE STRUCTURE Support (External) Program & (T-03) 517, 519 Exposed to Weather Building Deformation Monitoring Program MYS - Concrete CONTROL Increase in Porosity and Structures ROOM MAKEUP AIR Air Outdoor Permeability, Cracking, Loss lll.A3-10 Missile Barrier Concrete Mon itoring 3. 5. 1-24 A INTAKE STRUCTURE (External) of Material (Spalling, (T-06)

Program Exposed to Weather Scaling)

MYS - Concrete CONTROL Increase in Porosity and Structures ROOM MAKEUP AIR Structural Air Outdoor Permeability, Cracking, Loss lll.A3-10 Concrete Monitoring 3.5.1-24 A INTAKE STRUCTURE Support (External) of Material (Spalling , (T-06)

Program Exposed to Weather Scaling)

MYS - Concrete CONTROL Structures ROOM MAKEUP AIR Air Outdoor lll.A3-6 Missile Barrier Concrete Loss of Material , Cracking Mo nito ring 3. 5. 1-26 A INTAKE STRUCTURE (External) (T-0 1)

Program Exposed to Weather

SBK-L-17155 I Enclosure 2/ Page 101 U.S . Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation 1: ,1. I ':II' 1* I 'I*

1Agjng

1:1*

1: 1:' '1, NUREG 1

' Table t

,1:

Intended '* Aging Effect Requiring Component Type Material Environment Management * ,1801 V ol'. 2 '3.X. 1 Note Function Management 1 Program Item item MYS - Concrete CONTROL Structures ROOM MAKEUP AIR Structural Air Outdoor 111.A3-6 Concrete Loss of Material , Cracking Monitoring 3.5. 1-26 A INTAKE STRUCTURE Support (External) (T-0 1)

Program Exposed to Weather MYS - Concrete Air Indoor ENCLOSURE FOR Fire Protection Vll. G-29 Fire Barrier Concrete Uncontrolled Loss of Material 3.3.1-67 A CONDE NSATE STORAGE Program (A-9 1)

(External)

TANK Air Indoor Uncontrolled MYS - Concrete Air Indoor ENCLOSURE FOR Structural Fire Protection Vll.G-29 Concrete Uncontrolled Loss of Material 3.3.1-67 A CONDENSATE STORAGE Support Program (A-9 1)

(External)

TANK Air Indoor Uncontrolled MYS - Concrete Air Indoor Cracking , Loss of Bond, Structures ENCLOSURE FOR lll.A3-9 Fire Barrier Concrete Uncontrolled Loss of Material (Spalling, Monitoring 3.5. 1-23 A CONDENSATE STORAGE (T-04)

(External) Scaling) Program TANK Air Indoor Uncontrolled MYS - Concrete Air Indoor Cracking, Loss of Bond , Structures ENCLOSURE FOR Structural lll.A3-9 Concrete Uncontrolled Loss of Material (Spalling , Monitoring 3.5.1-23 A CONDENSATE STORAGE Support (T-04)

(External) Scaling) Program TANK Air Indoor Uncontrolled MYS - Concrete Air Indoor ENCLOSURE FOR Concrete Cracking and Fire Protection Vll.G-28 Fire Barrier Concrete Uncontrolled 3.3. 1-65 A CONDENSATE STORAGE Spalling Program (A-90)

(External)

TANK Air Indoor Uncontrolled

SBK-L-17155 I Enclosure 2/ Page 102 U.S . Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation

'l'I I I

FAging NU REG Table

' .

Intended Aging Effect Requiring Component Type Material . Environment Management 1801 Vol. 2 3.X.1 Note Function Management Program Item Item MYS - Concrete Air Indoor ENCLOSURE FOR Structural Concrete Cracking and Fire Protection Vll.G-28 Concrete Uncontrolled 3.3 .1-65 A CONDENSATE STORAGE Support Spalling Program (A-90)

(External)

TANK Air Indoor Uncontrolled Structures Monitoring Program, Alkali-Silica Reaction MYS - Concrete (ASR)

Air Indoor ENCLOSURE FOR Monitoring lll.A3-2 A, E, Fire Barrier Concrete Uncontrolled Expansion and Cracking 3.5.1 -27 CONDENSATE STORAGE (External)

Program & (T-03) 517, 519 TANK Air Indoor Uncontrolled Building Deformation Monitoring Program Structures Monitoring Program , Alkali-Silica Reaction MYS - Concrete (ASR)

Air Indoor ENCLOSURE FOR Structural Monitoring lll.A3-2 A, E, Concrete Uncontrolled Expansion and Cracking 3.5.1-27 CONDENSATE STORAGE Support Program & (T-03) 517, 519 (External)

TANK Air Indoor Uncontrolled Building Deformation Monitoring Program MYS - Concrete Increase in Porosity and ENCLOSURE FOR Air Indoor Permeability, Cracking, Loss Fire Protection lll.A3-10 CONDENSATE STORAGE Fire Barrier Concrete Uncontrolled 3. 5.1-24 E, 513 of Material (Spalling , Program (T-06)

TANK Air Indoor (External)

Scaling)

Uncontrolled

SBK-L-17155 I Enclosure 2/ Page 103 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation

' I' * ,,jll'. rlilt"I' NUREd1l 11 I ' 'l'!'I: I <I l:ji ,:i:'

1

I'* ,1;!111f1:':!il I ;1,l!'F A '. : 'w*I {fr1Ta~J~.li l\I Intended

Aging Effe,c;:t Requi ~!Pg ll 1 ***'I' ,Managemer:it !*I I ~1 ,ng .!!l!li!I' I '*I".

Component Type Material Environment "' ~8011Nol. 2 111. , r p.~.1 '11'1' l:1:i } '4ote

I Management

11 ', !~1 1'1 ,11'+11'1 1 ,,. 'Hill .

rl:1*1 1: ' ),.11*P~ogl-am

Function ' . "i

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1!,f,l:.:!1,

.L,.I*, t~m ', ,* ' ltem'I;;. 11fili

1* ' *:1* I

"'I I *:I*

MYS - Concrete Increase in Porosity and ENCLOSURE FOR Air Indoor Structural Permeability, Cracking, Loss Fire Protection lll.A3-10 CONDENSATE STORAGE Concrete Uncontrolled 3.5. 1-24 E, 513 Support of Material (Spalling, Program (T-06)

TANK Air Indoor (External)

Scaling)

Uncontrolled MYS - Concrete Increase in Porosity and Air Indoor Structures ENCLOSURE FOR Permeability, Cracking, Loss lll.A3-10 Fire Barrier Concrete Uncontrolled Monitoring 3.5. 1-24 A CONDENSATE STORAGE of Material (Spalling, (T-06)

(External) Program TANK Air Indoor Uncontrolled Scaling)

MYS - Concrete Increase in Porosity and Air Indoor Structures ENCLOSURE FOR Structural Permeability, Cracking, Loss lll .A3-10 Concrete Uncontrolled Monitoring 3.5. 1-24 A CONDENSATE STORAGE Support of Material (Spalling, (T-06)

(External) Program TANK Air Indoor Uncontrolled Scaling)

MYS - Concrete Cracking, Loss of Bond, Structures ENCLOSURE FOR Structural Ground Water/Soil lll.A3-4 Concrete Loss of Material (Spalling, Monitoring 3.5. 1-3 1 A CONDENSATE STORAGE Support (External) (T-05)

Scaling) Program TANK Below Grade Structures Monitoring Program, Alkali-Silica Reaction MYS - Concrete (ASR)

ENCLOSURE FOR Structural Ground Water/Soil Monitoring lll.A3-2 A, E, Concrete Expansion and Cracking 3.5. 1-27 CONDENSATE STORAGE Support (External) Program & (T-03) 517, 519 TANK Below Grade Building Deformation Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 104 U.S . Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluat ion l*I *'*' ' ,I, Aging

NUREG' Table I:

Intended Ag ing Effect Requi ring Component Type Material Environment Management 1801 Vo l. 2 3.X: 1 ' Note Funct ion Management Program Item Item MYS - Concrete Increase in Porosity and Structu res ENCLOSURE FOR Structura l Ground Water/Soil Permeability, Cracking , Loss ll l.A3-5 Concrete Monitoring 3.5.1 -31 A CONDE NSATE STORAGE Support (External) of Material (Spalling , (T-07)

Program TANK Be low Grade Scaling )

MYS - Concrete Increase in Porosity and Structures ENCLOSURE FOR Structural Ground Water/Soil lll.A3-7 Concrete Permeability, Loss of Monitorin g 3.5.1-32 A, 509 CO NDENSATE STORAGE Support (External ) (T-02)

Strength Program TANK Below Grade MYS - Concrete Structures ENCLOSURE FOR Structura l Ground Water/Soil lll.A3-6 Concrete Loss of Material , Cracking Mon itori ng 3. 5. 1-26 A CONDE NSATE STORAGE Support (External) (T-01)

Program TANK Below Grade MYS - Concrete Cracking, Loss of Bond , Structures ENCLOSURE FOR Air Outdoor 111.A3-9 Missile Barrier Concrete Loss of Material (Spalling , Monitori ng 3. 5.1-23 A CONDENSATE STORAGE (External) (T-04)

Scaling) Program TANK Exposed to Weather MYS - Concrete Cracking , Loss of Bond, Structures ENCLOSURE FOR Structura l Ai r Outdoor lll.A3-9 Concrete Loss of Material (Spalling , Monitorin g 3.5.1-23 A CONDE NSATE STORAGE Support (External) (T-04)

Scaling) Prog ram TANK Exposed to Weather Stru ct ures Mon itoring Program, Alkali-MYS - Concrete Silica Reaction ENCLOSURE FOR Air Outdoor (ASR) lll.A3-2 A, E, Missile Barrier Concrete Expan sion and Cracking 3. 5.1-27 CO NDENSATE STORAGE (External ) Monitori ng (T-03) 517, 519 TANK Exposed to Weather Program &

B uildin g Deform ation Monitorinq

SBK-L-17155 I Enclosure 2/ Page 105 U.S . Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation I 'I : :, I l*I;!

,,, :j' Aging NU REG Table 1'1'fI:'

Component Type Intended Materia1 i'I ii , Environment Aging Effect Requiring ,

Management 1801 Vol. 2 3.X.1 Note'"'Ti 1

',:: ,:

Function " Mana,g ement ,*,i:,:

' ii! ni 11:

Program Item Item Program Structures Monitoring Program, Alkali-Silica Reaction MYS - Concrete (ASR)

ENCLOSURE FOR Structural Air Outdoor Monitoring lll.A3-2 A, E, Concrete Expansion and Cracking 3.5.1-27 CONDENSATE STORAGE Support (External) Program & (T-03) 517, 519 TANK Exposed to Weather Building Deformation Monitoring Program MYS - Concrete Increase in Porosity and Structures ENCLOSURE FOR Air Outdoor Permeability, Cracking, Loss lll.A3-10 Missile Barrier Concrete Monitoring 3.5 .1-24 A CONDENSATE STORAGE (External) of Material (Spalling, (T-06)

Program TANK Exposed to Weather Scaling)

MYS - Concrete Increase in Porosity and Structures ENCLOSURE FOR Structural Air Outdoor Permeability, Cracking, Loss lll.A3-10 Concrete Monitoring 3.5.1 -24 A CONDENSATE STORAGE Support (External) of Material (Spalling , (T-06)

Program TANK Exposed to Weather Scaling)

MYS - Concrete Stru'ctu res ENCLOSURE FOR Air Outdoor lll.A3-6 Missile Barrier Concrete Loss of Material, Cracking Monitoring 3.5.1-26 A CONDENSATE STORAGE (External) (T-0 1)

Program TANK Exposed to Weather

SBK-L-17155 I Enclosure 21 Page 106 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation

'.;, l'i' ' " '"*l'J

,

,' ,: 111*.111'1.1.1.JiT ,:i:i:,:.:

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.' 1.ntended Aging Effe.ct Requiring 1 Component Typ.~11 .;.11 Material Environment Management I . 1801 Vol. 2 3.X.1 Note"'i'.

I ', Function 1 Management ';i::

. I~ i Program Item Item

'

MYS - Concrete Structures ENCLOSURE FOR Structural Air Outdoor 111.A3-6 Concrete Loss of Material, Cracking Monitoring 3.5. 1-26 A CONDENSATE STORAGE Support (External) (T-0 1)

Program TANK Exposed to Weather MYS - Concrete Masonry Unit (CMU) STATION BLACKOUT Concrete Air Outdoor Fire Protection lll.A3-11 Fire Barrier Cracking 3.5.1 -43 E, 513 STRUCTURES Exposed to Block (External) Program (T-12)

Weather MYS - Concrete Masonry Unit (CMU) STATION BLACKOUT Structural Concrete Air Outdoor Fire Protection lll.A3-11 Cracking 3.5.1-43 E,513 STRUCTURES Exposed to Support BLOCK (External) Program (T-12)

Weather MYS - Concrete Masonry Unit Structures (CMU) STATION BLACKOUT Concrete Air Outdoor lll.A3-11 Fire Barrier Cracking Monitoring 3.5.1-43 A, 511 STRUCTURES Exposed to Block (External) (T-12)

Program Weather MYS - Concrete Masonry Unit Structures (CMU) STATION BLACKOUT Structural Concrete Air Outdoor lll.A3-11 Cracking Monitoring 3.5.1-43 A, 511 STRUCTURES Exposed to Support BLOCK (External) (T-12)

Program Weather MYS - Concrete NON SAFETY RELATED Air Indoor Cracking, Loss of Bond, Structures Structural lll .A3-9 ELECTRICAL DUCT Concrete Uncontrolled Loss of Material (Spalling, Monitoring 3.5.1 -23 A Support (T-04)

BANKS/MANHOLES Air (External) Scaling) Program Indoor Uncontrolled

SBK-L-17155 I Enclosure 2/ Page 107 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Ir I IJ 1;fi

1 ;'H:l j:~:i'!ii ' 'i"111 1 ' J:ij\1111+1,,

' 1 Agirig Effect Requiring iwi,I . ,I.: ii' ' 1;j: :i 1 1r: NURE!3

II J}ging 11:1: 'l'I ','":I:

Wrable 'r 'j, :11!,

!Ii Intended Management ' r 1801Vol.2

Component Ty,pe .Material E~v,i~or:iment 3.X.1 Note Function Management ., .r

,J;I: ' I l'i Program Item Item Structures Monitoring MYS - Concrete NON Program, Alkali-SAFETY RELATED Air Indoor Structural Silica Reaction lll.A3-2 A, E, ELECTRICAL DUCT Concrete Uncontrolled Expansion and Cracking 3.5. 1-27 Support (ASR) (T-03) 517 BANKS/MANHOLES Air (External)

Monitoring Indoor Uncontrolled Program MYS - Concrete NON Increase in Porosity and SAFETY RELATED Air Indoor Structures Structural Permeability, Cracking, Loss IIl.A3-10 ELECTRICAL DUCT Concrete Uncontrolled Monitoring 3.5.1-24 A Support of Material (Spalling , (T-06)

BANKS/MANHOLES Air (External) Program Scaling)

Indoor Uncontrolled MYS - Concrete NON SAFETY RELATED Cracking, Loss of Bond, Structures Structural Ground Water/Soil lll.A3-4 ELECTRICAL DUCT Concrete Loss of Material (Spalling, Monitoring 3.5. 1-31 A Support (External) (T-05)

BANKS/MANHOLES Below Scaling) Program Grade Structures Monitoring MYS - Concrete NON Program, Alkali-SAFETY RELATED IIl.A3-2 Structural Ground Water/Soil Silica Reaction A, E, ELECTRICAL DUCT Concrete Expansion and Cracking 3.5. 1-27 Support (External) (ASR) (T-03) 517 BANKS/MANHOLES Below Monitoring Grade Program MYS - Concrete NON Increase in Porosity and SAFETY RELATED Structures Structural Ground Water/Soil Permeability, Cracking, Loss lll.A3-5 ELECTRICAL DUCT Concrete Monitoring 3.5. 1-31 A Support (External) of Material (Spalling, (T-07)

BANKS/MANHOLES Below Program Scaling)

Grade MYS - Concrete NON SAFETY RELATED Increase in Porosity and Structures Structural Ground Water/Soil lll.A3-7 ELECTRICAL DUCT Concrete Permeability, Loss of Monitoring 3.5. 1-32 A, 509 Support (External) (T-02)

BANKS/MANHOLES Below Strength Program Grade

SBK-L-17155 I Enclosure 2/ Page 108 U. S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Cpmponent Type Material Environment Management 1801 Vol. 2 3.X~ 1 Note * ..,

Function ' i'I'" 1l'l1 Management 1:1.,,, '" l:i Program .Item 1,: '

Item 1.*

MYS - Concrete NON SAFETY RELATED Structures Structural Ground Water/Soil lll.A3-6 ELECTRICAL DUCT Concrete Loss of Material , Cracking Monitoring 3.5.1-26 A Support (External) (T-01)

BANKS/MANHOLES Below Program Grade MYS - Concrete NON Cracking, Loss of Bond, Structures SAFETY RELATED Structural Air Outdoor 111.A3-9 Concrete Loss of Material (Spalling, Monitoring 3.5.1-23 A MANHOLES Exposed to Support (External) (T-04)

Scaling) Program Weather Structures Monitoring MYS - Concrete NON Program, Alkali-SAFETY RELATED Structural Air Outdoor lll.A3-2 A, E, Concrete Expansion and Cracking Silica Reaction 3.5.1 -27 MANHOLES Exposed to Support (External) (T-03) 517 (ASR)

Weather Monitoring Proqram MYS - Concrete NON Increase in Porosity and Structures SAFETY RELATED Structural Air Outdoor Permeability, Cracking, Loss lll.A3-10 Concrete Monitoring 3.5.1 -24 A MANHOLES Exposed to Support (External) of Materi al (Spalling, (T-06)

Program Weather Scaling)

MYS - Concrete NON Structures SAFETY RELATED Structural Air Outdoor lll.A3-6 Concrete Loss of Material, Cracking Monitoring 3.5.1 -26 A MANHOLES Exposed to Support (External) (T-01)

Program Weather MYS - Concrete SAFETY Air Indoor Cracking , Loss of Bond, Structures RELATED ELECTRICAL Structural lll.A3-9 Concrete Uncontrolled Loss of Material (Spalling , Monitoring 3.5.1-23 A DUCT BANKS/MANHOLES Support (T-04)

(External) Scaling) Program Air Indoor Uncontrolled

SBK-L-17155 I Enclosure 2/ Page 109 U.S. Nuclear Regulatory Commission Tabl e 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation

+Fl"" 1, Aging .. 'I NU~Ep *+ , ~able Component Type Intended Material Environment 11 1 1! A'gi'ng Effect Requiring Management 1 1

1 1801 Vol. 2

,

1 3.X.1 111 Note ,

Function Management Program *1

Item Item ,*1:11 Structures Monitoring Program , Alkali-Silica Reaction MYS - Concrete SAFETY (ASR)

Air Indoor RELATED ELECTRICAL Structural Monitoring 111.A3-2 A, E, Concrete Uncontrolled Expan sion and Cracking 3.5.1-27 DUCT BANKS/MANHOLES Support Program & (T-03) 517, 519 (External)

Air Indoor Uncontrolled Building Deformation Monitoring Program MYS - Concrete SAF ETY Increase in Porosity and Air Indoor Structures RELATED ELECTRICAL Structural Permeability, Cracking, Loss 111.A3-10 Concrete Uncontrolled Monitoring 3.5. 1-24 A DUCT BANKS/MANHOLES Support of Material (Spalling , (T-06)

(External) Program Air Indoor Uncontrolled Scaling)

MYS - Concrete SAFETY Cracking, Loss of Bond, Structures RELATED ELECTRICAL Structural Ground Water/Soil 111.A3-4 Concrete Loss of Material (Spalling, Monitoring 3.5. 1-31 A DUCT BANKS/MANHOLES Support (External) (T-05)

Scaling) Program Below Grade Structures Monitoring Program, Alkali-Silica Reaction MYS - Concrete SAFETY (ASR)

RELATED ELECTRICAL Structural Ground Water/Soil Monitoring lll.A3-2 A, E, Concrete Expansion and Cracking 3.5. 1-27 DUCT BANKS/MANHOLES Support (External) Program & (T-03) 517, 519 Below Grade Building Deformation Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 110 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation

,f Aging NU REG Table Intended Aging Effect Requiring , *N.ole 'I: I Component Type Material Environment Management ' 1801 Vol. 2 3.X.1 1ITll Function Management Program Item Item MYS - Concrete SAFETY Increase in Porosity and Structures RELATED ELECTRICAL Structural Ground Water/Soil Permeability, Cracking, Loss lll.A3-5 Concrete Monitoring 3.5.1-31 A DUCT BANKS/MANHOLES Support (External) of Material (Spalling, (T-07)

Program Below Grade Scaling)

MYS - Concrete SAFETY Increase in Porosity and Structures RELATED ELECTRICAL Structural Ground Water/Soil lll.A3-7 Concrete Permeability, Loss of Monitoring 3.5.1-32 A, 509 DUCT BANKS/MANHOLES Support (External) (T-02)

Strength Program Below Grade MYS - Concrete SAFETY Structures RELATED ELECTRICAL Structural Ground Water/Soil lll.A3-6 Concrete Loss of Material, Cracking Monitoring 3.5.1-26 A DUCT BANKS/MANHOLES Support (External) (T-01)

Program Below Grade MYS - Concrete SAFETY Cracking, Loss of Bond, Structures Air Outdoor lll.A3-9 RELATED MANHOLES Missile Barrier Concrete Loss of Material (Spalling , Monitoring 3.5.1 -23 A (External) (T-04)

Exposed to Weather Scaling) Program MYS - Concrete SAFETY Cracking, Loss of Bond, Structures Structural Air Outdoor lll.A3-9 RELATED MANHOLES Concrete Loss of Material (Spalling, Monitoring 3.5.1-23 A Support (External) (T-04)

Exposed to Weather Scaling) Program Structures Monitoring Program, Alkali-Silica Reaction MYS - Concrete SAFETY Air Outdoor (ASR) lll.A3-2 A, E, RELATED MANHOLES Missile Barrier Concrete Expansion and Cracking 3.5.1-27 (External) Monitoring (T-03) 517, 519 Exposed to Weather Program &

Building Deformation Monitoring

SBK-L-17155 I Enclosure 2/ Page 111 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Ag ing Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X. 1 Note Function Management Program Item Item Program Structures Monitoring Program , Alkali-Silica Reaction (ASR)

MYS - Concrete SAFETY Monitoring lll.A3-2 Structural Air Outdoor A, E, RELATED MANHOLES Concrete Expansion and Cracking 3.5.1-27 Support (External) Prog ram & (T-03) 517 , 519 Exposed to Weather Building Deformation Monitoring Program Increase in Porosity and MYS - Concrete SAFETY Structu res Air Outdoor Permeability, Cracking , Loss lll .A3-10 RELATED MANH OLES Missile Barrier Concrete Monitorin g 3.5.1-24 A (External) of Material (Spalling, (T-06)

Exposed to Weather Program Scaling)

Increase in Porosity and MYS - Concrete SAFETY Structures Structural Air Outdoor Permeability, Cracking , Loss lll.A3- 10 RELATED MANHOLES Concrete Mon itoring 3. 5. 1-24 A Support (External) of Material (Spalling, (T-06)

Exposed to Weather Program Scaling)

MYS - Concrete SAFETY Stru ctures Air Outdoor lll.A3-6 RELATED MANHOLES Missile Barrier Concrete Loss of Material, Cracking Monitoring 3.5.1 -26 A (External) (T-01)

Exposed to Weather Program

SBK-L-17155 I Enclosure 2/ Page 112 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Stru ctures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring II

,. Note

~omp o nent Type Material Environment Management 1801 Vol. 2 3.X.1 Function '*:1:'1!1 Management

'I* Program Item Item MYS - Concrete SAFETY Structures Structural Air Outdoor lll.A3-6 RELATED MANHOLES Concrete Loss of Material, Cracking Monitoring 3.5.1 -26 A Support (External) (T-01)

Exposed to Weather Program MYS - Concrete SERVICE Air Indoor Cracking, Loss of Bond, Structures Structural lll.A3-9 WATER ACCESS VAULT Air Concrete Uncontrolled Lo ss of Material (Spalling , Monitoring 3.5.1 -23 A Support (T-04)

Indoor Uncontrolled (External) Scaling) Program Structures Monitoring Program, Alkali-Silica Reaction (ASR)

MYS - Concrete SERVICE Air Indoor Structural Monitoring 111.A3-2 A, E, WATER ACC ESS VAULT Air Concrete Uncontrolled Expan si on and Cracking 3.5.1 -27 Support Program & (T-03) 517, 519 Indoor Uncontrolled (External)

Building Deformation Monitoring Program Increase in Porosity and MYS - Concrete SERVI CE Air Indoor Structures Structural Permeability, Cracking, Loss lll.A3-10 WATER ACCESS VAULT Air Concrete Unco ntrolled Monitoring 3.5. 1-24 A Support of Material (Spalling, (T-06)

Indoor Uncontrolled (External) Program Scaling)

MYS - Concrete SE RVI CE Cracki ng, Loss of Bond, Structures Structural Gro und W ater/Soil 111.A3-4 WATER A CCESS VAULT Concrete Loss of Mate rial (Spalling , Monitoring 3.5.1 -31 A Support (External) (T-05)

Below Grade Scaling) Program

SBK-L-17155 I Enclosure 2/ Page 113 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation

'I.

:1; :1:

, ~~ing ,,, , 'NUREG *I 1Table Intended Aging Effect Requiring Component Type Material Environment M anag~ment 1801 1 \(ol. 2 3.X.1 Note Function ' Management Program Item Item Structures Monitoring Program , Alkali-Silica Reaction MYS - Concrete SERVICE (ASR)

Structura l Ground Water/Soil lll.A3-2 A ,E517, WATER ACCESS VAULT Concrete Expansion and Cracking Mon itoring 3.5. 1-27 Support (External) (T-03) 519 Below Grade Program &

Building Deformation Monitoring Proqram Increase in Porosity and MYS - Concrete SERVICE Stru ctures Structural Ground Water/Soil Permeability, Cracking , Loss lll.A3-5 WATER ACCESS VAULT Concrete Mon itoring 3.5 .1-31 A Support (External) of Material (Spalling , (T-07)

Below Grade Program Scaling)

MYS - Concrete SERVICE Increase in Poros ity and Structures Structural Ground Water/Soil lll.A3-7 WATER ACCESS VAULT Concrete Permeability, Loss of Monitoring 3.5. 1-32 A , 509 Support (External) (T-02)

Below Grade Strength Program MYS - Concrete SERVICE Structures Structural Ground Water/Soil lll.A3-6 WATER ACCESS VAULT Concrete Loss of Material, Cracking Monitori ng 3.5.1 -26 A Support (External) (T-01)

Below Grade Program MYS - Concrete SERVICE Cracking, Loss of Bond , Structures Structural Raw Water lll.A3-4 WATER ACCESS VAULT Concrete Loss of Material (Spalling , Monitoring 3.5.1 -31 A , 509 Support (External) (T-05)

Exp osed to Raw Water Scaling) Program

SBK-L-17155 I Enclosure 2/ Page 114 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneo us Yard Structures Summ ary of Aging Management Evaluation I

II Aging NU REG Table Intended Agin g Effect Requiring Component Type Material Enviro nment Management 1801 Vol. 2 r1 3.X.1 Note Functi on Management Program Item Item Structures Monitoring Program, Alkali-Silica Reaction MYS - Concrete SERVICE (ASR)

Structural Raw Water lll.A3-2 A, E WATER ACCESS VAULT Concrete Expansion and Cracking Monitoring 3.5.1-27 Support (External) (T-03) 517, 519 Exposed to Raw Water Program &

Building Deformation Monitoring Proqram MYS - Concrete STATION Cracki ng, Loss of Bond, Structures Structural Ground Water/Soil 111.A3-4 BLACKOUT STRUCTURES Concrete Loss of Material (Spalling, Monitoring 3.5.1 -31 A Support (External) (T-05)

Below Grade Scaling) Program Structures Monitoring Program, Alkali-Silica Reaction (ASR)

MYS - Concrete STATION Structural Ground Water/So il Monitoring lll.A3-2 A, E, BLACKOUT STRUCTURES Concrete Expansion and Cracking 3.5.1 -27 Support (External) Program & (T-03) 517, 519 Below Grade Building Deformation Monitoring Program Increase in Porosity and MYS - Concrete STATION Structures Structural Ground Water/Soil Permeability, Cracking , Loss lll.A3-5 BLACKOUT STRUCTURES Concrete Monitoring 3.5.1-31 A Support (External) of Materia l (Spalling, (T-07)

Below Grade Program Sca ling)

- - -

SBK-L-17155 I Enclosure 2/ Page 11 5 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Stru ctures Summary of Aging Management Evaluation Component Type Intended M aterial Environment

':l"!i' I

I r I Aging Effect Requiring 1

h1.';i:I:!, 1 I'. 1<'lill' ill1 1,n'jil 111 Aging {*' i .11 M anage' me~t '

1 1!'i1*11 INtJREGl' I 1111:* Table .

.. ,, . ' *, 11'*1

t

' I: ~ I.I:

I 3.~~ -1 '* 1 *" Note .

' I, *

, *

.I. Managemeht1 : 'i'l'I <:i r, I' 1181011i110L 2 .

Function 1*

.)

t l'j T I ; , 1 . ,f, .' ,,i 'TI i" I :

11 ' ' "'" 11 i ili ifl',

111 Program *.iii! Item ' Item .,. I ,.

'!',: I ,j.

MYS - Concrete STATION Increase in Porosity and Structures Structural Ground Water/Soil lll.A3-7 BLACKOUT STRUCTURES Concrete Permeability, Loss of Monito ring 3.5.1 -32 A, 509 Support (External) (T-02)

Below Grade Strength Program MYS - Concrete STATION Structu res Structu ral Ground Water/Soil lll.A3-6 BLACKOUT STRUCTURES Concrete Loss of Material, Cracking Monitoring 3.5.1-26 A Support (External) (T-01)

Below Grade Program MYS - Concrete STATION Cracking, Loss of Bond, Structu res Structural Air Outdoor lll.A3-9 BLACKOUT STRUCTURES Concrete Loss of Material (Spalling, Mon itoring 3.5.1 -23 A Support (External) (T-04)

Exposed to We ather Scaling) Program Structures Monitoring Program, MYS - Concrete STATION Structural Air Outdoor Alkali-Silica lll.A3-2 A, E, BLACKOUT STRUCTURES Concrete Expansion and Cracking 3.5.1-27 Support (External) Reaction (ASR) (T-03) 517 Exposed to W eather Monitoring Program Increase in Porosity and MYS - Concrete STATION Structures Structura l Air Outdoor Permeability, Cracking, Loss lll.A3-10 BLACKOUT STRUCTURES Concrete Monitoring 3.5. 1-24 A Support (External) of Material (Spalling, (T-06)

Exposed to Weather Program Scaling)

MYS - Concrete STATION Structures Structural Air Outdoor lll.A3-6 BLACKOUT STRUCTURES Concrete Loss of Material, Cracking Monitoring 3.5.1 -26 A Support (External) (T-01)

Exposed to Weather Program

SBK-L-17155 / Enclosure2/ Page 116 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation

' . Aging * *:; NUREG ' Table T Intended Aging Effect Requiring ,1 Component Type Material Environment ' Management ,, 1801 Vol. 2 3.X.1 Note .,

Function Management Program Item Item MYS - Concrete Sump Cracking, Loss of Bond, Structures CONTROL ROOM MAKEUP Structural Raw Water lll.A3-4 Concrete Loss of Material (Spal ling , Monitoring 3.5.1-31 A, 509 AIR INTAKE STRUCTURE Support (External) (T-05)

Scaling) Program Exposed to Raw Water Structures Monitoring Program, Alkali-Silica Reaction MYS - Concrete Sump (ASR)

CONTROL ROOM MAKEUP Structural Raw Water Monitoring lll.A3-2 A , E, Concrete Expansion and Cracking 3.5.1-27 AIR INTAKE STRUCTURE Support (External) Program & (T-03) 517, 519 Exposed to Raw Water Building Deformation Monitoring Program MYS - Concrete Sump NON SAFETY RELATED Cracking , Loss of Bond, Structures Structural Raw Water lll.A3-4 ELECTRICAL DUCT Concrete Loss of Material (Spalling, Monitoring 3.5.1 -31 A, 509 Support (External) (T-05)

BANKS/MANHOLES Scaling) Program Exposed to Raw Water Structures Monitoring MYS - Concrete Sump NON Program , Alkali-SAFETY RELATED Structural Raw Water Silica Reaction lll.A3-2 A , E, ELECTRICAL DUCT Concrete Expansion and Cracking 3.5.1-27 Support (External) (ASR) (T-03) 517 BANKS/MANHOLES Monitoring Exposed to Raw Water Program MYS - Concrete Sump SAFETY RELATED Cracking, Loss of Bond , Structures Structural Raw Water lll.A3-4 ELECTRICAL DUCT Concrete Loss of Material (Spalling, Monitoring 3.5.1-31 A, 509 Support (External) (T-05)

BANKS/MANHOLES Scaling) Program Exposed to Raw Water

SBK-L-17155 I Enclosure 2/ Page 117 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function Management Program It.em Item

I' Structures Monitoring Program, Alkali-MYS - Concrete Sump Silica Reaction SAFETY RELATED (ASR)

Structural Raw Water lll.A3-2 A, E, ELECTRICAL DUCT Concrete Expansion and Cracking Monitoring 3.5.1 -27 Support (External) (T-03) 517, 519 BANKS/MANHOLES Program &

Exposed to Raw Water Building Deformation Monitoring Proqram Structures Monitoring MYS - EPDM Roof Program, Separation , Environmental ENCLOSURE FOR Shelter, Air Outdoor Building lll.A6-12 A, 505, Roofing Degradation , Water In- 3.5.1 -44 CONDENSATE STORAGE Protection (External) Deformation (TP-7) 520 Leakage TANK Exposed to Weather Monitoring Program MYS - EPDM Roof STATION Separation , Environmenta l Structures Shelter, Air Outdoor lll.A6-12 BLACKOUT STRUCTURES Roofing Degradation, Water In- Monitoring 3.5.1 -44 A, 505, Protection (External) (TP-7)

Exposed to Weather Leakage Program MYS - Penetration Seal Increased Hardness and Structures ENCLOSURE FOR Shelter, Air Outdoor Vll.G-2 Elastomer Shrinkage and Loss of Monitoring 3.3.1-61 E, 515 CONDENSATE STORAGE Protection (External) (A-20)

Strength Program TANK Exposed to Weather MYS - Seismic Isolation Joint SAFETY RELATED Air Indoor Increased Hardness and Structures Expansion/ Vll.G-1 ELECTRICAL DUCT Elastomer Uncontrolled Shrinkage and Loss of Monitoring 3.3.1-61 E, 515 Separation (A-19)

BANKS/MANHOLES Air (Exte rna l) Strength Program Indoor Uncontrolled

SBK-L-17155 I Enclosure 2/ Page 118 U.S. Nuclear Regulatory Commission Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation

" ri'.',

1 11 1 : i:1' *11 1*, \I:!** , 1, , *.* A~'fr19 111r1: 11 illil 1t.JuFi.EG Table 1,.: .i, 1

11111::J 111

,Intended Agihg Effect Requiring 1:1 r Component Type ,. I*: .. ,

11 Material Environment I Management 1801 Vol. 2 3.X.1 Note ' :.,.i 11 Function Management

:1' 1*1 " 1: Program Item Item MYS - Stainless Steel Structures ENCLOSURE FOR Structural Stainless Air Outdoor 111.82-7 Loss of Material Monitoring 3.5.1-50 A CONDENSATE STORAGE Support Steel (External) (TP-6)

Program TANK Exposed to Weather Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Standard Notes Note Description A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP.

B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.

C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP .

D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.

E Consistent with NUREG-1801 for material , environment and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program .

F Material not in NUREG-1801 for this component.

G Environment not in NUREG-1801 for this component and material.

H Aging effect not in NUREG-1801 for this component, material and environment combination.

1 Aging effect in NUREG-1801 for this component, material and environment combination is not applicable.

J Neither the component nor the material and environment combination is evaluated in NUREG-1801 .

501 Not used.

502 Aging effect includes "Fretting or Lockup" due to wear.

503 Crevice and pitting will be included along with loss of material-corrosion due to a saltwater atmosphere environment.

504 Fatigue analysis exists and TLAA applies.

505 Built-up roofing is not in GALL; lll.A6-12 is for elastomer-material is similar, aging effect is similar, environment is same , and AMP is Structures Monitoring.

506 Component is cementitious fire proofing/insulating material and will exhibit similar aging effects as concrete.

507 Spent Fuel Pool temperature< 60°C (<140° F); water chemistry and temperature will be maintained by the Water Chemistry Program .

SBK-L-171 55 /Enclosure 2/ Page 119 U.S. Nuclear Regulatory Commission 508 Cracking, loss of bond, and loss of material (spalling, scaling)/corrosion of embedded steel-is not listed in GALL 111 .A.6 as an aging effect for concrete in raw water.

Seabrook manages this effect with Structures Monitoring Program.

509 For aging management purposes, buried, below grade, soil, and ground water/ raw & treated water environments are treated the same.

51 O Reduction in concrete anchor capacity is an aging effect that is addressed in LRAM-SUPT.

511 At Seabrook Station, Xl.S7 "RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" and XI.SS "Masonry Wall Program" are combined under Xl.S6 "Structures Monitoring Program".

512 Raw water in lined & unlined concrete sumps.

513 Seabrook Station will age manage this condition through the Fire Protection Program.

514 Seabrook Station will age manage this condition through the Structures Monitoring Program.

515 Increased hardness, shrinkage, or loss of strength of elastomer seals due to weathering is addressed by GALL only for Fire Barrier seals. Seabrook Station wi ll manage such aging effects for non-Fire Barrier elastomer seals with the Structures Monitoring Program.

516 Seabrook Station Structures Monitoring Program will perform concrete testing and rebar inspection to determine the effects of the aggressive groundwater on the concrete. The concrete testing and the rebar inspection will represent all concrete below grade.

517 After initial identification and determination of the presence of alkali-silica reactivity by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Alkali-Silica Reaction (ASR) Monitoring Program.

519 After initial identification of alkali-silica reaction (ASR) induced building deformation by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Alkali-Silica Reaction (ASR) Monitoring Program and the Building Deformation Monitoring Program.

520 After initial identification of alkali-silica reaction (ASR) induced building deformation affecting plant equipment and componen ts by th e Structures Monitoring Program, Seabrook Station will age manage this condition through th e Building Deformation Monitoring Program .

SBK-L-17 155 I Enclosure 2/ Page 120 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

, Ii' 11: ifr'*'* i i ' ., , , '. .

I*;

, Aging 1

I' ,*I Intended :, l1iil'Agj ng ~ff~ct '. ~ef;! U i[i ng NU REG 1801 . ,. . *.Table '

Component Type Material . Management .. , Note

,1.I' Function Environme rit ,,.i:J, ,11'l'ill'1'i:Jlil1 Management I'**** *flI'll' *"1111 I'

0* T*Ir w v11 o1n:ltem ji'.': !;:*:111*1 3.x;1 n

l:':'I .1: 1111 P ~ 9 ['fl!11 i;;1:111: l!I ,* 1:11.* 11:: 1 11fr1:1ii:;i: 1.th1I I:*: ;:t 1:**

t*:1:*]!!1'j:!1!"

1 l'l'l'I' ,, .. ij* '.i:l*.111:1 :':1:1:'.IJ;l,H!,:ii*1ll 1*l* u*.: :* *i:i *;'::1:1:. ,!:1 1 *'.

Item 1;<i :';T

" I Non-PST - (Structural) Fire Proofing - Air Indoor Metallic Fire Protection Vl l. G-29 COG- Exposed to Air Indoor Fire Barrier Uncontrolled Loss of Material 3.3. 1-67 C, 506 Fire- Program (A-9 1)

Uncontrolled (External)

Proofing Non-PST - (Structural) Fire Proofing - Air Indoor Structures Metallic V ll. G-29 COG- Exposed to Air Indoor Fire Barrier Uncontrolled Loss of Material Monitoring 3.3. 1-67 C, 506 Fire- (A-9 1)

Uncontrolled (External) Program Proofing Non-PST - (Structural) Fire Proofing - Air Indoor Metallic Fire Protection Vll. G-29 COG- Exposed to Air Indoor Fire Barrier Uncontrolled Loss of Material 3.3.1-67 C, 506 Fire- Prog ram (A-9 1)

Uncontrolled (External)

Proofing Non-PST - (Structural) Fire Proofing - Air Indoor Structures Metallic Vll. G-29 COG- Exposed to Air Indoor Fire Barrier Uncontrolled Loss of Material Monito ri ng 3.3.1-67 C, 506 Fire- (A-9 1)

Uncontrolled (External) Program Proofing Structures Monitoring Prog ram Separation , Environmental PST - Built-Up Roofing -COG- Shelter, Air Outdoor lll.A6- 12 H, 505, Roofing Degradation, Water In- 3.5. 1-44 Exposed to Air Outdoor Protection (External) Building (TP-7) E, 520 Leakage Deformation Monitoring Program Structures Monitoring Program Separation, Environmental PST - Built-Up Roofing -EFP- Shelter, Air Outdoor lll.A6-12 H, 505 ,E, Roofing Degradation , Water In- 3 .5. 1-44 Exposed to Air Outdoor Protection (External) (TP-7) 520 Leakage Building Deformation Monitoring

SBK-L-17155 I Enclosure 2/ Page 121 U. S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

" Aging Table Intended Aging Effect Requiring NU REG 1801 Component Type Material Environment Management 3.X. 1 Note Function Management Vol. 2 Item Program Item Program Structures Mo nitoring Pro gram Separation , Environmental PST - Built-Up Roofing -FSB- Shelter, Air Outdoor lll.A6-12 H, 505 ,

Roofing Degradation , Water In- 3.5.1-44 Exposed to Air Outdoor Protectio n (External)

Leakage Building (TP-7) E, 520 Deformation Monitoring Program Structures Monitoring Program Separation , Environmental PST - Bui lt-Up Roofing -PAB- Shelter, Air Outdoor lll.A6-12 H, 505 ,

Roofing Degradation , Water In- 3.5.1 -44 Exposed to Air Outdoor Protection (External)

Leakage Building (TP-7) E, 520 Deformation Monitoring Proaram Structures Monitoring Program Separation , Environmental PST - Built-Up Roofing -PCEW- Shelter, Air Outdoor lll.A6-12 H, 505, Roofing Degradation , Water In- 3.5.1-44 Exposed to Air Outdoor Protection (External)

Leakage Building (TP-7) E,520 Deformation Monitoring Program Structures Monitoring Program Separation , Environmental PST - Built-Up Roofing -PHA- Shelter, Air Outdoor lll.A6-12 H, 505 ,

Roofing Degradation , Water In- 3.5.1 -44 Exp osed to Air Outdoor Protection (External)

Leakage Building (TP-7) E, 520 Deformation Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 122 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Table Intended Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X.1 Note 1 .'

Function Management Vol. 2 Item Program Item Structures Monitoring Program Separation , Environmental PST - Bui lt-Up Roofing -TFA- Shelter, Air Outdoor lll.A6-12 H, 505, Roofing Degradation , Water In- 3.5.1-44 Exposed to Air Outdoor Protection (External) Building (TP-7) E, 520 Leakage Deformation Monitoring Proqram Structures Monitoring Program Separation , Environmental PST - Built-Up Roofi ng -WPS- Shelter, Air Outdoor 111.A6-12 H, 505, Roofing Degradation , Water In- 3.5.1-44 Exposed to Air Outdoor Protection (External)

Leakage Building (TP-7) E, 520 Deformation Monitoring Proqram PST - Carbon Steel -COG- Air Indoor Structures Structural lll.A1 -12 Exposed to Air Ind oor Steel Uncontrolled Loss of Material Monitoring 3.5. 1-25 A Support (T-11)

Uncontrolled (Extern al) Program Structures PST - Carbon Steel -COG- Structural Air Outdoor lll.A1 -12 Steel Loss of Material Monitoring 3.5.1-25 A, 503 Exposed to Air Outdoor Support (External) (T-11)

Program Structu res PST - Carbon Steel -CEHMS- Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5 .1 -25 A, 503 Exposed to Air Outdoor Support (External) (T-1 1)

Program PST - Carbon Steel Door -COG- Air Indoor Structures Structura l lll.A1 -12 Expo sed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3. 5.1 -25 A Support (T-11)

Uncontrolled (External) Program

SBK-L-171 55 I Enclosure 2/ Page 123 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Ag ing Management Evaluation Aging Table ':1: t1:

Intended Aging Effect Requi ring NUREG 1801 Component Type Material* Environment Management 3.X.1 Note Function Management Vol. 2 Item Program Item Structures PST - Carbon Steel Door -COG- Structural Air Outdoor ll l.A1 -12 Steel Loss of Material Monitori ng 3.5. 1-25 A, 503 Exposed to Ai r Outdoor Support (External) (T-11)

Prog ram PST - Carbon Steel Door -EFP- Air Indoor Structures Structural lll. A3-12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A Support (T-11)

Uncontrolled (External) Program Structures PST - Carbon Steel Door -EFP- Structura l Air Outdoor ll l.A3-12 Steel Loss of Material Monitori ng 3. 5. 1-25 A, 503 Exposed to Ai r Outdoor Support (External) (T-11)

Program PST - Carbon Steel Door -FSB- Air Indoor Structures HELB lll.A5-12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5 .1 -25 A Shielding (T-11)

Uncontrolled (External) Program PST - Carbon Steel Door -FSB- Air Indoor Structures Structura l lll.A5- 12 Exposed to Ai r Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A Support (T-11 )

Uncontrolled (External) Program Structures PST - Carbon Steel Door -FSB- Structural Air Outdoor lll.A5- 12 Steel Loss of Material Monitoring 3.5.1 -25 A , 50 3 Exposed to Air Outdoor Support (External) (T- 11)

Prog ram

SBK-L-17155 I Enclosure 21 Page 124 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

' 1] 1,1 I' , ,,1, , ,1:rl l.j Aging Table I Intended , Aging Effect Requiring NU REG 1801 1, I Component Type Material Envi~onment 1 ' Management 3.X. 1 Note

,,

Function " ':' ",:, I'll1

Jiii, 1y1 i*ll ,11'1 'Iii' Management1 Program Vol. 2 Item:,

Jtem

'1 *T I !*Ill I 1111111'1"11 I, li1'1 11 ,,,, " '"r:!*

PST - Carbon Steel Door -FSB- Air w/Borated HELB Boric Acid lll. B2-11 in Air with Borated Water Steel Water Leakage Loss of Material 3.5.1-55 A Shielding Program (T-25)

Leakage (External)

PST - Carbon Steel Door -FSB- Air w/Borated Structural Boric Acid lll .B2-11 in Air with Borated Water Steel Water Leakage Loss of Material 3.5.1-55 A Support Program (T-25)

Leakage (External)

PST - Carbon Steel Door -PAB- Air Indoor Structures HELB lll.A3-12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5. 1-25 A Shielding (T-11)

Uncontrolled (External) Program PST - Carbon Steel Door -PAB- Air Indoor Structures Structural lll.A3-12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A Support (T-11)

Uncontrolled (External) Program Structures PST - Carbon Steel Door -PAB- Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A, 503 Exposed to Air Outdoor Support (External) (T-11 )

Program PST - Carbon Steel Door -PAB- Air w/Borated HELB Boric Acid 111. 82-11 in Air with Borated Water Steel Water Leakage Loss of Material 3.5.1-55 A Shielding Program (T-25)

Leakage (External)

SBK-L- 171 55 I Enclosure 2/ Page 125 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation i'I Aging " Table Intended Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X. 1 Note Function Management Vol. 2 Item Program Item PST - Carbon Steel Door -PAB- Air w/Borated Structu ral Boric Acid 111. 82-11 in Air with Borated Water Steel Water Leakage Loss of Material 3.5.1 -55 A Support Program (T-25)

Leakage (External)

PST - Carbon Steel Door - Air Indoor Structures HELB lll.A3- 12 PCEW- Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5. 1-25 A Shielding (T-11)

Uncontro lled (External) Prog ram PST - Carbon Steel Door - Air Indoor Structures Structural lll.A3-12 PCEW- Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A Support (T-11)

Uncontrol led (External) Program Structures PST - Carbon Steel Door - Structural Air Outdoor 11 1.A3-12 Steel Loss of Material Monitoring 3.5.1 -25 A, 503 PCEW- Exposed to Air Outdoor Support (External) (T-11)

Prog ram PST - Carbon Steel Door -WPB- Air Indoor Structures Structura l lll .A3-1 2 Exposed to Air Indoor Steel Uncontrolled Loss of Materi al Monitoring 3.5.1 -25 A Suppo rt (T-11)

Uncontrolled (External) Program Structures PST - Carbon Steel Door -WPB- Structural Air Outdoor lll.A3-12

Steel Loss of Material Monitoring 3.5.1 -25 A, 503 Exposed to Air Outdoor Support (External) (T- 11)

Program

SBK-L-17155 I Enclosure 2/ Page 126 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

,:1* I*

Aging Table Intended Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X.1 Note Function Management Vol. 2 Item Program Item PST - Carbon Steel Door -WPB- Air w/Borated Structural Boric Acid lll.B2-11 in Air with Borated Water Steel Water Leakage Loss of Material 3.5.1-55 A Support Program (T-25)

Leakage (External)

PST - Carbon Steel -EFP- Air Indoor Structures Structural lll.A3-12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A Support (T-11)

Uncontrolled (External) Program Structures PST - Carbon Steel -EFP- Shelter, Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A , 503 Exposed to Air Outdoor Protection (External) (T-11 )

Program Structures PST - Carbon Steel -EFP- Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5. 1-25 A, 503 Exposed to Air Outdoor Support (External) (T-11)

Program PST - Carbon Steel Fire Door - Air Indoor Fire Protection Vll.G-3 CDG- Exposed to Air Indoor Fire Barrier Steel Uncontrolled Loss of Material 3.3.1-63 A Program (A-21 )

Uncontrolled (External)

PST - Carbon Steel Fire Door - Air Indoor Fire Protection Vll.G-3 EFP- Exposed to Air Indoor Fire Barrier Steel Uncontrolled Loss of Material 3.3.1-63 A Program (A-21)

Uncontrolled (External)

SBK-L-17155 I Enclosure 2/ Page 127 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1

'II Agin~ li NURE~, 180~,l'l'I 'I ~ote 1

, '

11 1"111 ' * *1 1: , ' ' Table 111

,,, '. Jl*li: : ',, 1' l'I Component Type Intended Function Material Environment ' 11 l'I 1

,,

1 11n11 Ir j;i

,,li;girig pffect fl.equ,1.rin.g '1,1,,1 1 r.'i*i' , Managementill'

{]

1 i; M.' '!nag~men~,l: j:j'. *Iii*, *ti1v ol'Y2]*1l*tem 111 1 l!I::1 ! , ' " 1111 IProgram 1:

1

,

1*i:l.1*1*'1*1 1 1111 l:!,11

, ,

!i b .x.1 1:111 Ii lil!1 1tem'1 1 11 ,

*

'1,;

',,

,, , i;1 11 PST - Carbon Steel Fire Door - Air Indoor Fire Protection Vll.G-3 FSB- Exposed to Air Indoor Fire Barrier Steel Uncontrolled Loss of Material 3.3.1-63 A Program (A-21)

Uncontrolled (External)

PST - Carbon Steel Fire Door - Air w/Borated Boric Acid lll.B2-11 FSB- in Air with Borated Water Fire Barrier Steel Water Leakage Loss of Material Program (T-25) 3.5.1-55 A Leakage (External)

PST - Carbon Steel Fire Door - Air Indoor Fire Protection Vll .G-3 PAB- Exposed to Air Indoor Fire Barrier Steel Uncontrolled Loss of Material 3.3.1-63 A Program (A-21)

Uncontrolled (External)

PST - Carbon Steel Fire Door - Air w/Borated Boric Acid lll.B2-11 PAB- in Air with Borated Water Fire Barrier Steel Water Leakage Loss of Material 3.5.1-55 A Program (T-25)

Leakage (External)

PST - Carbon Steel Fire Door - Air Indoor Fire Protection Vll.G-3 PCEW- Exposed to Air Indoor Fire Barrier Steel Uncontrolled Loss of Material 3.3.1-63 A Program (A-21)

Uncontrolled (External)

PST - Carbon Steel Fire Door - Air Indoor Fire Protection Vll .G-3 WPB- Exposed to Air Indoor Fire Barrier Steel Uncontrolled Loss of Material 3.3.1-63 A Program (A-21)

Uncontrolled (External)

SBK-L- 17 155 I Enclosure 2/ Page 128 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1

I Intended r . . *:r!!ll "'.ill ~gin~11 : Eff~~t,~;quiring Ag ing ,

NUREG 1801

1:

Table 11 Component Type Function Material Environment'! : I 'I' '

' Management. "

' ' 111 Management v oi. 2 1tem : :1 1

3:X.1 ' Note I

I* .° 1!11 "111:

11: /11'1 'I* *1il!l*lll: ' 11 i::l'1!1ili1 1 * *:1:1' I

'*' ~ rogran:i I iii! ' ::i1:' \1: ,': ; j 1tehi , '!

PST - Carbon Steel Fire Door - Air w/Borated Boric Acid lll. B2-11 WPB- in Air with Borated Water Fire Barrier Steel Water Leakage Loss of Materfal 3.5.1-55 A Program (T-25)

Leakage (External)

PST - Carbon Steel -FSB- Air Indoor Structures Structural ll l.A5-12 Exposed to Air Indoor Steel Uncontrol led Loss of Material Monitoring 3.5.1 -25 A Support (T-11 )

Uncontrolled (External) Program Air w/Borated PST - Carbon Steel -FSB- in Air Structural Boric Acid ll l.B2-11 Steel Water Leakage Loss of Material 3.5.1-55 A with Borated Water Leakage Support Program (T-25)

(External)

PST - Carbon Steel -PAB- Air Indoor Structures Structura l lll.A3-12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5. 1-25 A Support (T-11)

Uncontrolled (External) Program Structures PST - Carbon Steel -PAB- Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5. 1-25 A, 503 Exposed to Air Outdo or Support (External) (T-11)

Program Air w/Borated PST - Carbon Steel -PAB- in Air Structural Boric Acid lll. B2-11 Steel Water Leakage Loss of Material 3.5. 1-55 A with Bo rated Water Leakage Support Program (T-25)

(External)

SBK-L- 17155 I Enclosure 2/ Page 129 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging , ' Table 1 '1! 1 ~

11 Intended Aging Effect Requiring NU REG 1801 *' I'. I:

. .'I{'I Component Type 'l r 1 Material Environment Management 3.X.1 Note ,

1

I* I ' Function .*1, Management Vol. 2 Item I '*. '

Program Item ' l 1 ' :l:

1 PST - Carbon Steel -PCEW- Air Indoor Structures lll.A3-12 Exposed to Air Indoor Flood Barrier Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A (T-1 1)

Uncontrolled (External) Program PST - Carbon Steel -PCEW- Air Indoor Structures Structural lll.A3-12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5. 1-25 A Support (T-11)

Uncontrolled (External) Program Structures PST - Carbon Steel -PCEW- Structural Air Outdoor 111.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A, 503 Exposed to Air Outdoor Support (External) (T-11)

Program PST - Ca rb on Steel -PHA- Air Indoor Structures Structural lll.A3-12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1 -25 A Support (T-11)

Uncontrolled (External) Program Structures PST - Carbon Steel -PHA- Shelter, Air Outdoor ll l.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A, 503 Exposed to Air Outdoor Protection (External) (T-11 )

Program Structures PST - Carbon Steel -PHA- Structural Air Outdoor lll. A3-12 Steel Loss of Material Monitoring 3.5 .1-25 A, 503 Exposed to Air Outdoor Support (External) (T-11 )

Program

SBK-L-17155 I Enclosure 2/ Page 130 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

11

'

Aging Table

" ' Intended Aging Effect Requiring NUREG 1801 .,.

Component Type Material Environment Management 3.X.1 Note Function ' Management Vol. 2 Item Program Item PST - Carbon Steel -TFA- Air Indoor Structures Structural lll.A3-12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5 .1-25 A Support (T-11)

Uncontrolled (External) Program Structures PST - Carbon Steel -TFA- Shelter, Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A , 503 Exposed to Air Outdoor Protection (External) (T-11)

Program Structures PST - Carbon Steel -TFA- Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A , 503 Exposed to Air Outdoor Suppo rt (External) (T-11)

Program Air w/Borated PST - Carbon Steel -TFA- in Air Structural Boric Acid 111.82-11 Steel Water Leakage Loss of Material 3.5.1-55 A with Borated Water Leakage Support Program (T-25)

(External)

PST - Carbon Steel -WPB- Air Indoor Structures Structural 111.A3-12 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5 .1-25 A Support (T-11 )

Uncontrolled (External) Program Structures PST - Carbon Steel -WPB- Shelter, Air Outdoor lll. A3-12 Steel Loss of Material Monitoring 3.5.1-25 A, 503 Exposed to Air Outdoor Protection (External) (T-11)

Program

SBK-L-17 155 I Enclosure 2/ Page 131 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1:1 Aging Table Intended Aging Effect Requiring NUREG 1801 Component Type Material 1 Environment Management I* 3.X.1 Note Function Management Vol. 2 Item :*j*I Program Item Structures PST - Carbon Steel -WPB- Structura l Air Outdoor ll l.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A, 503 Exposed to Air Outdoor Support (External) (T-11 )

Program Air w/Borated PST - Carbon Steel -WPB- in Structural Boric Acid ll l.B2-11 Steel Water Leakage Loss of Material 3.5.1-55 A Air with Borated Water Leakage Support Program (T-25)

(External)

Nef\e PST - Conduit Fire Wrap -COG- Air Indoor Nef\e Building lll.B2-4 Exposed to Air Indoor Fire Barrier Aluminum Uncontrolled Deformation/reduction in Deformation 3.5 .1-58 A, E, 520 (TP-8)

Uncontrolled (External) structural capacity Monitoring Program Nef\e PST - Conduit Fire Wrap -PAB- Air Indoor Nef\e Building lll.B2-4 Exposed to Air Indoor Fire Barrier Aluminum Uncontrolled Deformation/reduction in Deformation (TP-8) 3.5 .1-58 A, E, 520 Uncontrolled (External) structural capacity Monitoring Program PST - Conduit Fire Wrap -PAB- Air w/Borated lll.B2-6 Boric Acid in Air with Borated Water Fire Barrier Aluminum Water Leakage Loss of Material (TP-3) 3.5.1-55 A Program Leakage (External))

Nef\e Nef\e PST - Conduit Fire Wrap -WPB- Air Indoor Building Deformation/reduction in lll. B2-4 Exposed to Air Indoor Fire Barrier Aluminum Uncontrolled Deformation 3.5. 1-58 A, E, 520 structural capacity (TP-8)

Uncontrolled (External) Monitoring Program

SBK-L-17 155 I Enclosure 2/ Page 132 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1:1+ ' *l'l'i'I . *I: .,, :I 111 Aging I Table Intended il Aging Effect 'Requiring NU REG 1801 Component Type Material Environment 1 Management 3.X.1 Note Function '*

1

Management Vol. 2 Item 1:'; Program Item PST - Condu it Fire Wrap - WPB- Air w/Borated lll. B2-6 Boric Acid in A ir with Borated Water Fire Barrier Aluminum Water Leakage Loss of Material (TP-3) 3. 5.1 -55 A Program Leakage (External))

PST - Elastomers -CDG- Air Indoor Increased Hardness, Structures Control Bldg Vll. G- 1 Exposed to Air Indoor Elastomer Uncontrolled Shrinkage and Loss of Mon itoring 3.3. 1-6 1 E, 515 Habitability (A- 19)

Uncontroll ed (External) Strength Program PST - Elastomers -CDG- Air Indoor Increased Hardness, Structures Vll. G-1 Exp osed to Air Indoor Flood Barrier Elastomer Uncontrolled Shrinkage and Loss of Mon itoring 3.3. 1-61 E, 515 (A-19)

Uncontrolled (External) Strength Program Increased Hardness, Structures PST - Elastomers -CDG- Expansion/ Air Outdoor Vll.G-2 Elastomer Shrinkage and Loss of Mon itoring 3.3.1-61 E, 515 Exposed to Air Outdoor Separation (External) (A-20)

Strength Program Increased Hardness, Stru ctures PST - Elastomers -CDG- She lter, Air Outdoor Vll.G-2 Elastomer Shrinkage and Loss of Monitoring 3.3. 1-6 1 E, 515 Exposed to Air Outdoor Protection (External) (A-20)

Strength Program Increased Hardness, Structures PST - Elastom ers -EFP- Expansion/ Air Outdoor Vll.G-2 Elastomer Shrinkage and Loss of Monitoring 3.3.1 -6 1 E, 515 Exposed to Air Outdoor Separation (External) (A-20)

Strength Program

SBK-L-17155 I Enclosure 2/ Page 133 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1 1 1 1 Ma:a~~~~nt ""'1* 1*1* ~G ," .

~Eci '.~ ~~1 ' I'

Table "

I " ':l:1:1'.""*l' .. '*h1 *1:1' 11 :11*1 Intended

, fl . 'i' I Aging Effect Requiring :*

I j!'

1

1' 1

Component Type Material ,Environment 1 1Note.1 *,

Function 1 jl:, :111:1 Management Program Vol. 2* 1tem 3.X. 1 'I . ,

" *I*

Item Increased Hardness, Structures PST - Elastomers -EFP- Shelter, Air Outdoor Vll.G-2 Elastomer Shrinkage and Loss of Mon itoring 3.3.1 -6 1 E, 515 Exposed to Air Outdoor Protection (External) (A-20)

Strength Program Increased Hardness, Structures PST - Elastomers -FSB- Expansion/ Air Outdoor Vll. G-2 Elastomer Shrinkage and Loss of Monitoring 3.3.1 -6 1 E, 515 Exposed to Air Outdoor Separation (External) (A-20)

Strength Program Increased Hardness, Structures PST - Elastomers -FSB- Shelter, Air Outdoor Vll.G-2 Elastomer Shrinkage and Loss of Mo nitoring 3.3 .1-6 1 E, 515 Exposed to Air Outdoor Protection (External) (A-20)

Strength Program Increased Hardness, Structures PST - Elastomers -PAB- Expansion/ Air Outdoor Vll.G-2 Elastomer Shrinkage and Loss of Monitoring 3.3.1-61 E, 515 Expo sed to Air Outdoor Separation (External) (A-20)

Strength Program Increased Hardness, Structures PST

Elastomers -PAB- Shelter, Air Outdoor Vll.G-2 Elastomer Shrinkage and Loss of Mo nitoring 3.3.1-61 E, 515 Exposed to Air Outdoor Protection (External) (A-20)

Strength Program Increased Hardness, Structu res PST* Elastomers -PCEW- Expansion/ Air Outdoor Vll.G-2 Elastomer Shrinkage and Loss of Mon itoring 3.3.1-61 E, 515 Exp osed to Air Outdoor Separation (External) (A-20)

Strength Program

SBK-L- 171 55 I Enclosure 2/ Page 134 U. S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Ag ing Management Evaluation I; I~ ;

I ' I 'I : I : '

Intended

,1'1'1'

. Aging Effect Requiring Aging NUREG 1801 I

Table II ,ff .

Com'p onent Type Material Environment Management 3.X. 1 Note. .r' Function I, M~nagement Vol. 2 Item Prog ram Item Increased Hardness, Structures PST - Elastomers -PCEW- Shelter, Air Outdoor V ll. G-2 Elastomer Shrinkage and Loss of Monitoring 3.3.1-6 1 E, 515 Exposed to Air Outdoor Protection (External) (A-20)

Strength Program Increased Hardness, Structures PST - Elastomers -PHA- Expansion/ Ai r Outdoor Vll. G-2 Elastomer Shrinkage and Loss of Monitoring 3.3. 1-6 1 E, 515 Exposed to Ai r Outdoor Separation (External) (A-20)

Strength Program Increased Hardness, Structures PST - Elastomers -PHA- Shelte r, Air Outdoor Vll. G-2 Elastomer Shrinkage and Loss of Mon itori ng 3.3.1 -6 1 E, 515 Exposed to Air Outdoor Protection (External) (A-20)

Strength Program Increased Hardness, Stru ctures PST - Elastomers -TFA- Expansion/ Air Outdoor Vl l.G-2 Elastomer Shrinkage and Loss of Monitori ng 3.3. 1-61 E, 515 Exposed to Air Outdoor Separation (External) (A-20)

Strength Program Increased Hardness, Structu res PST - Elastomers -TFA- Shelter, Air Outdoor Vll. G-2 Elastomer Shrinkage and Loss of Monitoring 3.3.1-61 E, 515 Exposed to Ai r Outdoor Protection (External) (A-20)

Strength Program Increased Hardness, Structures PST - Elastomers -W PB- Expansion/ Air Outdoor Vll. G-2 Elastomer Shrinkage and Loss of Monitoring 3.3.1-6 1 E, 515 Exposed to Ai r Outdoor Separation (External) (A-20)

Strength Program

SBK-L- 17155 I Enclosure 2/ Page 135 U. S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

,.,.,

1

~~~~!'l.'lil l1 I I I :j* I *1 1* 11Y*, ; '~ !' Aging Table Intended "1 11 Aging Effect Requiring NUREG 1801 Component Type Material 1 Environment Management 3.X. 1 I Function I ' l*I* Management Vol. 2 Item I

I I' 'i T .( 1j: "'I' :l"lli* :1 P.rogram Item I

Increased Hardness, Structures PST - Elastomers -WPB- Shelter, Air Outdoor Vll.G-2 Elastomer Shrinkage and Loss of Monitoring 3.3.1-61 E, 515 Exposed to Air Outdoor Protection (External) (A-20)

Strength Program PST - Fire Penetration Seal - Air Indoor Increased Hardness, Fire Protection Vll. G- 1 COG- Exposed to Air Indoor Fire Barrier Elastomer Uncontrolled Shrinkage and Loss of 3.3.1-61 A Program (A-19)

Uncontrolled (External) Strength PST - Fire Penetration Seal - Air Indoor Increased Hardness, Fire Protection Vll.G-1 EFP- Exposed to Air Indoor Fire Barrier Elastomer Uncontrolled Shrinkage and Loss of 3.3.1-61 A Program (A-19)

Uncontrolled (External) Strength PST - Fire Penetration Seal - Air Indoor Increased Hardness, Fire Protection Vll.G-1 FSB- Exposed to Air Indoor Fire Barrier Elastomer Uncontrolled Shrinkage and Loss of 3.3.1-61 A Program (A-19)

Uncontrolled (External) Strength PST - Fire Penetration Seal - Air Indoor Increased Hardness, Fire Protection Vll.G-1 PAB- Exposed to Air Indoor Fire Barrier Elastomer Uncontrolled Shrinkage and Loss of 3.3.1 -61 A Program (A-19)

Uncontrolled (External) Strength PST - Fire Penetration Seal - Air Indoor Increased Hardness, Fire Protection Vll.G-1 PCEW- Exposed to Air Indoor Fire Barrier Elastomer Uncontrolled Shrinkage and Loss of 3.3 .1-61 A Program (A-19)

Uncontrolled (External) Strength

SBK-L-17 155 I Enclosure 2/ Page 136 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

,. ' 111. ,,

I Ag ing .Table '

Intended Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X. 1 Note Function Management Vol. 2 Item Program Item PST - Fire Penetration Seal - Air Indoor Increased Hardness, Fire Protection Vll. G- 1 WPB- Exposed to Air Indoor Fire Barrier Elastomer Uncontrolled Shrinkage and Loss of 3.3.1-61 A Program (A-19)

Uncontro lled (External) Strength PST - Lubrite Plate -PAB- Air Indoor Structures Structural 111. 82-2 Exposed to Air Indoor Lubrite Uncontrolled Loss of Mechanical Function Mon itoring 3.5.1 -52 A Support (TP-1)

Uncontrolled (External) Program Ground Structures PST - Reinforced Concrete - Cracking , Loss of Bond, Loss lll. A 1-4 Flood Barrier Concrete Water/Soil Mon itoring 3.5.1 -31 A COG- Below Grade of Material (Spalling, Scaling) (T-05)

(External) Program Ground Structures PST - Reinforced Concrete - Structu ral Cracking, Loss of Bond, Loss lll.A1 -4 Concrete Water/Soil Monitoring 3.5.1 -31 A COG- Below Grade Support of Material (Spalling , Scaling) (T-05)

(External) Program Structures Monitoring Program Al kali-Silica Ground Reaction (ASR)

PST - Reinforced Concrete - lll.A 1-2 A, E, Flood Barrier Concrete Water/Soil Expansion and Cracking Monitoring 3.5.1-27 COG- Below Grade (T-03) 517, 519 (External) Prog ram Building Deformation Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 137 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

' 10

' Aging

1 , ,

NU~E~ ' 1 ~01

'I' Aging Effect Requiring' *Table 1

1, ..

Intended Component Type Material Environment ' Man~gement 3.X.1 Note Function Management Vol. 2 lteni Program *item Structures Monitoring Program Alkali-Silica Ground Reaction (ASR)

PST - Reinforced Concrete - Structural lll.A1-2 AE , 517, Concrete W ater/Soil Expansion and Cracking Monitoring 3.5 .1-27 COG- Below Grade Support (T-03) 5 19 (External) Program Building Deformation Monitoring Proaram Ground Increase in Porosity and Structures PST - Reinforced Concrete - lll.A1-5 Flood Barrier Concrete Water/Soil Permeability, Cracking , Loss Monitoring 3.5 .1-3 1 A COG- Below Grade (T-07)

(External) of Material (Spalling , Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A1-5 Concrete Water/Soil Permeability, Cracking , Loss Monitoring 3.5.1-31 A COG- Below Grade Support (T-07)

(External) of Material (Spalling, Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - lll.A1-7 Flood Barrier Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-32 A, 509 COG- Below Grade (T-02)

(External) Strength Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A1-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-32 A , 509 COG- Below Grade Support (T-02)

(External) Strength Program

SBK-L- 17 155 I Enclosure 2/ Page 138 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures S ummary of Aging Management Evaluation

,,

Intended :.

11 I

Ii II :I l,'

Agmg Eft'.ect Requmng II '. '.' !~ltl l,f*j:i:;: li I

1Hi'!1

'l'*r,t .*!<

Aging j

' '"ti NUREG 1801 I" 1 11 . Table I

Component Type Material Environment Management .3.X.1 Note Function Management Program v o1. 21tem'1 Item Ground Structures PST - Reinforced Concrete - lll.A3-6 Flood Barrier Concrete Water/Soil Loss of Material , Cracking Monitoring 3.5.1-26 A COG- Below Grade (T-0 1)

(External) Program Ground Structures PST - Reinforced Concrete - Structural ll l.A3-6 Concrete Water/Soil Loss of Materi al, Cracking Monitoring 3.5.1-26 A COG- Below Grade Support (T-0 1)

(External) Program PST - Re inforced Concrete - Air Indoor Fire Protection Vll. G-29 COG - Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Loss of Material 3.3.1-67 A Program (A-91)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Fire Protection V ll. G-29 COG- Exposed to Air Ind oor Concrete Uncontrolled Loss of Material 3.3.1-67 A Support Program (A-91)

Uncontrolled (External)

PST - Re inforced Con crete - Air Indoor Structures Cracki ng, Loss of Bond, Loss lll.A 1-9 COG- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Monitoring 3.5.1-23 A of Material (Spalling , Scaling ) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Structures Structural Cracking, Loss of Bond, Loss lll.A 1-9 COG- Exposed to Air Indoor Concrete Uncontrolled Monitoring 3.5.1 -23 A Support of Materia l (Spalling , Scaling) (T-04)

Uncontrolled (External) Program

SBK-L-17155 I Enclosure 2/ Page 139 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

, , *. l . ,1 , l {'"'II ' I' 'j'l'l'I' ~' ,,1 :!1.1i:!1J:i.11. ::!:*:1:1 1';1;1*::1; [T ,,. , .

il'f\;~qle ',,

1 11 Intended *' Aging Effect R~~~iri ~'g 'i:i' I 1 '1ii'l: 1 i:l ~gm~ 1 i;i1111}': 1 NUREG 1 ~ 1 80f I' 1 1 1ili:l 3.X.tl:i ;'

"Iii 'vb1t 2 1t~i'n" 11 ' Note

!

Component Type ' Material Environment Management ' 11" i 1.Management 1.j,1 1111 1

' 1 Function '

Program'1

1teln *'1' T 1111~t,:c1,1.1.,:1:*:

'1 ij' I ' ' '

i "I' :.;

1 **,. 'l 1,,

1

'

PST - Reinforced Concrete - Air Indoor Concrete Cracking and Fire Protection Vl l. G-28 COG- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled 3.3.1-65 A Spalling Program (A-90)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Concrete Cracking and Fire Protection Vll.G-28 COG- Exposed to Air Indoor Concrete Uncontrolled 3.3 .1-65 A Support Spalling Program (A-90)

Uncontrolled (External)

Structures Monitoring Program Alkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Air Indoor Monitoring 111.A1 -2 A , E, COG- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Expansion and Cracking 3.5.1 -27 Program (T-03) 517 , 519 Uncontrolled (External)

Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR)

Structural 111.A1-2 A , E, COG- Exposed to Air Indoor Concrete Uncontrolled Expansion and Cracking Monitoring 3.5.1-27 Support (T-03) 517 , 519 Uncontrolled (External) Program Building Deformation Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 140 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

,, l ,I ~' : i'i ,I !lI ' 'i' ~

Agirig' 1:1'!1:1,, 11 ';i':1:NUREG I jq ,:hi. .pl:1:1:1:r:*1

.,1 1.1. ti Aging ' Effect Requiring II

'1801 , Table i:I ,,

Intended 'I' ' ,j, Component Type Material Environment Management ,:,

Function Managem~nt Vol. 2 Item' '\ 3;x.1 * Note Program Item ' ,;:1.

PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures lll.A1 -10 COG- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5.1-24 A (T-06)

Uncontrolled (External) of Material (Spalling , Scaling) Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures Structural lll.A1-10 COG- Exposed to Air Indoor Concrete Uncontrolled Permeability, Cracking, Loss Monitoring 3.5 .1-24 A Support (T-06)

Uncontrolled (External) of Material (Spalling, Scaling) Program Structures PST - Reinforced Concrete - Air Outdoor Cracking, Loss of Bond , Loss lll.A1-9 Missile Barrier Concrete Monitoring 3.5 .1-23 A COG- Exposed to Air Outdoor (External) of Material (Spalling , Scaling) (T-04)

Program Structures PST - Reinforced Concrete - Shelter, Air Outdoor Cracking, Loss of Bond, Loss lll.A1 -9 Concrete Monitoring 3.5.1-23 A COG- Exposed to Air Outdoor Protection (External) of Material (Sp alling , Scaling) (T-04)

Program Structures Monitoring Program Alkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Air Outdoor lll.A1-2 A , E, Missile Barrier Concrete Expan sion and Cracking Monitoring 3.5. 1-27 COG- Exposed to Air Outdoor (External) (T-03) 517, 519 Program Building Deformation Monitoring Program

SBK-L-17155 / Enclosure2/ Page 14 1 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

,,,,, I 1l *1 1 ;.J. *1*

1 1

,j;, 1:.

I I Aging Table Intended Aging Effect Requiring NUREG 1801 Component Type Material Environment " Management 3.X.1 Note Function Management Vol. 2 Item Program Item Structures Monitoring Program Alka li-Silica Reaction (ASR)

PST - Reinforced Concrete - Shelter, Air Outdoor lll.A1 -2 A, E, Concrete Expansion and Cracking Monitoring 3.5.1 -27 COG- Exposed to Air Outdoor Protection (External) (T-03) 517, 519 Program Building Deformation Monitoring Proa ram Increase in Porosity and Structures PST - Re inforced Concrete - Air Outdoor lll.A 1-10 Missile Barrier Concrete Permeability, Cracking , Loss Monitoring 3.5.1-24 A COG- Exposed to Air Outdoor (External) (T-06) of Material (Spalling , Scaling) Program Increase in Porosity and Structures PST - Re inforced Concrete - Shelter, Air Outdoor ll l.A1 -10 Concrete Permeability, Cracking , Loss Monitoring 3.5.1 -24 A COG- Exposed to Air Outdoor Protection (External) (T-06) of Material (Spall ing , Scaling) Program Structures PST - Re inforced Concrete - Air Outdoor ll l.A1-6 Missile Barrier Concrete Loss of Material , Cracking Monitoring 3.5. 1-26 A COG- Exposed to Air Outdoor (External) (T-01)

Program Structures PST - Reinforced Concrete - Shelter, Air Outdoor ll l.A1 -6 Concrete Loss of Material , Cracking Monitoring 3.5.1 -26 A COG- Expo sed to Air Outdoor Protection (Extern al) (T-01 )

Program

SBK-L-17155 I Enclosure 2/ Page 142 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1:1; ' Agir\g' I 'I;: '1 11 1:/'i'lil' *l"I . 'l!I.'

/ Intended Aging Effect Requiring 1 *

, NUREG 1801 r Table ' ,!1' ti'; 11:11'1 I!

Component Type Material Environment Management 3.X.1 Note : .. 1 Function Management Vol. 2 Item '.../',:l:j:: *I Program Item I

" ' '

Structures PST - Reinforced Concrete - Structural Raw Water Cracking , Loss of Bond, Loss 111.A1-4 Concrete Monitoring 3.5.1-31 A, 512 CDG- Exposed to Raw Water Support (External) of Material (Spalling, Scaling) (T-05)

Program Structu res Monitoring Program Alkali-Silica Reaction (ASR) A, 512, E PST - Reinforced Concrete - Structural Raw Water lll.A1-2 Concrete Expansion and Cracking Monitoring 3.5.1-27 ' 517, CDG- Exposed to Raw Water Support (External) (T-03)

Program 519 Building Deformation Monitoring Proqram Ground Structures PST - Reinforced Concrete - Structural Cracking, Loss of Bond, Loss 111.A3-4 Concrete Water/Soil Monitoring 3.5.1-31 A CEHMS- Below Grade Support of Material (Spalling, Scaling) (T-05)

(External) Program Structures Monitoring Program Alkali-Silica Ground Reaction (ASR)

PST - Reinforced Concrete - Structural 111.A3-2 A, E, Concrete Water/Soil Expansion and Cracking Monitoring 3.5.1 -27 CEHMS- Below Grade Support (T-03) 517, 519 (External) Program Building Deformation Monitoring Proqram

SBK-L-17155 I Enclosure 2/ Page 143 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1

1:1 Ag/ng 11 1: I

);

' 1:1 1;; i!li I 11 Table .

1 Intended Aging Effect Requiring NUREG 1801 3.X.1 '

Component Type Material Environment Management Note Function Management Vol. 2 Item Program Item Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-5 Concrete Water/Soil Permeability, Cracking , Loss Monitoring 3.5.1-31 A CEHMS- Below Grade Support (T-07)

(External) of Material (Spalling , Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1 -32 A , 509 CEHMS - Below Grade Support (T-02)

(External) Strength Program Ground Structures PST - Reinforced Concrete - Structural lll.A3-6 Concrete Water/Soil Loss of Material , Cracking Monitoring 3.5.1-26 A CEHMS- Below Grade Support (T-01)

(External) Program PST - Reinforced Concrete - Structures Air Outdoor Cracking, Loss of Bond, Loss lll.A3-9 CEHMS- Exposed to Air Missile Barrier Concrete Monitoring 3.5.1-23 A (External) of Material (Spalling, Scaling) (T-04)

Outdoor Program Structures Monitoring Program Alkali-Silica PST - Re inforced Concrete - Reaction (ASR)

Air Outdoor lll.A3-2 A, E, CEHMS- Exposed to Air Missile Barrier Concrete Expansi on and Cracking Monitoring 3.5 .1-27 (External) (T-03) 517, 519 Outdoor Program Building Deformation Monitoring Proaram

SBK-L-17155 I Enclosure 2/ Page 144 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1111'1' ' ['111'1"1' 1'l'l"IT1"1' 'llfl iil:1: IT:1!ji:,1.,j ~ ,:.: 111:11:+1 .. ' 1*1<<1'"';1

! 1*

11 ~I',,,,+ l'i!l:if'I: 111 1 I

.,: ~

'I i

! :

!

1'1* ' 111 Aging .. r 1

1i:Taple i; . !' '

i! :l,1 f~~]il'IJ

'

Intended Ag1,ng Efl'.ect1 Req\J m'lg '11 fl ],Ill,,, IJl"I 11 NUREG'[1 sot Component "f;ype II',

Function !1.11' Material Environment Management 1 , *, 1 1*k,Management '1:i 111 1 1:*1:i,vol'.:1 211i0ln'mJ1, fl Note 1l1vHl:11111,.

" :1 ii~ !

' P,r6gram ,!!l':)l ! "n:u11j::!'1 '"':11:1 : 11 :1:1:1' 1f:.1.,J*i:;

PST - Reinforced Concrete - Increase in Porosity and Structures Air Outdoor lll.A3-10 CEHMS- Exposed to Air Missile Barrier Concrete Permeabi lity, Cra cking, Loss Monitoring 3.5. 1-24 A (External) (T-06)

Outdoor of Material (Spalling, Scaling) Program PST - Reinforced Concrete - Structures Air Outdoor 111.A3-6 CEHMS- Expo sed to Air Missile Barrier Concrete Loss of Material, Cracking Monitoring 3.5, 1-26 A (External) (T-01)

Outdoor Program Ground Structures PST - Reinforced Concrete - Cracking , Loss of Bond, Loss ll l.A3-4 Flood Barrier Concrete Water/Soil Monitoring 3.5.1-31 A EFP- Below Grade of Material (Spalling, Scaling) (T-05)

(External) Program Ground Structures PST - Reinforced Con crete - Structural Cracking, Loss of Bond , Loss lll.A3-4 Concrete Water/Soil Monitoring 3.5.1-31 A EFP- Below Grade Support of Material (Spalling , Scaling) (T-05)

(External) Program Structures Monitoring Program Alkali-Silica Ground Reaction (ASR)

PST - Reinforced Concrete - lll.A3-2 A, E, Flood Barrier Concrete Water/So il Expan sion and Cracking Monitoring 3.5.1 -27 EFP- Below Grade (T-03) 517, 519 (External) Program Building Deformation Monitoring Proaram

SBK-L-17155 I Enclosure 2/ Page 145 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

':1: .Ii 1 11 Table ,,

'I {j Aging I *'

Intended Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X.1 Note Function Management Vol. 2 Item Program Item Structures Monitoring Program Alkali-Silica Ground Reaction (ASR)

PST - Reinforced Concrete - Structural lll.A3-2 A , E, Concrete Water/Soil Expansion and Cracking Monitoring 3.5.1-27 EFP- Below Grade Support (T-03) 517, 519 (External) Program Building Deformation Monitoring Proaram Ground Increase in Porosity and Structures PST - Reinforced Concrete - lll.A3-5 Flood Barrier Concrete Water/Soil Permeability, Cracking, Loss Monitoring 3.5.1-31 A EFP- Below Grade (T-07)

(External) of Material (Spalling, Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-5 Concrete Water/Soil Permeability, Cracking, Loss Monitoring 3.5.1-31 A EFP- Below Grade Support (T-07)

(External) of Material (Spall ing, Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-32 A, 509 EFP- Below Grade Support (T-02)

(External) Strength Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-32 A, 509 EFP- Below Grade Support (T-02)

(External) Strength Program

SBK-L-171 55 /Enclosure 2/Page 146 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluatio n Aging Table Intended Aging Effect Requiring NU REG 1801 Component Type Material Environment Management 3.X. 1 Note Function Management Vol. 2 Item Program Item ..,

Ground Structures PST - Reinforced Concrete - lll.A3-6 Flood Barrier Concrete Water/Soil Loss of Material, Cracking Monitoring 3.5.1-26 A EFP- Below Grade (T-01)

(External) Program Ground Structu res PST - Reinforced Concrete - Structural lll.A3-6 Concrete Water/Soil Loss of Material , Cracking Monitoring 3.5.1-26 A EFP- Below Grade Support (T-01 )

(External) Program PST - Reinforced Concrete - Air Indoor Fire Protection Vll. G-29 EFP- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Loss of Material 3.3.1 -67 A Program (A-91)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Fire Protection Vll. G-29 EFP- Exposed to Air Indoor Concrete Uncontrolled Loss of Material 3.3.1 -67 A Support Prog ram (A-91)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Stru ctu res Cracking , Loss of Bond , Loss lll.A3-9 EFP- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Monitoring 3.5 .1 -23 A of Material (Spall ing, Scaling) (T-04)

Uncontrol led (External) Program PST - Reinforced Concrete - Air Indoor Stru ctures Structural Cracking , Loss of Bond , Loss lll.A3-9 EFP- Exposed to Air Indoor Concrete Uncontrolled Monitoring 3.5.1-23 A Support of Material (Spalling, Scaling) (T-04)

Uncontrolled (External) Program

SBK-L-1 71 55 I Enclosure 2/ Page 147 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Stru ctures Summary of Aging Management Evaluation

,, ,,,

Aging Table Intended Aging Effect Requiring NUREG 1801 Component Type Material ,,, Environment Management 3.X.1 Note Function Management Vol. 2 Item Program Item PST - Reinforced Concrete - Air Indoor Concrete Cracking and Fire Protection Vll.G-2 8 EFP- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled 3.3.1 -65 A Spalling Program (A-90)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Concrete Cracking and Fire Protection Vll.G-28 EFP- Exposed to Air Indoor Concrete Uncontrolled 3.3 .1-65 A Support Spalling Program (A-90)

Uncontrolled (External)

Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR) lll.A3-2 A, E, EFP- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Expansion and Cracking Monitoring 3.5. 1-27 (T-03) 517, 519 Uncontrolled (External) Program Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR)

Structural lll.A3-2 A , E, EFP- Exp osed to Air Indoor Concrete Uncontrolled Expan sion and Cracking Monitoring 3.5.1-27 Support (T-03) 517 , 519 Uncontrolled (External) Program Building Deformation Monitoring Program

SBK-L-17 155 I Enclosure 2/ Page 148 U. S. Nuclear Regulatory Commiss ion Table 3.5.2-5 Primary Structures Summary of Ag ing Management Eva luation 1:1 ,,,

}I ' 111 1lli ' Ag ing I I*

i:I Ill 1:1 . Table Intended Environment *:I ' Jil Aging Effect* Requ iring i,lll NU REG 1801 *

Component Type

Function

'I:

I ii' Material

'I" *:1*1 1

',11. Ji r.lian~9Eim e~t ,11, 11

n 11 Management

,, prog ramL1 ..'l' 1iil:1M* . V oL 21item jj 1*1 il'ljl *

'Jr3cX; 1 iii'] :J!l:ll'I :: 1:IJlil :* iH ltem,)!I' Note i.1,I,,., *I , i' PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures lll. A3-10 EFP- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5, 1-24 A (T-06)

Uncontrolled (External) of Material (Spalling, Scaling) Prog ram PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures Structural lll .A3-10 EFP- Exposed to Air Indoor Concrete Uncontrolled Permeability, Cracking, Loss Monitoring 3.5 .1 -24 A Support (T-06)

Uncontrolled (External) of Material (Spalling , Scaling) Program Structures PST - Reinforced Concrete - Air Outdoor Cracking, Loss of Bond, Loss lll.A3-9 Missile Barrier Concrete Mon itoring 3.5.1 -23 A EFP- Exposed to Air Outdoor (External) of Material (Spalling , Scaling) (T-04)

Program Structures PST - Reinforced Concrete - Shelter, Air Outdoor Cracking , Loss of Bond , Loss lll.A3-9 Concrete Monitoring 3.5 ,1-23 A EFP- Exposed to Air Outdoor Protection (External) of Material (Spalling , Scaling) (T-04)

Program Structures Monitoring Program A lkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Air Outdoor lll.A3-2 A, E, Missile Barrier Concrete Expansion and Cracking Monitoring 3.5, 1-27 EFP- Exposed to Air Outdoor (External) (T-03) 517, 5 19 Prog ram Building Deform ation Monitorin g Proqram

SBK-L- 171 55 I Enclosure 2/ Page 149 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

' ' ' '"11 ,, ti : ,j1l':11'!! ' ,l*I :li.,4_'i' ,. 'I' , !j:I 1: ,,,

~gipg Effect Requ iring ljj' 1' 1l'IManage' gmg Table \'

1 I 1:11 '

Intended NUREG 1801 Component Type , Material Environment 1 m ent ' *Ir 3.x .1 Note Function Management Vol. 2 Item Program Item Structures Mon itoring Program Al kali-Silica Reacti on (ASR)

PST - Reinforced Concrete - Shelter, Air Outdoor Mon itoring 111.A3-2 A , E, Concrete Expansion and Cracking 3.5.1 -27 EFP- Exposed to Air Outdoor Protection (External) Program (T-03) 517, 519 Building Deformation Monitoring Program Increase in Porosity and Structures PST - Re inforced Concrete - Air Outdoor lll.A3- 10 Missile Barrier Concrete Permeability, Cracking , Loss Monitoring 3.5.1-24 A EFP- Exposed to Air Outdoor (External) (T-06) of Material (Spalling , Scaling) Program Increase in Porosity and Structures PST - Reinforced Concrete - Shelter, Air Outdoor lll.A3-10 Concrete Permeabi lity, Cracking, Loss Monitoring 3.5.1 -24 A EFP- Exposed to Air Outdoor Protection (External) (T-06) of Material (Spalling , Sca ling) Program Structures PST - Reinfo rced Concrete - Air Outdoor ll\.A3-6 Missile Barrier Concrete Loss of Material, Cracking Monitoring 3.5.1 -26 A EFP- Exposed to Air Outdoor (External) (T-0 1)

Program Structures PST - Reinfo rced Concrete - Shelter, Air Outdoor lll.A3-6 Concrete Loss of Material, Cracking Monitoring 3.5.1 -26 A EFP- Exposed to Air Outdoor Protection (External) (T-01)

Program

SBK-L-171 55 I Encl osure 2/ Page 150 U. S. Nuclear Regulatory Commission Tab le 3.5.2-5 Primary Structures Sum mary of Ag ing Management Ev aluat ion

",,,1;, ':, _,!11_i:1, ,

1

l~l *j*I* ;.

.I*;* .

ii',' 1:i: ,:1111 1, ' :1;1:* ,:1:: :f*' I:' ' '

, Ag ing , 1 1:1IT~ble' 'Iii

'I Component Type Intended Function Material Environmeht 11:1,, , 1 , 11 , tig1,~~~~=~l~:~~i ri ng 111111 i: 1111:1': Management , . NU REG 1 ~ 9 ~ , ,, '

, ,,,i, , :Vol. 2 Item1 :h 1:Jl ~.,~ . t }I Note

, i:i,,,l:v:1, 1 1 g Ji,, 1:1. *," , 1J Prog~~m.1: Ii' 1:1: ':1111it, 1il'jli1!lli;1 111: Item

- '

Structures PST - Reinforced Concrete - Structural Raw Water Cracking , Loss of Bond , Loss lll. A3-4 Concrete Monitoring 3.5. 1-3 1 A, 512 EFP- Exposed to Raw Water Support (External) of Material (Spalling, Scaling) (T-05)

Program Structures Monitoring Program A lkali-S ilica Reaction (ASR) A, 512, PST - Reinforced Concrete - Structural Raw Water 111.A3-2 Concrete Expansion and Cracking Monitoring 3.5. 1-27 E, 517, EFP- Exposed to Raw Water Support (External) (T-03)

Program 519 Building Deformation Monitorin g Proqram Ground Structures PST - Re inforced Concrete - Cracking , Loss of Bond , Loss lll.A5-4 Flood Barrier Concrete Water/Soil Monitoring 3.5. 1-3 1 A FSB- Below Grade of Material (Spalling , Scaling) (T-05)

(External) Program Ground Structures PST - Reinforced Concrete - Structural Cracking, Loss of Bond , Loss lll.A5-4 Concrete Water/Soil Monitoring 3.5. 1-31 A FSB- Below Grade Support of Material (Spalling , Scaling) (T-05)

(External) Program Structures Monitoring Program Ground PST - Reinforced Concrete - lll.A5-2 A, E, Flood Barrier Concrete Water/Soil Expansion and Cracking Al kali-Silica 3.5 .1-27 FSB- Be low Grade (T-03) 517, 519 (External) Reaction (ASR)

Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 151 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

,, ':

1: Aging ' Table Intended , Aging Effect Requiring

NUREG 1801 Component Type Material Environment ' Management 3.X.1 Note Function Management Vol. 2 Item Program Item Building Deformation Monitoring Program Structures Monitoring Program Alkali-S ilica Ground Reaction (ASR)

PST - Reinforced Concrete - Structural 111.A5-2 A, E, Concrete Water/Soil Expansion and Cracking Monitoring 3.5.1-27 FSB- Below Grade Support (T-03) 517, 5 19 (External) Program Building Deformation Monitoring Proaram Ground Increase in Porosity and Structures PST - Reinforced Concrete - lll.A5-5 Flood Barrier Concrete Water/Soil Permeability, Cracking , Los s Monitoring 3.5.1-31 A FSB- Below Grade (T-07)

(External) of Material (Spalling, Sca ling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A5-5 Concrete Water/Soil Permeability, Cracking , Loss Monitoring 3.5. 1-31 A FSB- Below Grade Support (T-07)

(External) of Material (Spalling, Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A5-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-31 A, 509 FSB- Below Grade Support (T-02)

(External) Strength Program

SBK-L-17155 I Enclosure 2/ Page 152 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1:: ', Aging Table

'* Intended Aging Effect Requiring NU REG 1801 Component Type Material Environment* Management 3.X.1 Note Function ;:I ' : , Management Vol .. 2 .ltem I

.

1:1 I*

111'1 .'li'l!I l*11:'"11l:ff 1

'I *' 'tl1ii' 111 :j:I ,., ,,,, ., Pr9gram ,

1 I ;' 1 ::::p,., 111:1'i'*'l}*!,:!:1 *l'"11* J~e'T1.1i:,.: :

Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural Ill.AS-?

Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-31 A, 509 FSB- Below Grade Support (T-02)

(External) Strength Program Ground Structures PST - Reinforced Concrete - 111.AS-6 Flood Barrier Concrete Water/Soil Loss of Material, Cracking Monitoring 3.5.1-26 A FSB- Below Grade (T-01)

(External) Program Ground Structures PST - Reinforced Concrete - Structural 111.AS-6 Concrete Water/Soil Loss of Material, Cracking Monitoring 3.5.1-26 A FSB- Below Grade Support (T-01)

(External) Program PST - Reinforced Concrete - Air Indoor Fire Protection Vll.G-29 FSB- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Loss of Material 3.3.1-67 A Program (A-91)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Fire Protection Vll.G-29 FSB- Exposed to Air Indoor Shielding Concrete Uncontrolled Loss of Material 3.3.1-67 A Program (A-9 1)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Fire Protection V ll .G-29 FSB- Exposed to Air Indoor Concrete Uncontrolled Loss of Material 3.3 .1-67 A Support Program (A-91)

Uncontrolled (External)

SBK-L-17 155 I Enclosure 2/ Page 153 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

Aging Table Intended Aging Effect Requ iring NUREG 1801

.; Environment ***'

Component Type Material Management 3.X.1 Note Function Management Vol. 2 Item Program Item PST - Reinforced Concrete - Air Indoor Structures Cracking , Loss of Bond , Loss lll. A5-9 FSB- Exposed to Air Indoor Fire Ba rrier Concrete Uncontrolled Monitoring 3.5.1 -2 3 A of Materi al (Spalling, Scaling) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Structures Cracking , Loss of Bond , Loss lll.A5-9 FSB- Exposed to Air Indoor Shield ing Concrete Uncontrolled Monitoring 3.5. 1-23 A of Material (Spalling, Scaling ) (T-04)

Uncontrolled (External) Program PST - Re inforced Concrete - Air Indoor Structures Structural Cracking, Loss of Bond , Loss lll.A5-9 FSB- Exposed to Air Indoor Concrete Uncontro lled Mon itoring 3.5.1-23 A Support of Material (Spalling , Sca ling) (T-04)

Uncontrolled (External) Program PST - Re inforced Concrete - Air Indoor Concrete Cracking and Fire Protection Vll. G-28 FSB- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled 3.3. 1-65 A Spalling Program (A-90)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Concrete Cracking and Fire Protection V ll.G-28 FSB- Exposed to Air Indoor Shielding Concrete Uncontrolled 3.3.1 -65 A Spalli ng Prog ram (A-90)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Concrete Cracking and Fire Protection V ll. G-28 FSB- Exposed to Air Indoor Concrete Uncontrolled 3.3.1 -65 A Support Spalling Program (A-90)

Uncontrolled (External)

SBK-L-17155 I Enclosure 2/ Page 154 U. S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation l!'1' :I: 11IJ":l!I; 'I' :11(1: i:1!I.,. :Iii: :11,

i;::fab1~ '111 1* 1

I: i]li.,. * :11 1 * ** I 111 Ag'ing 1 , .

.Intended , {'-gir:i,9 ,Effect 1 Rrq~i,rin g 'l 1 I1* ilil N:u~EG1 1 1 ~~1 1 1 1 1 1

~ pte:

I 'I: I 11f Component Type Material Environment 11 111 !I

. :1:1 h function

I,'

'::1 " Manageinen't " '!;, "* 11 I '

1

Management

,.!, ,I, ii! 1~rog~am J.il:,

{I' I l,j1j::: ,: .i:I'.'Vc 'I' 211tehl

,,' :l\J'.: 111 !11: I:

11 ' 1111 1

"

- 1

1 ~tJ~*"I 1: l

!f:;,

~ r .:,. .i Structures Monitoring Program Alkali-Si lica PST - Reinforced Concrete - Air Indoor Reaction (ASR) lll. A5-2 A, E, FSB- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Expan sion and Cracking Monitoring 3.5.1 -27 (T-03) 517, 519 Uncontrolled (External) Program Building Deformation Monitoring Proqram Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR) lll.A5-2 A, E, FSB- Exposed to Air Indoor Shielding Concrete Uncontrolled Expansion and Cracking Monitoring 3.5.1 -27 (T-03) 517 , 519 Uncontrolled (External) Program Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR)

Structural lll.A5-2 A, E, FSB- Exposed to Air Indoor Concrete Uncontrolled Expansion and Cracking Monitoring 3.5. 1-27 Support (T-03) 517, 519 Uncontrolled (External) Program Building Deformation Monitoring Proqram

SBK-L-17155 I Enclosure 2/ Page 155 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation I

I .

Aging ' **I I I Table Intended Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X. 1 Note Function Management Vol. 2 Item Program Item PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures lll.A5-10 FSB- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5.1-24 A (T-06)

Uncontrolled (External) of Material (Spalling, Scaling) Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures lll.A5-10 FSB- Exposed to Air Indoor Shielding Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5 .1-24 A (T-06)

Uncontrolled (External) of Material (Spalling, Scaling) Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures Structural l ll.A5-10 FSB- Exposed to Air Indoor Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5.1 -24 A Support (T-06)

Uncontrolled (External) of Material (Spalling, Scaling) Program Structures PST - Reinforced Concrete - Air Outdoor Cracking , Loss of Bond , Loss lll.A5-9 Missile Barrier Concrete Monitoring 3.5. 1-23 A FSB- Exp osed to Air Outdoor (External) of Material (Spalling, Scaling) (T-04)

Program Structures PST - Reinforced Concrete - Shelter, Ai r Outdoor Cracking , Loss of Bond , Loss lll .A5-9 Concrete Monitoring 3.5. 1-23 A FSB- Exposed to Air Outdoor Protection (External) of Material (Spalling, Scaling) (T-04)

Program Structures Monitoring Program PST - Reinforced Concrete - Air Outdoor Alkali-Silica lll.A5-2 A , E, Missile Barrier I Concrete (External)

Expansion and Cracking Reaction (ASR) (T-03) 3.5.1-27 FSB- Exposed to Air Outdoor 517, 519 Monitoring Program Buildinq

SBK-L-17155 I Enclosure 2/ Page 156 U.S . Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1,

Aging l'I ,11 " :1:1', /', '

Table Intended Aging Effect Requiring NUREG '1801 " ;,

,,

Component Type Material Environment Management ' 11 3.X.1 Note Function Man'agement Vol. 2 Item Program Item Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Shelter, Air Outdoor lll. A5-2 A, E, Concrete Expansion and Cracking Monitoring 3.5.1 -27 FSB- Exposed to Air Outdoor Protection (External) (T-03) 517, 519 Program Building Deformation Monitoring Proaram Increase in Porosity and Structures PST - Reinforced Concrete - Air Outdoor lll.A5-10 Missile Barrier Concrete Permeability, Cracking, Loss Monitoring 3.5 .1-24 A FSB- Exposed to Air Outdoor (External) (T-06) of Material (Spalling, Scaling) Program Increase in Porosity and Structures PST - Re inforced Concrete - Shelter, Air Outdoor lll.A5-10 Concrete Permeability, Cracking , Loss Monitoring 3.5.1-24 A FSB- Exposed to Air Outdoor Protection (External) (T-06) of Material (Spalling, Scaling) Program Structures PST - Re inforced Concrete - Air Outdoor lll. A5-6 Missile Barrier Concrete Loss of Material, Cracking Monitoring 3.5.1 -26 A FSB- Exposed to Air Outdoor (External) (T-01 )

Program

SBK-L-17155 I Enclosure 2/ Page 157 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

l*I 1:1 *1:' ii' .J Aging Table I

.i:I:

Intended 111 Aging .Effect Requiring NUREG 1801 Component Type Material ,,:

11 Environment Management 3.X.1 Note I Function Management Vol. 2 Item I I!! :, ', ::1 :, :j11 1

.I* Program Item Structures PST - Reinforced Concrete - Shelter, Air Outdoor lll.A5-6 Concrete Loss of Material, Cracking Monitoring 3.5.1-26 A FSB- Exposed to Air Outdoor Protection (External) (T-0 1)

Program Structures PST - Reinforced Concrete - Structural Raw Water Cracking, Loss of Bond, Loss lll.A5-4 Concrete Monitoring 3.5.1 -3 1 A, 512 FSB- Exposed to Raw Water Support (External) of Material (Spalling, Scaling) (T-05)

Program Structures Monitoring Program Alkali-Silica Reaction (ASR) A, 512, PST - Reinforced Concrete - Structural Raw Water lll.A5-2 Concrete Expansion and Cracking Monitoring 3.5 .1-27 E, 517, FSB- Exposed to Raw Water Support (External) (T-03)

Program 519 Building Deformation Monitoring Proaram Ground Structures PST - Reinforced Concrete - Cracking, Loss of Bond, Loss lll.A3-4 Flood Barrier Concrete Water/Soil Monitoring 3.5.1 -31 A PAB- Below Grade of Material (Spalling , Scaling) (T-05)

(External) Program Ground Structures PST - Reinforced Concrete - Structural Cracking, Loss of Bond, Loss lll.A3-4 Concrete Water/Soil Monitoring 3.5.1 -31 A PAB- Below Grade Support of Material (Spalling, Scaling) (T-05)

(External) Program

SBK-L-17155 I Enclosure 2/ Page 158 U. S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluati on I

I :* I ' I Aging Table ni1 Intended , I lili Aging Effect Requiring NUREG 1801 Com.ponent Type Material Environ '"l:1. ~ ~~ :ii 11 Management 3.X.1 Note Function '" 11 Management Vol. 2 Item 11 i11 i.1 Iii' rilil : ,;;;: :11 Program :item Structu res Monitoring Program Alkali-Silica Ground Reaction (ASR)

PST - Reinforced Concrete - lll.A3-2 A, E, Flood Barrier Concrete Water/Soil Expansion and Cracking Monitoring 3.5 .1-27 PAB- Below Grade (T-03) 517, 519 (External) Program Building Deformation Monitoring Proqram Structures Monitoring Program Alkal i-S ilica Ground Reaction (ASR)

PST - Reinforced Concrete - Structural ll l.A3-2 A, E, Concrete Water/Soil Expansion and Cracking Monitoring 3.5.1 -27 PAB- Below Grade Support (T-03) 517, 519 (External) Program Building Deformation Monitoring Proaram Ground Increase in Porosity and Structures PST - Reinforced Concrete - 111.A3-5 Flood Barrier Concrete Water/Soil Permeability, Cracking , Loss Monitoring 3.5.1 -3 1 A PAB- Below Grade (T-07)

(External ) of Material (Spalling , Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural ll l.A3-5 Concrete Water/Soil Permeability, Cracking, Loss Monitori ng 3.5. 1-3 1 A PAB- Below Grade Support (T-07)

(External) of Material (Spalling , Scaling) Program

SBK-L-17 155 I Enclosure 2/ Page 159 U. S. Nuclear Regulatory Commission Tab le 3.5.2-5 Primary Structures Summary of Ag i ng Management Evaluat ion

,,

,,,. A ging ,

, NUREG 1B01iil: +;:~able '

1:,*, :IJtFil"' :1;, 'I' I ':i!!:'f I '!:::': I: 1

't I I I

'I Intended ,11 , Aging .E:ttei;t Requ iring ,:,

1:: * ' 1'l111 M4hag~m~nt ' *i [,:lil ..,1:1f I 1 em : 1'*,31tem' '! x] ~ 1l'lli Component Type Material Envi ronment I, 1 11 1 lt'"'Mah age'm ent ' i'I ' ' V i '2 1,{ ,i,'iji 1 + Note Function I', o ,. '

Ii 11 11 ,,,, :,' "1'h Hi!: '.11:i,I. ' '1'1 H1i:1 i'I::'"' !ll:i11il l'i:' l*Jili iJ * . iH

' ,1:111,,,,

I Rrpg ' ~~m lfl , ,1111*1il11 l1;1ilil1,111 l*,:1:1111111i:l 1 11 1

' ' 11': :1:, 1 1

,

1:l.1:1JI "I ,,, ,,,**h:1., di* ,:i"'ii Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5. 1-32 A, 509 PAB- Below Grade Support (T-02)

(External) Strength Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5 .1-32 A, 509 PAS- Below Grade Support (T-02 )

(External) Strength Program Ground Structures PST - Reinforced Concrete - lll.A3-6 Flood Barrier Concrete Water/Soil Loss of Material , Cracking Monitoring 3.5. 1-26 A PAB- Below Grade (T-01 )

(External) Prog ram Ground Structures PST - Reinforced Concrete - Structural lll.A3-6 Concrete Water/Soil Loss of Material, Cracking Monitoring 3.5. 1-26 A PAS- Below Grade Support (T-0 1)

(External) Program PST - Reinforced Concrete - Air Indoor Fire Protection Vll .G-29 PAS- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Loss of Material 3.3. 1-67 A Program (A-9 1)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Fire Protection Vll .G-29 PAS- Exposed to Air Indoor Concrete Uncontrolled Loss of Material 3.3 .1-67 A Support Program (A-9 1)

Uncontrolled (External)

SBK-L-17155 I Enclosure 2/ Page 160 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1: I 1, 1;1:1:1,:1:

Aging Table Intended I Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X.1 Note Function Management Vol. 21tem Program Item PST - Reinforced Concrete - Air Indoor Structures Cracking, Loss of Bond, Loss lll.A3-9 PAB- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Monitoring 3.5.1-23 A of Material (Spalling , Scaling) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Structures Structural Cracking, Loss of Bond, Loss lll.A3-9 PAS- Exposed to Air Indoor Concrete Uncontrolled Monitoring 3.5.1-23 A Support of Material (Spalling, Scaling) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Concrete Cracking and Fire Protection Vll.G-28 PAS- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled 3.3.1-65 A Spalling Program (A-90)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Concrete Cracking and Fire Protection Vll.G-28 PAS- Exposed to Air Indoor Concrete Uncontrolled 3.3.1-65 A Support Spalling Program (A-90)

Uncontrolled (External)

Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR) ll l.A3-2 A , E, PAS- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Expan sion and Cracking Monitoring 3.5. 1-27 (T-03) 517 , 519 Uncontrolled (External) Program Building Deformation Monitoring Proaram

SBK-L- 17 155 I Enclosure 2/ Page 161 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluatio n 1

'\" * , 1:1 ~ !i1,,:f ;I ilA 11ii 11 '* 1:111 11 1:1ili1:1: , ';Ir'. '1, 1Jjj ,;li'1:1 1

,J,

" I

'I' . . 1'A . ' ,,,,. 1::* ;J:i ili1ili! .1!~l!l".jil11 1::' 1tt~bl1e [l'lif Intended , {'-gang Effect Requm r;i g 1'I' 11: ,11 ::J'i 1' ,.; g m g :ii1*1,( 'Ii NUREG.i1801':jil 1

'1 j:i. 'f Manag 1 e~ ent i:1+ 1 iJi . I*I' Note

'

Component Type Material Envi ro nment l: JI 1 1 I :I:

Funetion , Management

1 1. ' ' k : 11111v<:m Prog r~m 1 1 '1'*:1 .:;1 ,ti:,1

2. t0r.T{' .**, .. '3,.X.

11 *I'

'j:'

Item . 1 *Ii\ ** I ';I Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR)

Structural lll.A3-2 A , E, PAB- Exposed to Air Indoor Concrete Uncontrolled Expansion and Cracking Monitoring 3.5. 1-27 Support (T-03) 5 17, 519 Uncontrolled (External) Program Building Deformation Monitoring Proaram PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures lll.A3-10 PAS- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5.1 -24 A (T-06)

Uncontrolled (External) of Material (Spalling, Scaling) Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures Structural l ll.A3-10 PAB- Exposed to Air Indoor Concrete Uncontrolled Permeability, Cracking, Loss Monitoring 3.5. 1-24 A Support (T-06)

Uncontrolled (External) of Material (Spalling , Scaling) Program Structures PST - Reinforced Concrete - Air Outdoor Cracking, Loss of Bond, Loss 111.A3-9 Missile Barrier Concrete Monitoring 3.5.1 -23 A PAB- Exposed to Air Outdoor (External) of Material (Spalling , Scaling) (T-04)

Program Structures PST - Reinforced Concrete - Shelter, Air Outdoor Cracking, Loss of Bond, Loss 111.A3-9 Concrete Mon itoring 3.5. 1-23 A PAB- Exp osed to Air Outdoor Protection (External) of Material (Spalling, Scaling) (T-04)

Program

SBK-L-17155 I Enclosure 2/ Page 162 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Table Intended Aging Effect Requiring NUREG 1801 Component Type Material Envirohm~nt Management Management Vol. 2 Item 3.X.1 Note Function I*' **: Program lt~m Structures Monitoring Program Alkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Air Outdoor lll.A3-2 A, E, Missile Barrier Concrete Expansion and Cracking Monitoring 3.5.1-27 PAB- Exposed to Air Outdoor (External) (T-03) 517, 519 Program Building Deformation Monitoring Proqram Structures Monitoring Program Alkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Shelter, Air Outdoor lll. A3-2 A, E, Concrete Expan sion and Cracking Monitoring 3.5.1-27 PAB- Exposed to Air Outdoor Protection (External) (T-03) 517, 519 Program Building Deformation Monitoring Proaram Increase in Porosity and Structures PST - Reinforced Concrete - Air Outdoor lll.A3-10 Missile Barrier Concrete Permeability, Cracking , Loss Monitoring 3.5.1 -24 A PAB- Exposed to Air Outdoor (External) (T-06) of Material (Spalling , Scaling) Program Increase in Porosity and Structures PST - Reinforced Concrete - Shelter, Air Outdoor lll.A3-10 Concrete Permeability, Cracking, Loss Monitoring 3.5.1 -24 A PAB- Exposed to Air Outdoor Protection (External) (T-06) of Mate rial (Spalling , Scaling) Program

SBK-L-17155 I Enclosure 2/ Page 163 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation l:i', ' ,.1 Aging 1 Table NU REG 1so1 II f:J 1:1.

Intended .Aging 1Effect Requiring :

Component Type Material Environment 1 Management 3.X.1 Note Function Management Vol. 2 Item Progra.m Item Structures PST - Reinforced Concrete - Air Outdoor lll.A3-6 Missile Barrier Concrete Loss of Material, Cracking Monitoring 3.5.1-26 A PAB- Exp osed to Air Outdoor (External) (T-01)

Program Structures PST - Reinforced Concrete - Shelter, Air Outdoor 111.A3-6 Concrete Loss of Material , Cracking Monitoring 3.5. 1-26 A PAB- Exposed to Air Outdoor Protection (External) (T-01 )

Program Ground Structures PST - Reinforced Concrete - Cracking , Loss of Bond , Loss lll.A3-4 Flood Barrier Concrete Water/Soil Monitoring 3.5.1-31 A PCEW- Below Grade of Material (Spalling, Scaling) (T-05)

(External) Program Ground Structures PST - Reinforced Concrete - Structural Cracking, Loss of Bond , Loss 111.A3-4 Concrete Water/Soil Monitoring 3.5.1-31 A PCEW- Below Grade Support of Material (Spalling, Scaling) (T-05)

(External) Program Structures Monitoring Program Alkali-Silica Ground Reaction (ASR)

PST - Reinforced Concrete - lll.A3-2 A, E, Flood Barrier Concrete Water/Soil Expansion and Cracking Monitoring 3.5.1 -27 PCEW- Below Grade (T-03) 517, 519 (External) Program Building Deformation Monitoring Proqram

SBK-L- 17155 I Enclosure 2/ Page 164 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1: ,, , ' II'::,,,,, '*11*1*

1:1 ,,

Aging Table Environ~ent,l:f Intended 1 1 'Aging Effect Requiring NUREG 1801 Component Type Material Management 3.X. 1 Note Vol. 2 lt~m, ., ,

11 Function ll,,iij' 1111,+

" ,1,1:1l::,:r*"'l',.'j1'***I*,

1 .ji11 ManagelT)ent :l1l *!:1J11l*1, *:* "H ~rogram 11111',' 1l*i'IFl'I ' J1,1 '~~ITl 1:1('1 '

Structures Monitoring Program Alkali-Silica Ground Reaction (ASR)

PST - Reinforced Concrete - Structural ll l.A3-2 A, E, Concrete Water/Soil Expansion and Cracking Monitoring 3.5.1 -27 PCEW- Below Grade Support (T-03) 517, 519 (External) Program Building Deformation Monitoring Proaram Ground Increase in Porosity and Structures PST - Reinforced Concrete - lll.A3-5 Flood Barrier Concrete Water/Soil Permeability, Cracki ng, Loss Monitoring 3.5.1-3 1 A PCEW- Below Grade (T-07)

(External) of Material (Spalling, Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-5 Concrete Water/Soil Permeability, Cracking, Loss Monitoring 3.5.1-31 A PCEW- Below Grade Support (T-07)

(External) of Material (Spalling, Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1 -32 A, 509 PC EW - Below Grade Support (T-02)

(External) Strength Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-7 Concrete Water/Soil Perme ability, Loss of Monitoring 3.5.1-32 A, 509 PC EW- Below Grade Support (T-02)

(External) Strength Program

SBK-L-17155 I Enclosure 2/ Page 165 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1; I II I T1 ' II' Ill ,, ' 1l'l,,,,1'.

1!1:1:1: , . ,*ii

' ,

' ,,, l'I ' I!'

,', ,, 11

' A ging I*' ji!I {j ; :1:l*l*l'i1*1 1:,

I' ,, NUREG '1:?B0111Fi ' 1:Table

'r:I ' ;:'I' 1

Intended , , 'I Ag1ryg 1 EffElc~ , Rrqu 1r,ir"1 g ,' :11 ,,,, ,1 ,,, "

Component Type Material Environment 1:1 'Management ** I' i:i_:r1*I '1 I i'I :*,**r1 :. 1'1'1 '3)<!:1,,:, {

1 1

1 111:, Note 1:1.1 ...1.Jl~?l.

,.. , , I " '1 ~

'~lm 1

Functi on Management111 :1 11 ,, '.*;I 1 .1,11,.1.:11 .*l:i 1 ,,:' ' 1tem ' ' I:

1

'1:1'1 1'1:,

1

,, 1:1' ::* ' ' Ii 11111

'*

Rrogram I ' , ,,

111' r*: 1'Ti*l*I .. l.,j .1'.1 '

Ground Structures PST - Reinforced Concrete - lll.A3-6 Flood Barrier Concrete Water/Soil Loss of Material, Cracking Monitoring 3.5.1 -26 A PCEW- Below Grade (T-0 1)

(External) Program Ground Structu res PST - Reinforced Concrete - Structural lll. A3-6 Concrete Water/Soil Loss of Material, Cracking Mo nitoring 3.5.1 -26 A PCEW- Below Grade Support (T-01 )

(External) Program PST - Reinforced Concrete - Air Indoor Fire Protection Vll. G-29 PCEW- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Loss of Material 3.3.1 -67 A Program (A-91 )

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor HELB Fire Protection Vll.G-2 9 PCEW- Exposed to Air Indoor Concrete Uncontrolled Loss of Material 3.3.1-67 A Shielding Program (A-91)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Fire Protection Vll. G-29 PCEW- Exposed to Air Indoor Shielding Concrete Uncontrolled Loss of Material 3.3.1-67 A Program (A-9 1)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Fire Protection Vll. G-29 PCEW- Exposed to A ir Indoor Concrete Uncontrolled Los s of Material 3.3.1-67 A Support Program (A-91)

Uncontrolled (External)

SBK-L-17155 I Enclosure 2/ Page 166 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation i:

l 'i Aging Table Intended Aging Effect Requiring NU REG 1801 Cornponent Type Material Environment Management 3.X.1 N o~e Function Management Vol. 2 Item Program Item 1:,

PST - Re inforced Concrete - Air Indoor Structures Cracking , Loss of Bond , Loss 111.A3-9 PCEW- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Monitoring 3.5. 1-23 A of Material (Spalling, Scaling) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Structures HELB Cracking, Loss of Bond , Loss lll.A3-9 PCEW- Exposed to Air Indoor Concrete Uncontrolled Monitoring 3.5. 1-23 A Shielding of Material (Spalling , Scaling) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Structures Cracking, Loss of Bond , Loss lll.A3-9 PCEW- Exposed to Air Indoor Shielding Concrete Uncontrolled Monitoring 3.5. 1-2 3 A of Material (Spalling , Sca ling) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Structures Structural Cracking , Loss of Bond , Loss lll.A3-9 PCEW- Exposed to Air Indoor Concrete Uncontrolled Monitoring 3.5. 1-23 A Support of Material (Spalling, Scaling) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Concrete Cracking and Fire Protection Vll.G-28 PCEW- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled 3.3. 1-65 A Spalling Program (A-90)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor HELB Concrete Cracking and Fire Protection Vll.G-2 8 PCEW- Exposed to Air Indoor Concrete Uncontrolled 3.3. 1-65 A Shielding Spalling Program (A-90)

Uncontro lled (External)

SBK-L-17155/Enclosure2/Page167 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

,.!: 1::

Intended Aging Effect Requiring Aging 1*11;1 NUREG 1801 Table ;i:!: 1::i:,

1 Component Type Mate'rial Environment Management 3.X.1 Note',:,,

Function Management Vol. 2 Item I*!;

Program Item PST - Reinforced Concrete - Air Indoor Concrete Cracking and Fire Protection Vll.G-28 PCEW- Exposed to Air Indoor Shielding Concrete Uncontrolled 3.3.1-65 A Spalling Program (A-90)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Concrete Cracking and Fire Protection Vll.G-28 PCEW- Exposed to Air Indoor Concrete Uncontrolled 3.3.1-65 A Support Spalling Program (A-90)

Uncontrolled (External)

Structures Monitoring Program Alkali-S ilica PST - Reinforced Concrete - Air Indoor Reaction (ASR) lll.A3-2 A, E, PCEW- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Expansion and Cracking Monitoring 3.5.1-27 (T-03) 517, 519 Uncontrolled (External) Program Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR)

HELB lll.A3-2 A, E, PCEW- Exposed to Air Indoor Concrete Uncontrolled Expansion and Cracking Monitoring 3.5.1-27 Shielding (T-03) 517, 519 Uncontrolled (External) Program Building Deformation Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 168 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 111' I ' ,!; ,I,,' :1 I* Aging 'Table Intended Aging Effect Requiring 111 NUREG 1801 Component Type Material Environment Management I 3.X.1 Note Function Management- * '

Vol. 2 Item I Pr~gram Item Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR) lll.A3-2 A , E, PCEW- Exposed to Air Indoor Shielding Concrete Uncontrolled Expansion and Crackin g Monitoring 3.5.1-27 (T-03) 517, 519 Uncontrolled (External) Program Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR)

Structu ral lll.A3-2 A, E, PCEW- Exposed to Air Indoor Concrete Uncontrolled Expansion and Cracking Monitoring 3.5.1 -27 Support (T-03) 517, 519 Uncontrolled (External) Prog ram Building Deformation Monitoring Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Stru ctures lll .A3-10 PCEW- Exposed to A ir Indoor Fire Barrier Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5.1-24 A (T-06)

Uncontrolled (External) of Material (Spalling , Scaling) Program PST - Re inforced Concrete - Air Indoor Increase in Porosity and Structures HELB lll.A3-10 PCEW- Exposed to Air Indoor Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5.1 -24 A Shielding (T-06)

Uncontrolled (External) of Material (Spalling, Scaling) Program

SBK-L-17155 I Enclosure 21 Page 169 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

1:

Aging Table 1:1 Intended Aging Effect Requ iring NU REG 1801 Component Type Material '

Environment Management 3.X. 1 Note "

Function

' I , :1:1:1.l!f!il; !l'it l![i ****. ~anagement

l!I , *, 11 * *1*1 I

,Program Vol. 2 Item I: Item PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures lll.A3-10 PCEW- Exposed to Air Indoor Shielding Concrete Uncontrolled Permeability, Cracking, Loss Monitoring 3.5.1-24 A (T-06)

Uncontrolled (External) of Material (Spalling , Scaling) Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures Structural lll.A3-10 PCEW- Exposed to Air Indoor Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5.1-24 A Support (T-06)

Uncontrolled (External) of Material (Spalling, Scaling) Program Structu res PST - Reinforced Concrete - Air Outdoor Cracking, Loss of Bond, Loss lll.A3-9 Missile Barrier Concrete Monitoring 3.5.1 -2 3 A PCEW- Exp osed to Air Outdoor (External) of Material (Spalling, Scaling) (T-04)

Program Structures PST - Reinforced Concrete - Shelter, Air Outdoor Cracking , Loss of Bond, Loss lll.A3-9 Concrete Monitoring 3.5.1 -2 3 A PCEW- Exposed to Air Outdoor Protection (External) of Material (Spall ing, Scaling) (T-04)

Program Structures Monitoring Program Alkali-S ilica Reaction (ASR)

PST - Reinforced Concrete - Air Outdoor lll.A3-2 A, E, Missile Barrier Concrete Expansion and Cracking Monitoring 3.5.1 -27 PCEW- Expo sed to Air Outdoor (External) (T-03) 517, 519 Program Building Deformation Monitoring Proaram

SBK-L-17155 I Enclosure 2/ Page 170 U.S. Nuclear Regulatory Commission Tabl e 3.5.2-5 Primary Stru ctures Summary of Aging Management Evaluation

'I Intended Aging Effect Requiring Ag'ing NUREG 1801 Table , 'Iii

,I:~ ,,

Component Type Material Environment Management 3.X. 1 Note i:

Function Management Vol. 2 Item Program Item *: '

Structures Monitoring Program Alkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Shelter, Air Outdoor lll.A3-2 A , E, Concrete Expansion and Cracking Monitoring 3.5.1-2(

PCEW- Exposed to Air Outdoor Protection (External) (T-03) 517, 519 Program Building Deformation Monitoring Proqram Increase in Porosity and Structu res PST - Reinforced Concrete - Air Outdoor lll.A3- 10 Missile Barrier Concrete Permeability, Cracking , Loss Monitoring 3.5.1-24 A PCEW- Exposed to Air Outdoor (External) (T-06) of Material (Spalling, Scaling) Program Increase in Porosity and Structures PST - Reinforced Concrete - Shelter, Air Outdoor lll.A3-10 Concrete Permeability, Cracking , Loss Monitoring 3.5.1 -24 A PCEW- Exposed to Air Outdoor Protection (External) (T-06) of Material (Spalling, Scaling) Program Structures PST - Reinforced Concrete - Air Outdoor lll.A3-6 Missile Barrier Concrete Loss of Material, Cracking Monitoring 3.5.1-26 A PCEW- Exposed to Air Outdoor (External) (T-01 )

Program Structures PST - Reinforced Concrete - Shelter, Air Outdoor lll.A3-6 Concrete Loss of Material, Cracking Mon itoring 3.5.1-26 A PCEW- Exposed to Air Outdoor Protection (External) (T-0 1)

Program

SBK-L- 17155 I Enclosure 2/ Page 171 U. S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

,,,,,, 1 11 ,::111, ' Aging Table Intended Aging Effe~t Req'uiring ,:,. NUREG 1801 Component Type Material Environment I!:* Management J;X.1 Note Function

'!:1 ,1111:,,11!:11m 1~,~ ~, ~~~;1 Pt , 11 , ,11 Pr9g,ram ,

Vol. 2 lfom 1,'"*: " , ".:!': l:!*l'i]JI 1;:11: 11 ., !tem.,

Structures PST - Reinforced Concrete - Structural Raw Water Crack ing, Loss of Bond, Loss lll. A3-4 Concrete Monitoring 3.5.1 -31 A , 512 PCEW- Exposed to Raw Water Support (External) of Materi al (Spalling, Scaling) (T-05)

Program Structures Monitoring Program Alkali-Silica Reaction (ASR)

A, 512, PST - Reinforced Concrete - Structural Raw Water Monitoring 111.A3-2 Concrete Expansion and Cracking 3.5.1 -27 E, 517, PCEW- Exposed to Raw Water Support (External) Program (T-03) 519 Building Deformation Monitoring Program Ground Structures PST - Reinforced Concrete - Cracking, Loss of Bond , Lo ss lll .A3-4 Flood Barrier Concrete Water/Soil Monitoring 3.5.1-31 A PHA- Below Grade of Materia l (Spalling, Scaling) (T-05)

(External) Program Ground Structures PST - Reinforced Concrete - Structural Cracki ng, Loss of Bond, Loss lll.A3-4 Concrete Water/Soil Monitoring 3.5.1-31 A PHA- Below Grade Support of Material (Spalling , Scaling) (T-05)

(Externa l) Program Structures Monitoring Program Ground PST - Reinforced Concrete - lll.A3-2 A, E, Flood Ba rrier Concrete Water/Soil Expansion and Cracking 3.5.1-27 PHA- Below Grade Alkali-Silica (T-03) 517, 5 19 (External)

Reaction (ASR)

Monitoring ProQram

SBK-L-17155 I Enclosure 2/ Page 172 U.S. Nuclear Regulatory Commission Tabl e 3.5.2-5 Primary Stru ctures Summary of Aging Management Evaluation i'

Aging Table :r Intended Aging Effect Requiring NU REG 1801 Component Type Material Environment. Management 3.X.1 Note Function Management Vol. 2 Item Program Item .

Building Deformation Monitoring Program Structures Monitoring Program Alkali-Si lica Ground Reaction (ASR)

PST - Re inforced Concrete - Structural lll.A3-2 A , E, Concrete Water/Soil Expa nsion and Cracking Monitoring 3.5.1 -27 PHA- Below Grade Support (T-03) 517 , 519 (External) Program Building Deformation Monitoring Proaram Ground Increase in Porosity and Structures PST - Reinforced Concrete - lll.A3-5 Flood Barrier Concrete Water/Soil Permeability, Cracking, Loss Monitorin g 3.5.1 -3 1 A PHA- Below Grade (T-07)

(External) of Material (Spalling , Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural 111.A3-5 Concrete Water/Soil Permeability, Cracking, Loss Monitoring 3.5.1-31 A PHA- Below Grade Support (T-07)

(External) of Material (Spalling , Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1 -32 A , 509 PHA- Below Grade Support (T-02)

(External) Strength Program

SBK-L-17155 I Enclosure 2/ Page 173 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

I : ' 1i:1: 1111N!l ' 11:1,1 1 : I I:' 1:1:1'11:1' I, !1 1;1 ,1:! Aging . 1,:11,,, ,1; I Table Intended Aging Effect Requiring NUREG .' 1801 Component Type Material Environment Management 3.X.1 Note Function Management Vol. 2 Item Program Item Ground Increase in Porosity and Structures PST - Re inforced Concrete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-32 A , 509 PHA- Below Grade Support (T-02)

(External) Strength Program Ground Structures PST - Reinforced Concrete - lll.A3-6 Flood Barrier Concrete Water/Soil Loss of Material, Cracking Monitoring 3.5.1-26 A PHA- Below Grade (T-01 ) .

(External) Program Ground Structures PST - Re inforced Concrete - Structural lll.A3-6 Concrete Water/Soil Loss of Material , Cracking Monitoring 3.5.1 -26 A PHA- Below Grade Support (T-0 1)

(External) Program PST - Reinforced Concrete - Air Indoor Fire Protection Vll.G -29 PHA- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Loss of Material 3.3.1-67 A Program (A-9 1)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structu ral Fire Protection Vll.G-2 9 PHA- Exposed to Air Indoor Concrete Uncontrolled Loss of Material 3.3.1-67 A Support Program (A-91 )

Uncontroll ed (External)

PST - Reinforced Concrete - Air Indoor Structures Cracking, Loss of Bond, Loss lll.A3-9 PHA- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Monitoring 3.5.1 -23 A of Material (Spalling, Scaling) (T-04)

Uncontrolled (External) Program

SBK-L-17155 I Enclosure 2/ Page 174 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluati on

, Agi~g Effect Requiring1, . J Ii! :1'l!F . i:q. ! Mdnagement 1 Table Comphnent Type Intended Material 1

I I iF *I*

' M

Aging t NUREG 1801

, 3.X.1 . Note I 'I Environmenr l 11 Progr~m ,

Function 1 il' 111 . . anagemen V ol. 2 Item 1,

1111 IJ l1',uf!f!l:l'l11:i:'l't:1111 ' 1,1:1:W':1:,,- , .,. , '!f!:l.1 I ,!I :1!!:*1 '1:i:* :1: :l:1!l*i: ,,,1,,!: '.. ,,,1, 1~e*1n 1 * '.i 'I' I* .,1,11 1 PST - Reinforced Concrete - Air Indoor Structures Structural Cracking, Loss of Bond, Loss 111.A3-9 PHA- Exposed to Air Indoor Concrete Unco ntrolled Monitoring 3.5 . 1-23 A Support of Material (Spalling, Scaling) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Concrete Cracking and Fire Protection Vll. G-28 PHA- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled 3.3. 1-65 A Spal ling Program (A-90)

Uncon trol led (External)

PST - Reinforced Concrete - Air Indoor Structural Concrete Cracking and Fire Protection Vll. G-28 PHA - Exposed to Air Indoor Concrete Uncontrolled 3.3. 1-65 A Support Spalling Program (A-90)

Uncontrolled (External)

Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR) lll.A3-2 A, E, PHA- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Expan sion and Cracking Mon itoring 3.5. 1-27 (T-03) 517, 519 Uncontrolled (External) Program Building Deformation Monitoring Proqram Structures Monitoring Program PST - Reinforced Concrete - Air Indoor Structural lll.A3-2 A, E, PHA- Exposed to Air Indoor Concrete Unco ntrolled Expansion and Cracking Al kali -Silica 3.5. 1-27 Support (T-03) 5 17, 519 Uncontrolled (External) Reaction (AS R)

Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 175 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1:1:' :111 ', 1111 .,11: Aging NUREG 1801 I

. g.*i~.: g Intended Table Component Type Material Environment ** :i!li A . f:iHect Requiring , , Management Vol. 2 Item 3.X.1 Note Function 1 I .I 'I' 'l'l'il: ,: Management .

1

.,

1*:: II :l:H:l1 <j11I: : *l:'":i: ' 'I 1 Program *i :i, 'I* , ,,,: 11 11j. ltem Building Deformation Monitoring Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures lll.A3-10 PHA- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Perm eability, Cracking, Loss Monitoring I 3.5.1-24 IA (T-06)

Uncontrolled (External) of Material (Spalling , Scaling) Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures PHA- Exposed to Air Indoor Structural Concrete Uncontrolled Permeability, Cracking, Loss Monitoring I lll .A3-10 I 3.5.1-24 IA Support (T-06)

Uncontrolled (External) of Material (Spalling, Scaling) Program Structures PST - Reinforced Concrete - Shelter, Air Outdoor Cracking, Loss of Bond, Loss 111.A3-9 PHA- Exposed to Air Outdoor Protection I Concrete (External) of Material (Spalling, Scaling)

Monitoring (T-04)

I 3.5 .1-23 IA Program Structures Monitoring Program Alkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Shelter, Air Outdoor 111.A3-2 A, E, PHA- Exposed to Air Outdoor Protection I Concrete (External)

I Expans ion and Cracking Monitoring (T-03) I 3.5 .1-27 517, 519 Program Building Deformation Monitoring Program

SBK-L- 171 55 I Enclosure 2/ Page 176 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluati on Intended

,1,

,

l:' Agingl:'I"Effect' Requi ri'ng

' 'i' ,,, ' 1:. ,,

1 Aging NUREG 1801 Table

,Management 1

' Component Type Material Environment 3.X. 1 Note '

Function Management Vol. 2 Item

! ' I ' ' Program Item Increase in Porosity and Structures PST - Re inforced Concrete - Shelter. Air Outdoor lll.A3-10 Concrete Permeability, Cracking, Loss Mon itoring 3.5.1-24 A PHA- Exposed to Air Outdoor Protection (External) (T-06) of Material (Spalling , Scaling) Program Structu res PST - Re inforced Concrete - Shelter, Air Outdoor lll.A3-6 Concrete Loss of Material, Cracking Monitoring 3.5. 1-26 A PHA- Exposed to Air Outdoor Protection (External) (T-0 1)

Program Ground Structures PST - Reinforced Concrete - Cracking , Loss of Bond , Loss lll.A3-4 Flood Barrier Concrete Water/Soil Mon itori ng 3.5.1 -31 A TFA- Below Grade of Material (Spalling , Scaling) (T-05)

(Externa l) Program Ground Structures PST - Reinforced Concrete - Structura l Cracking , Loss of Bond , Loss lll.A3-4 Concrete Water/Soil Monitoring 3.5.1 -3 1 A TFA- Below Grade Support of Material (Spalling , Scaling) (T-05)

(External) Program Structures Mon itoring Program Alkali-Silica Ground Reaction (ASR)

PST - Re inforced Concrete - lll.A3-2 A, E, Flood Barrier Con crete Water/Soil Expansion and Cracking Monitoring 3.5.1 -2 7 TFA- Below Grade (T-03) 517 , 519 (Externa l) Program Building Deformation Monitoring Proaram

SBK-L-17155 I Enclosure 2/ Page 177 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

1

'I Aging Table Intended Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X.1 Note Function Management Vol. 2 Item Program Item Structures Monitoring Program Alkali-Silica Ground Reaction (ASR)

PST - Reinforced Concrete - Structural lll. A3-2 A, E, Concrete Water/Soil Expansion and Cracking Monitoring 3.5.1-27 TFA- Below Grade Support (T-03) 517, 519 (External) Program Building Deformation Monitoring Proaram Ground Increase in Porosity and Structures PST - Reinforced Concrete - lll.A3-5 Flood Barrier Concrete Water/Soil Permeability, Cracking , Loss Monitoring 3.5.1-31 A TFA- Below Grade (T-07)

(External) of Material (Spalling , Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-5 Concrete Water/Soil Permeability, Cracking , Loss Monitoring 3.5.1-31 A TFA- Below Grade Support (T-07)

(External) of Material (Spalling, Scaling) Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-32 A, 509 TFA- Below Grade Support (T-02)

(External) Strength Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-32 A , 509 TFA- Below Grade Support (T-02)

(External) Strength Program

SBK-L-17 155 I Enclosure 2/ Page 178 U. S. Nuclear Regulatory Comm ission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluati on 111 + ,,*

~gih~;l: ~~~~~l~~~~ir;1 1ngii11.f: 11[:'.1 1:t!l,:1: :1,Manager:nrnt, t t I

~f~J:

A gi ng i; :1, Intended NUREG 180,11'n 1 Component Type :r* Material Environment ~ ote

'" ., 1",111Function 1,

' I Management

' *

,,, : 11 JI 11.1:'11.,, 11;i'l;,1

1 1 ,1.,1* Program 1

t1 ;111 '. v61.

, ,

1 1

.1 2 1 1t~r\1 1 1i1::1:1 1':;1i :\11.1, 1[ :1:... I Item 'l1,1 lij: 1*1 .'

' ,I.' I ::1*I; 'l l J1'1:1! l111111 *'*l:i!ll 1f:I::,,, '.:

1 1 Ground Structures PST - Reinforced Concrete - lll.A3-6 Flood Barrier Concrete Water/Soil Loss of Material , Cracking Monitoring 3.5 .1-26 A TFA- Below Grade (T-0 1)

(External) Program Ground Structures PST - Reinforced Concrete - Structural lll.A3-6 Concrete Water/Soil Loss of Material, Cracking Monitoring 3.5. 1-26 A TFA- Below Grade Support (T-0 1)

(External) Program PST - Reinforced Concrete - Air Indoor Fire Protection V ll.G-29 TFA- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Loss of Material 3.3. 1-67 A Program (A-9 1)

Uncontrol led (External)

PST - Reinforced Concrete - Air Indoor Fire Protection Vll. G-29 T FA- Exposed to Air Indoor Shielding Concrete Uncontrolled Loss of Material 3.3.1-67 A Program (A-9 1)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Fire Protection Vll. G-29 TFA- Exposed to Air Indoor Concrete Uncontrolled Loss of Material 3.3 .1-67 A Support Program (A-9 1)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structures Cracking, Loss of Bond, Loss lll.A3-9 TFA - Exposed to Ai r Indoor Fire Barrier Concrete Uncontrolled Monitoring 3.5. 1-2 3 A of Material (Spalling, Scaling) (T-04)

Uncontrolled (External) Program

SBK-L-17 1SS I Enclosure 2/ Page 179 U. S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Agi ng Management Evaluati on I i+i I 'I ' Aging Table Intended ' ,*11 ~ ging Effect ~equiring NU REG 1801 1lil,j1:jll*.::1:1; Component Type Material ' Environment Management 3. X.1 Function I, I I :I: l'l:!Jli;

,,

1 111 '

1

, M a~~gement

:':1:j:1 *l 111:l:,:i:p11fDitl ,11 *1111: ':11 'I' Prog ram Vol. 2 Item Item

'

PST - Reinforced Concrete - Air Indoor Structures Cracking , Loss of Bond , Loss lll.A3-9 TFA- Exposed to Ai r Indoor Shielding Concrete Uncontrolled Monitoring 3.5.1-23 A of Material (Spalling, Scaling) (T-04)

Uncontro lled (External) Program PST - Reinforced Concrete - Air Indoor Structures Structural Cracking , Loss of Bond , Loss lll.A3-9 TFA- Exposed to Ai r Indoor Concrete Uncontrolled Monitoring 3.5. 1-23 A Support of Material (Spalling, Scaling) (T-04)

Uncontrol led (External) Program PST - Reinforced Concrete - Air Indoor Concrete Cracking and Fire Protection Vll. G-28 TFA- Exposed to A ir Indoor Fire Barrier Concrete Uncontrolled 3.3 .1-65 A Spa Iling Program (A-90)

Uncontro lled (External)

PST - Re inforced Concrete - Air Indoor Concrete Cracking and Fire Protection Vll. G-28 TFA- Exposed to Air Indoor Shielding Concrete Uncontrolled 3.3. 1-65 A Spa Iling Program (A-90)

Uncontro lled (External)

PST - Re inforced Concrete - Air Indoor Structural Concrete Cracking and Fire Protecti on Vll. G-28 TFA- Exposed to Air Indoor Concrete Uncontrolled 3.3.1 -65 A Support Spalling Program (A-90)

Uncontrolled (External)

Structures Monitoring Program PST - Reinforced Concrete - Air Indoor Al kali-Silica lll. A3-2 A , E, TFA- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Expansion and Cracking 3.5.1-27 Reaction (ASR) (T-03) 517, 519 Uncontrolled (External)

Mon itori ng Program Building

SBK-L- 17155 I Enclosure 2/ Page 180 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

!.t I H ,, Aging T~ble Intended Aging Effect,Requiri pg NU REG 1801 Component Type Material Environment Management 3.X. 1 Note Function Management Vol. 2 Item Program ,,, Item Deformation Monitoring Program Structu res Monitoring Program Alkali-Silica PST - Re inforced Concrete - Air Indoor Reaction (ASR) lll.A3-2 A, E, TFA- Exposed to Air Indoor Shielding Concrete Uncontrolled Expan sion and Cracking Monitoring 3.5.1-27 (T-03) 517, 519 Uncontrolled (External) Program Building Deformation Monitoring Proaram Structures Mon itoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR)

Structural lll.A3-2 A, E, TFA- Exposed to Air Indoor Concrete Uncontrolled Expa nsion and Cracking Monitori ng 3.5.1 -27 Support (T-0 3) 517, 519 Uncontrolled (External) Program Building Deformation Monitoring Proqram PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures lll.A3-10 TFA- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5. 1-24 A (T-06)

Uncontrolled (External) of Material (Spalling , Scaling) Program

SBK-L-171 55 I Enclosure 2/ Page 181 U.S . Nuclear Regulatory Commission Tabl e 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

,,,

'

II Aging Table Intended 1:! Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X.1 Note Function Management Vol. 2 Item Prog ram Item PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures lll.A3-10 TFA- Exposed to Air Indoor Shielding Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5.1 -24 A (T-06)

Uncontro lled (External) of Material (Spalling , Scaling) Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures Structural 111 .A3- 10 TFA- Exposed to Air Indoor Concrete Uncontrolled Permeabil ity, Cracking , Loss Monitoring 3.5.1-24 A Support (T-06)

Uncontrolled (External) of Material (Spalling , Scaling) Program Structures PST - Re inforced Concrete - Air Outdoor Cracking, Loss of Bond , Loss lll.A3-9 Missi le Ba rrier Concrete Monitoring 3.5.1-23 A TFA- Exposed to Air Outdoor (External) of Material (Spalling , Scaling) (T-04)

Program Structures PST - Re inforced Concrete - Shelter, Air Outdoor Cracking, Loss of Bond , Loss lll.A3-9 Concrete Mon itoring 3.5.1 -23 A TFA- Exposed to Air Outdoor Protection (External) of Material (Spalling, Scaling) (T-04)

Program

.

Structures PST - Reinforced Concrete - Air Outdoor lll.A3-2 Missile Barrier Concrete Expansion and Cracking Monitoring 3.5.1-27 A TFA- Exposed to Air Outdoor (External) (T-03)

Program Structures Mon itoring Program PST - Re inforced Concrete - Shelter, Air Outdoor Alkali-Silica ll l.A3-2 A, E, Concrete Expan si on and Cracking 3.5.1-27 TFA- Exposed to Air Outdoor Protection (External) Reaction (ASR) (T-03) 517, 519 Monitoring Program Building

SBK-L- 171 55 I Enclosure 2/ Page 182 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation II ' I*; 1::1:.i:* "' :[:i: IJ'* 111 n1>r"1*, 111:,j1: 1~g ,*q g,"~1* 1:1,l'I ' II'* 11] 1!*:,frl ,. ::I 'l' 1

1 ll ' *

1'r TableI !"'*

1

k Intended Aging Effect Requ iri ng , , NU REC?;,1,so1 1 1 1

Management i*ll ' 3.X. 1 *

,

Component Type Material Environment Note Function Management 111N ol. 2' Item Program Item Deformation Monitoring Program Increase in Porosity and Structures PST - Reinforced Concrete - Air Outdoor lll.A3-10 Missile Barrier Concrete Permeability, Cracking , Loss Mon ito ring 3.5. 1-24 A TFA- Exp osed to Air Outdoor (External) (T-06) of Material (Spalling , Scaling) Program Increase in Porosity and Structures PST - Reinforced Concrete - Shelter, Air Outdoor lll.A3-10 Concrete Permeability, Cracking , Loss Monitoring 3.5 .1-24 A TFA- Exp osed to Air Outdoor Protection (External) (T-06) of Material (Spalling , Scaling) Program Structures PST - Reinforced Concrete - Air Outdoor lll. A3-6 Missile Barrier Concrete Loss of Material , Cracking Monitorin g 3. 5.1-26 A TFA- Exposed to Ai r Outdoor (External) (T-0 1)

Prog ram Structures PST - Re info rced Concrete - Shelter, Air Outdoor lll .A3-6 Concrete Loss of Material , Cracki ng Monitoring 3.5.1 -26 A TFA- Exposed to Ai r Outdoor Protection (External) (T-0 1)

Program Ground Structures PST - Re inforced Concrete - Cracking, Loss of Bond , Loss lll.A3-4 Flood Barrier Concrete Water/Soil Monitori ng 3.5 .1-3 1 A WPB- Below Grade of Material (Spalling , Scaling) (T-05)

(External) Program

SBK-L-17155 I Enclosure 2/ Page 183 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Stru ctures Summary of Aging Management Evaluation

I

1: T Aging Table Intended Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X.1 Note Function Management Vol. 2 Item Program Item Ground Structures PST - Reinforced Concrete - Structural Cracking, Loss of Bond, Loss lll.A3-4 Concrete Water/Soil Monitoring 3.5.1-31 A WPB- Below Grade Support of Material (Spalling, Scaling) (T-05)

(External) Program Structures Monitoring Program Alkali-Silica Ground Reaction (ASR)

PST - Reinforced Concrete - lll.A3-2 A , E, Flood Barrier Concrete Water/Soil Expan sion and Cracking Monitoring 3.5.1 -27 WPB- Below Grade (T-03) 517, 519 (External) Program Building Deformation Monitoring Proa ram Structures Monitoring Program Alkali-Silica Ground Reaction (ASR)

PST - Reinforced Concrete - Structural lll.A3-2 A , E, Concrete Water/Soil Expansion and Cracking Monitoring 3.5.1-27 WPB- Below Grade Support (T-03) 517 , 519 (External) Program Building Deformation Monitoring Proaram Ground Increase in Porosity and Structures PST - Reinforced Concrete - lll.A3-5 Flood Barrier Concrete Water/Soil Permeability, Cracking, Loss Monitoring 3.5.1-31 A WPB- Below Grade (T-07)

(External) of Material (Spalling, Scaling) Program

SBK-L-17155 I Enclosure 2/ Page 184 U. S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

,, , 'l 'I'll:( i' : 1 ,,, ::IJ, fr,j:I ,,, , ITable ,

Aging Effect Requiring 11 ' ,,, Agir;ig Intended *NU REG 1,801 Component Type Function Material Environment

' ll Mana,gemen.t 1 Management Vol. 2 Item ix.1 Note

1 ,,,, Program '1;:;, , Item Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll. A3-5 Concrete Water/Soil Permeability, Cracking , Loss Monitoring 3.5.1 -31 A WPS- Below Grade Support (T-07)

(External) of Material (Spalling , Scaling) Program Ground In crease in Porosity and Structures PST - Reinforced Con crete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-32 A , 509 WPS- Below Grade Support (T-02)

(External) Strength Program Ground Increase in Porosity and Structures PST - Reinforced Concrete - Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-32 A , 509 WPB- Below Grade Support (T-02)

(External) Strength Program Ground Structures PST - Reinforced Concrete - lll.A3-6 Flood Barrier Concrete Water/Soil Loss of Material, Cracking Monitoring 3.5.1 -26 A WPS- Below Grade (T-01)

(External) Program Ground Structures PST - Re inforced Concrete - Structural 111.A3-6 Concrete Water/Soil Loss of Material , Cracking Monitoring 3.5.1 -26 A WPS- Below Grade Support (T-01 )

(External) Program PST - Reinforced Concrete - Air Indoor Fire Protection Vll.G-29 WPS- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Loss of Material 3.3 .1-67 A Program (A-91 )

Uncontrolled (External)

SBK-L-17155 I Enclosure 2/ Page 185 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

' ' Aging Table Intended ' Aging Effect Requiring NUREG 1801 Component Type Material Environment 1: Management 3.X~ 1 Note Function 1* Management Vol. 2 Item 1 Program 1tem PST - Reinforced Concrete - Air Indoor Fire Protection Vll.G-29 WPB- Exposed to Air Indoor Shielding Concrete Uncontrolled Loss of Material 3.3.1-67 A Program (A-91)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Fire Protection Vll.G-29 WPB- Exposed to Air Indoor Concrete Uncontrolled Loss of Material 3.3.1-67 A Support Program (A-91)

Uncontrolled (Extern al)

PST - Reinforced Concrete - Air Indoor Structures Cracking , Loss of Bond, Loss ll l.A3-9 WPB- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Monitoring 3.5.1-23 A of Material (Spalling , Sca ling) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Structures Cracking, Loss of Bond, Loss lll.A3-9 WPB- Exposed to Air Indoor Shielding Concrete Uncontrolled Monitoring 3.5.1-23 A of Material (Spalling, Scaling) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Structures Structural Cracking, Loss of Bond, Loss lll.A3-9 WPB- Exposed to Air Indoor Concrete Uncontrolled Monitoring 3.5 .1-23 A Support of Material (Spalling , Scaling) (T-04)

Uncontrolled (External) Program PST - Reinforced Concrete - Air Indoor Concrete Cracking and Fire Protection Vll.G-28 WPB- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled 3.3.1-65 A Spalling Program (A-90)

Uncontrolled (External)

SBK-L- 171 55 I Enclosure 2/ Page 186 U. S. Nuclear Regulatory Commi ssion Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

' ' Intended Agmg Effect ~equm~g , 1 1il1 l%:.A~i,rig , i1'!11i*1 I ~,UREGi11 ~0,1 11111:,,111 qi, ,1111 it.l, .11'111111111 11111 1-lillllillllll"llllli llr 11*1 1lirab11e /1 Component Type " Material Environment

Management '

1 3 x* ~111111 I I" 1[:1i

.*, 1. Note Function'!'

" :1:

Management

. ' Program 1

y o1.l 2 1tem t

Item ' 111,1_ !], .. 'I' PST - Reinforced Concrete - Air Indoor Concrete Cracking and Fire Protection Vll.G-28 WPS- Exposed to Air Indoor Shielding Concrete Uncontrolled 3.3.1-65 A Spalling Program (A-90)

Uncontrolled (External)

PST - Reinforced Concrete - Air Indoor Structural Concrete Cracking and Fire Protection Vll.G-28 WPS- Exposed to Air Indoor Concrete Uncontrolled 3.3.1-65 A Support Spalling Program (A-90)

Uncontrolled (External)

Structures Monitoring Program Alkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Air Indoor Monitoring lll.A3-2 A, E, WPS- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Expansion and Cracking 3.5.1 -27 Program (T-03) 517, 519 Uncontrolled (External)

Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica PST - Reinforced Concrete - Air Indoor Reaction (ASR) lll.A3-2 A, E, WPS- Exposed to Air Indoor Shielding Concrete Uncontrolled Expansion and Cracking Monitoring 3.5.1-27 (T-03) 517, 519 Uncontrolled (External) Program Building Deformation Monitoring Proqram

SBK-L-17155 I Enclosure 2/ Page 187 U. S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Ag ing Management Evaluation

+ . :1: 1: I1 ~ ! 1

, ln 1

illi" ~gii,l g' Etfe6i' ~~~ ui* r* i* n '9'.*.." .. '.' I I'. .I j' ,I" I I ' ' ': I 3 *1x ' 1' ' 1*;'.i' *:: r:. Note Intended Aging . NURE . G '

1 801-,' : :1Table

'1

, . i ~a'.~ag~~~nt ,1'1!1;:11 {Ir Environment ,.,

Component Type Function Material ')'

l::.1

'l*I*.* M

.. I.a nager:nent1ll'i,

'.,,,

. I

'"'.l*l \~ . 1 1 2

... '

0 'I'

. '1:1'1 'I'll Item *I.Ii :1 I. lte' m :1* 11i:"* \ 1*l"!l,1i:". . ' ,

1::. ::* *'1.:.' Prog ram I*):'.**} , 1 I

I

'" 1:1**1::

I *1*1*1*

'.,'1" 111 i !,,*11* '-!- ,,,,,,11111 "' I* ,

. '::.

.1 1 ... 1 Structures Monitoring Program Alkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Air Indoor Structural Monitoring lll.A3-2 A, E, WPS- Exposed to Air Indoor Concrete Uncontrolled Expansion and Cracking 3.5.1-27 Support Program (T-03) 517, 519 Uncontrolled (External)

Building Deformation Monitoring Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures lll.A3-10 WPS- Exposed to Air Indoor Fire Barrier Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5.1 -24 A (T-06)

Uncontrolled (External) of Material (Spalling, Scaling) Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures lll .A3-10 WPS- Exposed to Air Indoor Shielding Concrete Uncontrolled Permeability, Cracking, Loss Monitoring 3.5.1 -24 A (T-06)

Uncontrolled (External) of Material (Spalling , Scaling) Program PST - Reinforced Concrete - Air Indoor Increase in Porosity and Structures Structural lll.A3-10 WPS- Exposed to Air Indoor Concrete Uncontrol led Permeability, Cracking , Loss Monitoring 3.5. 1-24 A Support (T-06)

Uncontrolled (External) of Material (Spalling, Scaling) Program Structures PST - Reinforced Concrete -

I Missile Barrier I Concrete I Air Outdoor I Cracking, Loss of Bond, Loss Monitoring lll.A3-9 3.5.1-23 A WPS- Exposed to Air Outdoor (External) of Material (Spalling, Scaling) (T-04)

Program

SBK-L-17155 I Enclosure 2/ Page 188 U. S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

I Intended

,;1 IH' :;* Aging Effect Requiring

'

1

*' Aging 'l ;1:

'

NUREG 1801

' Table 'y, i'I, li' .

, *!::t1!1:

Component Typ,e Material Environment Management 3.X. 1 Note' .i 11:il:f':II!

Function ' Management Vol. 2 Item l'i'

\l 111 Program Item '

1:1:1 Structures PST - Reinforced Concrete - Shelter, Air Outdoor Cracking, Loss of Bond , Loss lll.A3-9 Concrete Monitoring 3.5.1-23 A WPS- Exposed to Air Outdoor Protection (External) of Material (Spalling, Scaling) (T-04)

Program Structures Monitoring Program Alkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Air Outdoor 111.A3-2 A, E, Missile Barrier Concrete Expansion and Cracking Monitoring 3.5.1-27 WPS- Exposed to Air Outdoor (External) (T-03) 517, 519 Program Building Deformation Monitoring Proaram Structures Monitoring Program Alkali-Silica Reaction (ASR)

PST - Reinforced Concrete - Shelter, Air Outdoor lll.A3-2 A, E, Concrete Expansion and Cracking Monitoring 3.5.1-27 WPS- Exposed to Air Outdoor Protection (External) (T-03) 517, 519 Program Building Deformation Monitoring Program Increase in Porosity and Structures PST - Reinforced Concrete - Air Outdoor lll. A3-10 Missile Barrier Con crete Permeability, Cracking , Loss Monitoring 3.5.1 -24 A WPS- Exposed to Air Outdoor (External) (T-06) of Materi al (Spalling, Scal ing) Program

SBK-L-17155 I Enclosure 2/ Page 189 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Stru ctures Summary of Aging Management Evaluation

'1:1,l:J:,. '. 111:1 Agi~gl'I, II l'I *. *l.1

,. *intended *:* NUREG 11ao1 * .** Tabre . 1:::1.r~***1*i,h,_:

Aging Effect Requiring Component Type Material

,,

Environment Management Management Vol. 2 Item 3.X. 1 Note I(

Fu nction 1"

1:1

.

Program Item I

.*

Increase in Porosity and Structures PST - Reinforced Concrete - Shelter, Air Outdoor lll.A3- 10 Concrete Permeability, Cracking, Loss Monitoring 3.5 .1-24 A WPB- Exposed to Air Outdoor Protection (External) (T-06) of Material (Spalling , Scaling) Program Structures PST - Reinforced Concrete - Air Outdoor lll.A3-6 Missile Barrier Concrete Loss of Material , Cracking Monitoring 3.5.1-26 A WPB- Exposed to Air Outdoor (External) (T-01)

Program Structures PST - Reinforced Concrete - Shelter, Air Outdoor lll.A3-6 Concrete Loss of Material, Cracking Monitoring 3.5.1-26 A WPB- Exposed to Air Outdoor Protection (External) (T-0 1)

Program Nooe PST - Stainless Steel -COG- Air Indoor Nooe Building Structural Stainless 111. 82-8 Exposed to Air Indoor Uncontrolled Deformation/reduction in Deformation 3.5.1-59 C, E, 520 Support Steel (TP-5)

Uncontrolled (External) structural capacity Monitoring Program Structures PST - Stainless Steel -COG- Shelter, Stainless Raw Water Vll.H2-18 Loss of Material Monitoring 3.3.1-80 E, 512 Exposed to Raw Water Protection Steel (External) (Ap-55)

Program Structures PST - Stainless Steel -CEHMS- Structural Stainless Air Outdoor 111. 82-7 Exposed to Air Outdoor Support Steel (External)

Loss of Material Monitoring (TP-6) 3.5.1-50 c Program

SBK-L-17155 I Enclosure 2/ Page 190 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1

!.j !*1:1 'l:I h 1.l,:1*1 :1:1 I' ,,

Aging 'i::' Table

,; ::':

Intended Aging Effect Requiring NUREG 1801 Component Type Material Environment ,Managemept 1 11 3.X.1 Note Function Management ' Vol. 2 1tem Program lt!'!m Nooe PST - Stainless Steel -FSB- Air Indoor Nooe Building Structural Stainless lll.B2-8 Exposed to Air Indoor Uncontrolled Deformation/reduction in Deformation 3.5.1-59 C, E, 520 Support Steel (TP-5)

Uncontrolled (External} structural capacity Monitoring Program Structures PST - Stainless Steel -FSB- Shelter, Stainless Raw Water Vll.H2-18 Loss of Material Monitoring 3.3 .1-80 E, 512 Exposed to Raw Water Protection Steel (External) (Ap-55)

Program PST - Stainless Steel -FSB-Shelter, Stainless Treated Borated Water Chemistry lll.A5-13 A, Exposed to Treated Borated Cracking 3.5.1-46 Protection Steel Water (External) Program (T-14) 507 ,518 Water PST - Stainless Steel -FSB-Shelter, Stainless Treated Borated Water Chemistry 111.A5-13 Exposed to Treated Borated Loss of Material 3.5.1-46 A,518 Protection Steel Water (External) Program (T-14)

Water Nooe PST - Stainless Steel -FSB- Air w/Borated Nooe Building Structural Stainless lll.B2-9 Fuel Transfer Tube in Air with Water Leakage Deformation/reduction in Deformation 3.5.1-59 A, E, 520 Support Steel (TP-5)

Borated Water Leakage (External) s tructural capacity Monitoring Program Nooe PST - Stainless Steel -FSB- Air Indoor Nooe Building Structural Stainless lll.B2-8 Fuel Transfer Tube in Air Indoor Uncontrolled Deformation/reduction in Deformation 3.5.1-59 C, E, 520 Support Steel (TP-5)

Uncontrolled (External) s tructural capacity Monitoring Program

SBK-L-171 55 /Enclosure 2/Page 191 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Pri mary St ructures Summary of Aging Management Ev aluati o n 11 1 1 , ,1'j:'W':1:111'i'k ; lll1Tab i1~ ,'i,l'i Intended,.,

1, 1Jff '1' 'l'i '1 , 1" ' 11" .

, Aging Effect ~equ 1 ri r g

,"'

It '\ 1:i:~,g ing 1 , 11:1 11:1 NU REG:,1so1 nr' 11: ~,ar agem, ~ nt

111 , Vo J.', 2 1tMm1'"1 :( 3:X_,~ 1,1 :1: Note Component Type Environment :i:I 111 l'I Mat eria l

Management: 1.,li

item 11 i' V

,Fu ncti on ,, 1

,

,.,,1,, ,,,,

'I I 1: 1 '

1

. , Prog ram IJ11111 '1111:! ' , , "'1 ' Hii:

Nooe Air w/Borated Nooe Building PST - Stainless Steel -FSB- in Structura l Stainless lll. B2-9 Water Leakage Deformation/reduction in Deform ation 3.5. 1-5 9 A, E, 520 A ir with Borated W ater Leakage Support Steel (TP-5)

(External) s truc tural capacity Monitoring Program Nooe PST - Stainless Steel -PAB- Air Indoor Nooe Building Structural Stainless lll. B2-8 Exposed to Air Indoor Uncontrolled Deformation/reduction in Deformation 3.5.1-59 C, E, 520 Support Steel (TP-5)

Uncontrolled (External) s tructural capacity Monitoring Program Structures PST - Stainless Steel -PAB- Shelter, Stainless Raw Water Vl l. H2-18 Loss of Material Monitori ng 3.3. 1-80 E, 512 Exposed to Raw W ater Protection Steel (External) (Ap-55)

Program Nooe Air w/Borated Nooe Building PST - Stainless Steel -PAB- in Structural Stainless lll .B2-9 Water Leakage Deforma tion/reduc tion in Deformation 3.5. 1-59 A , E, 520 A ir with Borated W ater Leakage Support Steel (TP-5)

(External) s truc tural capacity Monitoring Program Nooe PST - Stainless Steel -WPB- Air Indoor Nooe Building Structural Stainless lll. B2-8 Exposed to Air Indoor Uncontrolled Deformation/reduc tion in Deformation 3.5. 1-59 C , E, 520 Support Steel (TP-5)

Uncontro lled (External) s tructural capacity Monitoring Program Structu res PST - Stainless Steel -WPB- Shelter, Stainless Raw Water Vll.H 2-18 Loss of Material Monitoring 3.3 .1-80 E, 512 Exposed to Raw W ater Protection Steel (External) (Ap-55 )

Prog ram

SBK-L- 17 155 I Enclosure 2/ Page 192 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

'I:

Aging

1 *' '

Table Intended Aging Effect Requidng NUREG 1801 Component Type Material Environment Management 3.X.1 Note Function Management Vol. 2 Item Program Item NeRe Air w/Borated NeRe Building PST - Stainless Steel -WPB- in Structural Stainless lll.B2-9 Water Leakage Deformation/reduction in Deformation 3.5.1-59 A, E, 520 Air w ith Borated Water Leakage Support Steel (TP-5)

(External) structural capacity Monitoring Program PST - Tech Spec CEVA Seal - Structural Air Indoor Increased Hardness, Structures Vll.G-1 EFP- Exposed to Air Indoor Pressure Elastomer Uncontrolled Shrinkage and Loss of Monitoring 3.3.1-61 E, 515 (A-19)

Uncontrolled Barrier (External) Strength Program Structural Increased Hardness, Structures PST - Tech Spec CEVA Seal - Air Outdoor Vll.G-2 Pressure Elastomer Shrinkage and Loss of Monitoring 3.3.1-61 E, 515 EFP- Exposed to Air Outdoor (External) (A-20)

Barrier Strength Program PST - Tech Spec CEVA Seal - Structural Air Indoor Increased Hardness, Structures V ll.G-1 FSB- Exposed to Air Indoor Pressure Elastomer Uncontrolled Shrinkage and Loss of Monitoring 3.3.1-61 E, 515 (A-19)

Uncontrolled Barrier (External) Strength Program PST - Tech Spec CEVA Seal - Structural Air Indoor Increased Hardness, Structures Vll.G-1 PAB- Exposed to Air Indoor Pressure Elastomer Uncontrolled Shrinkage and Loss of Monitoring 3.3. 1-61 E, 515 (A-19)

Uncontrolled Barrier (External) Strength Program Structural Increased Hardness, Structures PST - Tech Spec CEVA Seal - Air Outdoor Vll.G-2 Pressure Elastomer Shrinkage and Loss of Monitoring 3.3.1-61 E, 515 PAB- Exposed to Air Outdoor (External) (A-20)

Barrier Strength Program

SBK-L-17155 I Enclosure 2/ Page 193 U. S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Stru ctures Summary of Aging Management Evaluation

' Aging Table Intended

Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X. 1 Note '

Function Management Vo l. 2 Item Program Item PST - Tech Spec CEVA Seal - Structural Air Indoor Increased Hardness, Structures Vll.G-1 PCEW- Exposed to Air Indoor Pressure Elastomer Uncontrolled Shrinkag e and Loss of Monitoring 3.3. 1-61 E, 515 (A-19)

Uncontrolled Barrier (External) Strength Program Structural Increased Hardness, Structures PST - Tech Spec CEVA Seal - Air Outdoor Vll.G-2 Pressure Elastomer Shrin kage and Loss of Monitoring 3.3. 1-61 E, 515 PCEW- Exposed to Air Outdoor (Externa l) (A-20)

Barrier Strength Program PST - Tech Spec Control Room Air Indoor Increased Hardness, Structures Control Bldg Vll.G-1 Seal -CDG- Exposed to Air Elastomer Uncontrolled Shrinkage and Loss of Monitoring 3.3.1-61 E, 515 Habitability (A-19)

Indoor Uncontrolled (External) Stre ngth Program PST - Tech Spec Fuel Storage Structural Air Indoor Increased Hardness, Structures Vll.G-1 Building Seal -FSB- Exposed to Pressure Elastome r Uncontrolled Shrinkage and Loss of Monitoring 3.3. 1-61 E, 515 (A-19)

Air Indoor Uncontrolled Barrier (External) Strength Program PST - Thermal Insulation Air w/Borated Structural Boric Acid lll. B2-6 A luminum Jacketing -FSB- in Air Aluminum Water Leakage Loss of Material 3.5. 1-55 A Support Program (TP-3) with Borated Water Leakage (External)

PST - Thermal Insulation Air w/Borated Structural Boric Acid lll. B2-6 Aluminum Jacketing -PAB- in Aluminum Water Leakage Loss of Material 3.5.1-55 A Support Program (TP-3)

Air with Borated Water Leakage (External)

SBK-L-17155 I Enclosure 2/ Page 194 U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation

I* ,1,,1, ,1 Aging

Table.

intended

Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X.1 Note Function Management Vol. 2 Item Program . Item PST - Thermal Insulation Air w/Borated Structural Boric Acid lll .B2-6 Aluminum Jacketing -TFA- in Air Aluminum Water Leakage Loss of Material 3.5.1-55 A Support Program (TP-3) with Borated Water Leakage (External)

PST - Thermal Insulation Air w/Borated Structural Boric Acid lll.B2-6 Aluminum Jacketing -WPB- in Aluminum W ater Leakage Loss of Material 3.5.1-55 A Support Program (TP-3)

Air with Borated Water Leakage (External)

SBK-L-171 SS I Enclosure 2/ Page 19S U.S. Nuclear Regulatory Commission Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Standard Notes Note Description A Consistent with NUREG-1801 item for component, material , environment, and aging effect. AMP is consistent with NUREG-1801 AMP.

B Consistent with NUREG-1801 item for component, material , environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.

C Component is different, but consistent with NUREG-1801 item for material , environment, and aging effect. AMP is cons istent with NUREG-1801 AMP.

D Component is different, but consistent with NUREG-1801 item for material , environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.

E Consistent with NUREG-18 01 for material , environment and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program .

F Material not in NUREG-1801 for this component.

G Environment not in NUREG-1801 for this component and material.

H Aging effect not in NUREG-1801 for this component, material and environment combination.

Aging effect in NUREG-1801 for this component, material and environment combination is not applicable.

J Neither the component nor the material and environment combination is evaluated in NUREG-1801.

501 Not used.

502 Aging effect includes "Fretting or Lockup" due to wear.

503 Crevice and pitting will be included along with loss of material-corrosion due to a saltwater atmosphere environment.

504 Fatigue analysis exists and TLAA applies.

505 Built-up roofing is not in GALL; lll.A6-12 is for elastomer-material is similar, aging effect is similar, environment is same, and AMP is Structures Monitoring.

506 Component is cementitious fire proofing/insulating material and will exhibit similar aging effects as concrete.

507 Spent Fuel Pool temperature< 60°C (<140° F); water chemistry and temperature will be maintained by the Water Chemistry Program.

508 Cracking, loss of bond , and loss of material (spalling, scaling)/corrosion of embedded steel-is not listed in GALL 111.A.6 as an aging effect for concrete in raw water.

Seabrook manages this effect with Structures Monitoring Program.

509 For aging management purposes , buried , below grade , soil , and ground water/ raw & treated water environments are treated the same.

51 O Reduction in concrete anchor capacity is an aging effect that is addressed in LRAM-SUPT.

511 At Seabrook Station , Xl.S7 "RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" and XI.SS "Masonry Wall Program" are combined under Xl. S6 "Stru ctures Monitoring Program".

512 Raw water in lined & unlined concrete sumps.

513 Seabrook Station will age manage this condition through the Fire Protection Program.

514 Seabrook Station will age manage this condition through the Structures Mon itoring Program.

515 Increased hardness, shrinkage, or loss of strength of elastomer seals due to weathering is addressed by GALL only for Fire Barrier seals. Seabrook Station will manage such aging effects for non-Fire Barrier elastomer seals with the Structures Monitoring Program.

SBK-L-17155 I Enclosure 2/ Page 196 U.S. Nuclear Regulatory Commission 516 Seabrook Station Structures Monitoring Program will perform concrete testing and rebar inspection to determine the effects of the aggressive groundwater on the concrete. The concrete testing and the rebar inspection will represent all concrete below grade.

517 After initial iden tification and determination of the presence of alkali-silica reactivity by th e Structures Monitoring Program, Seabrook Station will age manage this condition through the Alkali-Silica Reaction (ASR) Monitoring Program.

518 For this component, material , environment, and aging effect, aging management by the Water Chemistry Program is augmented by monitoring of spent fuel pool water level and leakage from the leak chase channels.

519 After initial identification of alkali-silica reaction (ASR) induced building deformation by the Structures Monitoring Program, Seabrook Station will age manage this condition through th e Alkali-Silica Reaction (ASR) Monitoring Program and the Building Deformation Monitoring Program.

520 After initial identification of alkali-silica reaction (ASR) induced building deformation affecting plant equipment and components by the Structures Monitoring Program, Seabrook Station will age manage this conditi on through th e Building Deformation Monitoring Program.

SBK-L-17155 I Enclosure 2/ Page 197 U.S. Nuclear Regulatory Commission Table 3.5.2-6 Supports Summary of Aging Management Evaluation 11~1 Intended Aging 'E ffect Requiring Aging .. NUREG I Table Component Type Material Environment Management , 1801 ~ol. 2

3.X.1 Note Function Management Program Item Item ASME Class 1 - Constant &

Air Indoor ASME Section Variable Load Spring Hangers - Structural 111.81 .1-2 Steel Uncontrolled Loss of Mechanical Function XI, Subsection 3.5.1-54 A Exposed to Air Indoor Support (T-28)

(External) IWF Program Uncontrolled ASME Class 1 - Constant &

Air w/Borated Boric Acid Variable Load Spring Hangers - Structural 111.81 .1-14 Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A in Air with Borated Water Support (T-25)

(External) Program Leakage ASME Class 1 - Lubrite - Air Indoor ASME Section Structural 111.81 .1 -5 Exposed to Air Indoor Lubrite Uncontrolled Loss of Mechanical Function XI,, Subsection 3.5.1-56 A Support (T-32)

Uncontrolled (External) IWF Program Structures Monitoring ASME Class 1 - Pipe Supports - Air Indoor Program, Alkali-Structural Reduction in Concrete Anchor 111.81 .1-1 Concrete -Exposed to Air Indoor Concrete Uncontrolled Silica Reaction 3.5.1-40 A, E, 517 Support Capacity (T-29)

Uncontrolled (External) (ASR)

Monitoring Program Nooe Structures Monitoring ASME Class 1 - Stainless Steel Air Indoor Nooe Structural Stainless Program, 111.81 .1-9

- Exposed to Air Indoor Uncontrolled Deformation/reduction in 3.5.1-59 A, E, 520 Support Steel Building (TP-5)

Uncontrolled (External) s tructural capacity Deformation Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 198 U. S. Nuclear Regulatory Commission Table 3.5.2-6 Supports Summary of Aging Management Evaluat ion 1 1 1 t ent.ed d 1 1: . f:I 1

/ 1

. A . . Eff t R .. Aging

NU REG Table Component Type Fn Material Environ ment:! 11il 1 ,il' gingM. ec equtm ng Management 1801 Vo l. *2 .3.X. 1 Note unc ion 1 :i ,

,.. I ,.,iii iJil!, *1*.... anagemen

. I'* ..:1:11* ,1.1, I * .i 1., *, T. * ,

', :1:.1,,l,1 p.r ogram .

. 111,, . ,* 1,!.;,t.e(Tl

. ,,:: 1:' i:*1: <<"'It

.I. 11 I * .. , ,I, em

,, Id

'I' Nooe Structures

. . Monitoring ASME Class 1 - Stam less Steel St t 1 St . 1 Air w/Borated Nooe p 11 1B 1 1 10

- in Air with Borated Water S~uc 0u~a St=~ ess Water Leakage Deformation! re~uction in a:~f:n~m, (T.P-4) - 3.5. 1-59 A, E, 520 Leakage PP (External) s truc tural capacity & gt*

0 e1orma ion Monitoring Program AS ME Class 1 Support - Carbon St t Air Indoor AS ME Section B _

1 111 1 1 13 Steel - Exposed to Air Indoor S~uc 0u~a Steel Uncontrolled Loss of Material XI, Subsection (T~ 24 ) 3.5.1 -53 A Uncontrolled PP (External) IWF Prog ram ASME Class 1 Support - Carbon St t Air w/Borated Boric Aci d B _

1 111 1 1 14 S~uc u~a (T~ 25 )

Steel - in Air with Borated Water Leakage PP 0 Steel Water Leakage (External)

Loss of Material Corrosion Program 3.5. 1-55 A ASME Class 2/3 - .constant and Air Indoor ASME Section Variab le Load Spring Hangers - Structura l . . . lll.B1 .2-2 E dt A d S rt Steel Uncontrolled Loss of Mechanical Function XI, Subsecti on (T ) 3.5.1-54 A xpose o 1r 1n oar uppo (External) IW F Program -28 Uncontrolled ASME Class 2/3 - .constant & Air w/Borated Boric Acid Variable Load Spring Hangers - Structural St W t L k L fM t . C . 111. B1.2-11 A

. A' 'th B t d W t S rt ee 1 a er ea age ass o a eria 1 orros1on (T 25 ) 3 .5 .1- 55 in ktr wt ora e a er uppo (External) Program -

Lea age AS ME Class 2/3 - Lubrite - St t I Air Indoor AS ME Section Ill B 1 2 _3 Exposed to Ai r Indoor Uncontrolled S~uc u~a PP 0 Lubrite Uncontrolled (External)

Loss of Mechanical Function XI, Subsecti on IWF Program (T~

32 ) 3.5.1 -56 A

SBK-L-17155 I Enclosure 2/ Page 199 U.S. Nuclear Regulatory Commission Table 3.5.2-6 Supports Summary of Aging Management Evaluation

'i'i Aging NU REG Table Intended . Aging 'E ffe.c:t ~equifi,ng Management Component Type Material Environment 1801 *Vol.2 1:1 3.X.1 '"1: Note Function Management Program Item Item Structures Monitoring ASME Class 2/3 Pipe Supports Air Indoor Program, Alkali-Structural Reduction in Concrete Anchor 111.81 .2-1

- Concrete - Exposed to Air Concrete Uncontrolled Silica Reaction 3.5.1-40 A, E, 517 Support Capacity (T-29)

Indoor Uncontrolled (External) (ASR)

Monitoring Program Nooe Structures Monitoring ASM E Class 2/3 - Stainless Air Indoor Nooe Structural Stainless Program, 111.81 .2-7 Steel - Exposed to Air Indoor Uncontrolled Deformation/ reduction in 3.5.1-59 A, E, 520 Support Steel Building (TP-5)

Uncontrolled (External) structural capacity Deformation Monitoring Program ASME Class 2/3 - Stainless Air w/Borated Boric Acid Structural Stainless 111.81 .2-11 Steel - in Air with Borated Water Leakage None Corrosion 3.5.1-55 A Support Steel (TP-25)

Water Leakage (Extern al) Program ASME Section ASME Class 2/3 - Stainless Structural Stainless Raw Water 111.81.1 -11 H, 509, Loss of Material XI, Subsection 3.5.1-49 Steel - in Raw Water Support Steel (Extern al) (TP-10) 514 IWF Program ASME Section ASME Class 2/3 - Stainless Structural Stainless Raw Water 111.81 .1-11 Loss of Material XI, Subsection 3.5.1-49 A, 509 Steel - in Raw Water Support Steel (External) (TP-10)

IWF Program

SBK-L-17155 I Enclosure 2/ Page 200 U.S. Nuclear Regulatory Commission Tabl e 3.5.2-6 Supports Summary of Aging Management Ev aluation

11 ., 1 1 Agin~ ' 1Effe'c~ ~~, tj~~ :i~g l'[' :!i 1 , *f *"' .

1:1* 1:1:1 ijAging '" i . :j ;1 "111' INUREG 1i'IHlr~b1e ,11:1, I

I; 11 I I *.:,

i1:

Intended ;1: 1 Component Type Fun ction Material Environment ' 1 Management .,. .1:

1 11

.i: . , :11111, i/i'ianage ine~t ' ' ,':..Ii 1 ao1 ,, 'I lv;o1.I

. 2 , 1

. 3.X.1 'I*1:.: ::N' ..ote l*j .:1: Ii I . . " : : ,. I',,. 'Program "'ilil' 11 H~1.1:: 111 ltelljl 1.

1 Item ' ,

ASME Class 2/3 - Stainless Structural Stainless Treated Borated Water Chemistry lll.A5-13 Loss of Material 3.5.1 -46 A Steel - in Treated Water Support Steel Water (Extern al) Program (T-14)

ASME Class 2/3 Support - Air Indoor ASME Section Structura l lll.B1.2-10 Carbon Steel - Exposed to Air Steel Uncontrolled Loss of Material XI, Subsection 3.5.1-5 3 A Support (T-24)

Indoor Uncontrolled (External) IWF Program ASME Class 2/3 Support Air w/Bo rated Boric Acid Structu ral lll.B1 .2-11 Carbon Steel - in Air with Steel Water Leakage Loss of Material Corrosion 3.5.1 -55 A Support (TP-25)

Borated Water Leakage (Extern al) Program Baral Poison Sheet in Spent Absorb Treated Borated Reduction of Neutron Absorbing Baral Monitoring Vll.A2-5 Bora I 3.3.1 -13 A Fuel Racks - in Treated Water Neutrons Water (Exte rnal) Capacity and Loss of Material Program (A-88)

Structures Monitoring Emergency Diesel Generator Air Indoor Program, Alkali-Structural Reduction in Concrete Anchor lll.B4-1 (EOG) - Concrete - Exposed to Concrete Uncontrolled Silica Reaction 3.5.1-40 A, E, 517 Support Capacity (T-29)

Air Indoor Unco ntrolled (External) (ASR)

Monitoring Program Emergency Diesel Gene rator Air Indoor Structures Structural lll.B4-2 (EOG) - Lubrite - Exposed to Lubrite Uncontrolled Loss of Mechanical Function Monitoring 3.5.1-52 A Support (TP-1)

Air Indoor Uncontrolled (Extern al) Program

SBK-L-17155 I Enclosure 2/ Page 201 U.S. Nuclear Regulatory Commission Table 3.5.2-6 Supports Summary of Aging Management Evaluation

., ',iJt*'

' :,

1'1

1 l*I Aging NU REG Table 111: 11,1 f'gil)g :. E~~s, t R~, quiring

,: '.I

1:1'!

Intended I

' component Type Material Enviro,n~E'.nt 'ij., 1 Management 1801,Vol.2 1*: J.X.1 Vci/. 1:1 Note Function ** 11 :1'111111" :I Management 1 1:! j;1:': I ' ,' : T

,,, . ,' *'j'I ' l::l:l'l:l"i:i:* i'l'!:HJ: 'li :1:11 1: '*** Prog,ram ;;,, 1:. :.. 11 1~ern . ,1 111 , 1 1. ~em :

Emergency Diesel Generator Air Indoor Structures (EOG) Support - Carbon Steel - Structural 111.84-10 Steel Uncontrolled Loss of Material Monitoring 3.5.1-39 A Exposed to Air Indoor Support (T-30)

(External) Program Uncontrolled Structures Monitoring Program, Alkali-HVAC System Components - Structural Air Outdoor Reduction in Concrete Anchor 111.84-1 Concrete Silica Reaction 3.5 .1-40 A, E, 517 Exposed to Air Outdoor Support (External) Capacity (T-29)

(ASR)

Monitoring Program Structures Monitoring Program, Alkali Silica Reaction (ASR)

HVAC System Components - Structural Air Outdoor 111.84-1 A,E, Concrete Expansion and cracking Monitoring 3.5.1-27 Exposed to Air Outdoor Support (External) (T-29) 517, 519 Program &

Building Deformation Monitoring Program Building HVAC System Components - Structural Air Outdoor Deformation/reduction in Deformation lll.B4-1 Steel 3.5.1-61 A, E, 520 Exposed to Air Outdoor Support (External) structural capacity Monitoring (T-29)

Program

SBK-L-17155 I Enclosure 2/ Page 202 U.S. Nuclear Regulatory Commission Tabl e 3.5.2-6 Supports Summary of Aging Management Evaluation

.' 1

'Intended

,'.!.'

Aging Effect Requiring "

1

~-H'.JREG 1

';!Aging 1:1 :1: *1 ' .:rl:r Table ' 111 111 .1J*1,,:111:

Component Type Material Environment Management . 1801 Vol. 2 3.X.1 Note , j;i Function w1: **. Management 1:i Program Item Item Building HVAC System Components - Structural Air Indoor Deformation/reduction in Deformation /11.84-1 Steel 3.5.1-61 A, E, 519 Exposed to Air Indoor Support (External) structural integrity Monitoring (T-29)

Program New Fuel Storage Racks Air Indoor Structures Support - Carbon Steel - Structural Vll.A1-1 Steel Uncontrolled Loss of Material Monitoring 3.3.1-86 A Exposed to Air Indoor Support (A-94)

(External) Program Uncontrolled New Fuel Storage Racks Air w/Borated Boric Acid Structural lll.B5-8 Support - Carbon Steel - in Air Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A Support (T-25) with Borated Water Leakage (External) Program Non-ASME - Constant and Air Indoor Structures Variable Load Spring Hangers - Structural lll.B1 .2-2 Steel Uncontrolled Loss of Mechanical Function Monitoring 3.5.1 -54 H, 514 Exposed to Air Indoor Support (T-28)

(External) Program Uncontrolled Non-ASME - Constant and Air w/Borated Boric Acid Variable Load Spring Hangers - Structural lll.B1 .2-11 Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A in Air with Borated Water Support (T-25)

(External) Program Leakage

SBK-L-17155 I Enclosure 2/ Page 203 U.S. Nuclear Regulatory Commission Table 3.5.2-6 Supports Summary of Aging Management Evaluation

1. * '1'1 :i:'

Aging NU REG ' Table Intended I I Aging ,E ffect Requiring Component Type Material Enviro nment . .

Management 11so1 vo1. 2

3.X;1 Note 111 Ma~agerrtent 1

Fun ction . ' .

I :J: .1 *1 +111.:IJ .. '1' 1,f 1_1, w Program *,

1

,i1' Ii *11it1:i1,~em1';,l*1,,!1 't~r.;i :1*

Structures Monitoring Non-ASM E Piping &

Air Indoor Program, Alkali-Components - Concrete - Structural Reduction in Concrete Anchor 111.82-1 Concrete Uncontrolled Silica Reaction 3.5.1-40 A, E, 517 Exposed to Air Indoor Support Capacity (T-29)

(External) (ASR)

Uncontrolled Monitoring Program Structures Monitoring Non-ASME Piping & Program, Alkali-Structural Air Outdoo r Redu ction in Concrete Anchor 111.82-1 Components - Concrete - Concrete Silica Reaction 3.5.1-40 A,E,517 Support (External) Capacity (T-29)

Exposed to Air Outdoor (ASR)

Monitoring Program Non-ASME Piping &

Air Indoor Structures Components - Lubrite - Structural 111.82-2 Lubrite Uncontrolled Loss of Mechan ical Function Monitoring 3.5 .1-52 A Exposed to Air Indoor Support (TP-1)

(External) Program Uncontrolled Nooe Structures Monitoring Nooe Non-ASME - Stainless Steel - Air Indoor Program, &

Structural Stainless Deformation/reduction in 111.81 .2-8 Exposed to Air Indoor Uncontrolled Building 3.5.1 -59 A, E, 520 Support Steel structural integrity (TP-4)

Uncontrolled (External) Deformation Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 204 U.S . Nuclear Regulatory Commission Table 3.5.2-6 Supports Summary of Aging Management Evaluation

" *' *I Aging NU REG Table ,\'1l':1:ri Intended 1 Aging Effect Requiring Componenf Type Material '1!1 1 Eriv,ironment ,, Management 1801Vol.2 3.X.1 Note "':,.

'Function Management

!'I 1* 1.

r'. 1 1

11 Program Item Item Non-ASM E Support - Carbon Air Indoor Structures Structural lll.B2-10 Steel - Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1-39 A Support (T-30)

Uncontrolled (External) Program Structures Non-ASME Support - Carbon Structural Air Outdoor lll.B2-10 Steel Loss of Material Monitoring 3.5.1 -39 A Steel - Exposed to Air Outdoor Support (External) (T-30)

Program Non-ASME Support - Carbon Air w/Borated Boric Acid Structural lll.B2-11 Steel - in Air with Borated Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A Support (T-25)

Water Leakage (External) Program Noo Structures Monitoring Air Indoor Noo Panels - Aluminum - Exposed Structural Program & lll.B3-2 Aluminum Uncontrolled Deformation/reduction in 3.5.1-58 A, E, 520 to Air Indoor Uncontrolled Support Building (TP-8)

(External) structural capacity Deformation Monitoring Program Air w/Borated Boric Acid Panels - Aluminum - in Air with Structural lll.B3-4 Aluminum Water Leakage Loss of Material Corrosion 3.5.1-55 A Borated Water Leakage Support (T-3)

(External) Program Panels - Carbon Steel - Air Indoor Structures Structural lll.B3-7 Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1-39 A Support (T-30)

Uncontrolled (External) Program

SBK-L-17155 I Enclosure 2/ Page 205 U.S. Nuclear Regulatory Commission Table 3.5.2-6 Supports Summary of Aging Management Evaluation 11 ' .,:I' ' 1 Vl ,11'11i.1'Jt' ,'1'1*1

!'],* .:1 1'1' Aging Effect ~e quiring 1 1!1, 111 '

1 '

1,f-9if'!~ I

' 'l' "* 'If i!]:ir NGREGill 11: I :, j;Tabl'e* : 1 ":

Intended i/ ~ ~te I

Component Type, Material Environment Ii: Management 1:. *I* ' 1801 Yol.11 2I1* Ii:I 3.X.1 11 ,,.,,*,

I IJI ..

Ji: Pr()g.ram 'it!I

11 i']i '1 lt~m

, ,Function Management ' ' 111 1

' I 1 ':1: .:1* '.1:. .'*' Item Ii; '] 1. .ll'.,.,,,,,

i1:1 :I Structures Panels - Carbon Steel -Exposed Structural Air Outdoor lll.B3-7 Steel Loss of Material Monitoring 3.5.1 -39 A to Air Outdoor Support (External) (T-30)

Program Air w/Borated Boric Acid Panels - Carbon Steel - in Air Structural lll.B3-8 Steel Water Leakage Loss of Material Corrosion 3.5. 1-5 5 A with Borated Water Leakage Support (T-25)

(External) Program Structures Monitoring Air Indoor Program, Alkali-Panels - Concrete - Exposed to Structural Reduction in Concrete Anchor lll.B3-1 Concrete Uncontrolled Silica Reaction 3.5. 1-40 A, E, 517 Air Indoor Uncontrolled Support Capacity (T-29)

(External) (ASR)

Monitoring Program Structures Monitoring Program, Alkali-Panels - Concrete - Exposed to Structural Air Outdoor Reduction in Concrete Anchor lll.B3-1 Concrete Silica Reaction 3.5. 1-40 A, E, 517 Air Outdoor Support (External) Capacity (T-29)

(ASR)

Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 206 U.S. Nuclear Regulatory Commission Table 3.5.2-6 Supports Summary of Aging Management Evaluation

*: 1:!*\;j.l~l:111*1:I ;-;I j'l:I: Jl:i 1;i.1; 111' _:j:i Aging 1 .*

NUREG lii 1

- - Table Component Type Intended Material Environment Aging Effect Requiring I I:! I Management 1* 1801 Vol. 2 .,

1 3.X.1 '

Note Function Management Program Item *lte.m Structures Monitoring Air Indoor Program , Alkali-Platform - Concrete - Exposed Structural Reduction in Concrete Anchor 111.85-1 Concrete Uncontrolled Silica Reaction 3.5.1 -40 A,E,517 to Air Indoor Uncontrolled Support Capacity (T-29)

(External) (ASR)

Monitoring Program Structures Monitoring Program, Alkali-Platform - Concrete - Exposed Structural Air Outdoor Reduction in Concrete Anchor 111.85-1 Concrete Silica Reaction 3.5.1 -40 A , E,517 to Air Outdoor Support (External) Capacity (T-29)

(ASR)

Monitoring Program Platform Supports - Carbon Air Indoor Structures Structural 111.85-7 Steel - Exposed to Air Indoor Steel Uncontrolled Loss of Material Monitoring 3.5.1 -39 A Support (T-30)

Uncontrolled (External) Program Structures Platform Supports - Carbon Structural Air Outdoor 111.85-7 Steel Loss of Material Monitoring 3.5.1-39 A , 503 Steel - Exposed to Air Outdoor Support (External) (T-30)

Program Platform Supports - Carbon Air Indoor Structures Structural Deformation/reduction in 111.85-7 Steel - Exposed to Air Indoor Steel Uncontrolled Monitoring 3.5. 1-59 E, 520 Support structural capacity (T-30)

Uncontrolled (External) Program, BD

SBK-L-17155 I Enclosure 2/ Page 207 U.S. Nuclear Regulatory Commission Table 3.5.2-6 Supports Summary of Aging Management Evaluation

"

Aging Effect Requ.i ring Aging NU REG Table Intended Component Type Material Environment Management 1801 Yol. 2 3.X.1 Note Function Management Program Item Item Platform Supports - Carbon Structures Structural Air Outdoor Deformation/reduction in lll.B5-7 Steel - Exposed to Air Steel Monitoring 3.5.1-61 E, 520 Support (External) structural capacity (T-30)

Outdoor Program, BD Platform Supports - Carbon Air w/Borated Boric Acid Structural lll.B5-8 Steel - in Air with Borated Steel Water Leakage Loss of Material Corrosion 3.5.1-55 A Support (T-25)

Water Leakage (External) Program Spent Fuel Rack Support -

Structural Stainless Treated Borated Water Chemistry Vll.A2-7 Stainless Steel - in Treated Cracking 3.3.1-90 A, 507 Support Steel Water (External) Program (A-97)

Water Nooe Thermal Insulation Aluminum Air Indoor Nooe Building Structural lll.B2-4 Jacketing - Exposed to Air Aluminum Uncontrolled Deformation/reduction in Deformation 3.5.1-58 A , E, 520 Support (TP-8)

Indoor Uncontrolled (External) structural capacity Monitoring Program Nooe Thermal Insulation Stainless Air Indoor Nooe Building Structural Stainless lll.B2-8 Steel Jacketing - Exposed to Air Uncontrolled Deformation/reduction in Deformation 3.5 .1-59 A , E, 520 Support Steel (TP-4)

Indoor Uncontrolled (External) s tructural capacity Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 208 U.S. Nuclear Regulatory Commission Table 3.5.2-6 Supports Summary of Aging Management Evaluation Standard Notes Note Description A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP.

B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.

C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP.

D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.

E Consistent with NUREG-1801 for material, environment and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program.

F Material not in NUREG-1801 for this component.

G Environment not in NUREG-1801 for this component and material.

H Aging effect not in NUREG-1801 for this component, material and environment combination .

I Aging effect in NUREG-1801 for this component, material and environment combination is not applicable.

J Neither the component nor the material and environment combination is evaluated in NUREG-1801.

501 Not used.

502 Aging effect includes "Fretting or Lockup" due to wear.

503 Crevice and pitting will be included along with loss of material-corrosion due to a saltwater atmosphere environment.

504 Fatigue analysis exists and TLAA applies.

505 Built-up roofing is not in GALL; lll.A6-12 is for elastomer-material is similar, aging effect is similar, environment is same, and AMP is Structures Monitoring.

506 Component is cementitious fire proofing/insulating material and will exhibit similar aging effects as concrete .

507 Spent Fuel Pool temperature< 60°C (<140° F); water chemistry and temperatu re will be maintained by the Water Chemistry Program.

508 Cracking, loss of bond, and loss of material (spalling, scaling)/corrosion of embedded steel-is not listed in GALL 111.A.6 as an aging effect for concrete in raw water.

Seabrook manages this effect with Structures Monitoring Program.

509 For aging management purposes, buried, below grade, soil, and ground water/ raw & treated water environments are treated the same.

510 Reduction in concrete anchor capacity is an aging effect that is addressed in LRAM-SUPT.

511 At Seabrook Station, Xl,.S7 RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" and Xl,.S5 "Masonry Wall Program" are combined under Xl,.S6 "Structures Monitoring Program".

512 Raw water in lined & unlined concrete sumps.

SBK-L-17155 I Enclosure 2/ Page 209 U.S. Nuclear Regulatory Commission 513 Seabrook Station will age manage this condition through the Fire Protection Program .

514 Seabrook Station will age manage this condition through the Structures Monitoring Program .

515 Increased hardness , shrinkage , or loss of strength of elastomer seals due to weathering is addressed by GALL only for Fire Barrier seals. Seabrook Station will manage such aging effects for non-Fire Barrier elastomer seals with the Structures Monitoring Program .

516 Seabrook Station Structures Monitoring Program will perform concrete testing and rebar inspection to determine the effects of the aggressive groundwater on the concrete. The concrete testing and the rebar inspection will represent all concrete below grade.

517 After initial identification and determination of the presence of alkali-silica reactivity by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Alkali-Silica Reaction (A SR) Monitoring Program.

519 After initial identification of alkali-silica reaction (A SR) induced building deformation by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Alkali-Silica Reaction (A SR) Monitoring Program and the Building Deformation Monitoring Program.

520 After initial identification of alkali-silica reaction (A SR) induced building deformation affecting plant equipment and components by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Building Deformation Monitoring Program.

SBK-L-17155 I Enclosure 2/ Page 210 U.S. Nuclear Regulatory Commission Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function Management Program Item Item Air Indoor TUR - Aluminum - in Air Indoor Structural Aluminum Uncontrolled None None 111.83-2 3.5.1-58 A Uncontrolled Support (External)

Structures TUR - Built-Up Roofing - Structural Air Outdoor Separation, Environmental Ill .A6-12 Roofing Monitoring 3.5.1-44 H, 505 Exposed to Air Outdoor Support (External) Degradation, Water In-Leakage (TP-7)

Program ,

Structures TUR - Carbon Steel - Exposed Structural Air Outdoor Ill .A3-12 Steel Loss of Material Monitoring 3.5.1 -25 A, 503 to Air Outdoor Support (External) (T-11)

Program Air Indoor Structures TUR - Carbon Steel - in Air Structural Ill .A3-12 Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A Indoor Uncontrolled Support (T-11)

(External) Program Structures TUR - Concrete (Sump) - Structural Raw Water Cracking, Loss of Bond, Loss of Ill .A3-4 Concrete Monitoring 3.5.1 -31 A , 509 Exposed to Raw Water Support (External) Materi al (Spalling, Scaling) (T-05)

Program

SBK-L-17155 I Enclosure 2/ Page 211 U.S. Nuclear Regulatory Commission Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation

, !j I *. Aging I. NUREG Table *:1:,:;:r:

Intended Aging Effect Requiring ,:j' Component Type Function Material Environment Management Managemen.t 1801 Vol. 2 3.x.1 :. Note

Program Item Item Structures Monitoring Program , Alkali-TUR - Concrete (Sump) - Structural Raw Water Ill .A3-2 Concrete Expa nsion and Cracking Silica Reaction 3.5.1-27 A, 517 Exposed to Raw Water Support (External) (T-03)

(ASR)

Monitoring Prog ram Structures TUR - Concrete - Exposed to Air Structural Air Outdoor Cra cking, Loss of Bond, Loss of Ill .A3-9 Concrete Monitoring 3.5.1-23 A Outdoor Support (Externa l) Material (Spall ing, Scaling) (T-04)

Program Structures Monitoring TUR - Concrete - Exposed to Air Structural Air Outdoor Program, Alkali- Ill .A3-2 Concrete Expa nsion and Cracking 3.5.1 -27 A, 517 Outdoor Support (Externa l) Silica Reaction (T-03)

(ASR)

Monitoring Increase in Porosity and Structures TUR - Concrete - Exposed to Air Structural Air Outdoor Ill .A3-10 Concrete Permeabil ity, Cracking, Loss of Monitoring 3.5.1-24 A Outdoor Support (External) (T-06)

Material (Spalling, Scal ing) Program

SBK-L-17155 I Enclosure 2/ Page 212 U.S. Nuclear Regulatory Commission Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation

:i:1.I: :

Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function Management Program Item Item Structures TUR - Concrete - Exposed to Air I Structural I Concrete I Air Outdoor I Loss of Material, Cracking Monitoring Ill .A3-6 3.5.1-26 A Outdoor Support (External) 1 (T-01)

Program

--

TUR - Concrete - in Air Indoor I Structural Air Indoor I Uncontrolled I Cracking

. , Loss of Bond, Loss of I MStructures

.t . Ill .A3-9 Uncontrolled Support I Concrete Material (Spalling, Scaling) 1 Pr~~ r~~g (T-04) 3.5.1-23 A (External)

Structures Monitoring Air Indoor TUR - Concrete - in Air Indoor Structural Program , Alkali- Ill .A3-2 Concrete Uncontrolled Expansion and Cracking 3.5.1-27 A , 517 Uncontrolled Support Silica Reaction (T-03)

(External)

(ASR)

Monitoring Air Indoor Increase in Porosity and Structures TUR - Concrete - in Air Indoor I Structural I Concrete I Uncontrolled Permeability, Cracking , Loss of Monitoring I Ill .A3-10 I 3.5.1-24 IA Uncontrolled Support (T-06)

(Externa l) Material (Spalling , Scaling) Program Structures TUR - Concrete Mason ry Units - I Structura l I Concrete Air Indoor I Uncontrolled Cracking Monitoring I Ill .A3-11 I 3.5.1-43 IA in Air Indoor Uncontrolled Support Block (T-12)

(External) Program

SBK-L-17155 I Enclosure 2/ Page 213 U. S. Nuclear Regulatory Commission Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation I'

1,i;

.1,., '*

,I* Aging NU REG Table Intended Aging Effect Requiring Component Type Material Environment Management 1801 Vol. 2 3.X.1 Note Function Management Program Item Item Air Indoor TUR - Fire Penetration Seal - in Increased Hardness, Shrinkage Fire Protection Vll.G-1 Fire Barrier Elastomer Uncontrolled 3.3.1 -61 A Air Indoor Uncontrolled and Loss of Strength Program (A-19)

(External)

Air Indoor Structures TUR - Fire Penetration Seal - in Increased Hardness, Shrinkage Vll.G-1 Fire Barrier Elastomer Uncontrolled Monitoring 3.3.1 -61 E, 514 Air Indoor Uncontrolled and Loss of Strength (A-19)

(External) Program Structures TUR - Penetration Seal - Structural Air Outdoor Increased Hardness, Shrinkage V ll.G-2 Elastomer Monitoring 3.3.1-61 E, 515 Exposed to Air Outdoor Support (External) and Loss of Strength (A-20)

Program

SBK-L-17155 I Enclosure 2/ Page 214 U.S. Nuclear Regulatory Commission Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation Standard Notes Note Description A Consistent with NUREG-1801 item for component, material , environment, and aging effect. AMP is consistent with NUREG-180 1 AMP.

B Consistent with NUREG-1801 item for component, material , environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.

C Component is different, but consistent with NUREG-1801 item for material , environment, and aging effect. AMP is consistent with NUREG-1801 AMP .

D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.

E Consistent with NUREG-1801 for materia l, environment and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program .

F Material not in NUREG-1801 for th is component.

G Envi ronment not in NUREG-1801 for th is component and material.

H Aging effect not in NUREG-1801 for this component, material and environment combination.

I Aging effect in NUREG-1801 for this component, material and environment combination is not applicable.

J Neither the component nor the material and environment combination is evaluated in NUREG-1801 .

50 1 Not used .

502 Aging effect includes "Fretting or Lockup" due to wear.

503 Crevice and pitting will be included along with loss of material-corrosion due to a saltwater atmosphere environment.

504 Fatigue analysis exists and TLAA applies.

505 Built-up roofing is not in GALL; lll.A6-12 is for elastomer-material is similar, aging effect is similar, envi ronment is same , and AMP is Structures Mon ito ring .

506 Component is cementitious fi re proofi ng/insulating material and will exhibit similar aging effects as concrete.

507 Spent Fuel Pool temperature< 60°C (<1 40° F); water chemistry and temperature will be maintained by the Water Chemistry Prog ram .

508 Cracking , loss of bond , and loss of material (spalling , scaling)/corrosion of embedded steel-is not listed in GALL 111.A.6 as an aging effect for concrete in raw water.

Seabrook manages this effect with Structures Monitoring Program.

509 For ag ing management purposes , buried , below grade, soil, and ground water/ raw & treated water environments are treated the same.

510 Reduction in concrete anchor capacity is an aging effect that is addressed in LRAM-SUPT.

511 At Seabrook Station , Xl.S7 "RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" and XI.SS "Mason ry Wall Program" are combined under Xl. S6 "Structures Monitoring Program".

512 Raw water in lined & unlined concrete sumps .

513 Seabrook Station will age manage this cond ition through the Fire Protection Program.

514 Seabrook Station will age manage this condition through the Structures Monitoring Program .

515 Increased hardness, shrinkage, or loss of strength of elastomer seals due to weathering is addressed by GALL only for Fire Barrier seals. Seabrook Station wi ll manage such aging effects for non-Fire Barrier elastomer seals with the Structures Monitoring Program .

516 Seabrook Station Structures Monitoring Program will perform concrete testing and reba r inspection to determine the effects of the aggressive groundwater on the concrete . The concrete testing and the rebar inspection will represe nt all concrete below grade.

517 After initial identification and determination of the presence of alkali-silica reac tivity by the Structures Monitorin g Program, Seabrook Station will age manage this condition through the Alkali-Silica Reaction (ASR) Monitoring Program.

SBK-L-17155 I Enclosure 2/ Page 215 U.S . Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Tab I ~

Intended Aging Effect., R~q!Jiring *:11 NU REG .1 1801 Component Type Material Environment Management 3.X. 1 Note Function Management Vol. 2 Item Program I Item Structures Monitoring WCS - Built-Up Roofing - Program ,

Separation , Environmental SERVICE WATER COOLING Shelter, Air Outdoor Building lll.A6-12 H, 505 ,

Roofing Degradation, Water In- 3.5.1-44 TOWER Including Switchgear Protection (External) Deformation (TP-7) E, 520 Leakage Rooms in Air Outdoor Monitoring Program Structures Monitoring Program, WCS - Built-Up Roofing - Separation , Environmental Shelter, Air Outdoor Building lll.A6-12 H, 505 ,

SERVICE WATER Roofing Degradation , Water In- 3.5.1-44 Protection (External) Deformation (TP-7) E, 520 PU MPHOUSE in Air Outdoor Leakage Monitoring Program WCS - Carbon Steel Door -

Structures SERVICE WATER COOLING Shelter, Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A, 503 TOWER Including Switchgear Protection (External) (T-11)

Program Rooms in Air Outdoor W CS - Carbon Steel Door -

Air Indoor Structu res SERVICE WATER COOLING Structural lll.A3-12 Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A TWR Including Swgr Rms in Air Support (T-11)

(External) Program Indoor Uncontrolled WCS - Carbon Steel Door -

Air Indoor Structures SERVICE WATER Structural lll.A3-12 Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 A PU MPHOUSE in Air Indoor Support (T-11)

(External) Program Uncontrolled WCS - Carbon Stee l Door - Structures Shelter, Air Outdoor lll.A3-12 SERVICE WATER Steel Loss of Material Monitoring 3.5. 1-25 A, 503 Protection (External) (T-11)

PUMPHOUSE in Air Outdoor Program

SBK-L-17 155 I Enclosure 2/ Page 216 U. S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation 1:l

' I: '*' :, . Fl"I' Aging n* .Jable Intended Aging Effect Requiring NUREG 18P1 Component Type Material Environment Management *: 3.X.1 Note Function Management Vol. 2 Item Program ltein WCS - Carbon Steel Fire Door -

Air Indoor SERVICE WATER COOLING Fire Protection Vll.G-3 Fire Barrier Steel Uncontrolled Loss of Material 3.3. 1-63 A TWR Including Swgr Rms in Air Program (A-2 1)

(External)

Indoor Uncontrolled WCS - Carbon Steel Fire Door -

Air Indoor SERVICE WATER Fire Protection Vll.G-3 Fire Barrier Steel Uncontrolled Loss of Material 3.3. 1-63 A PUMPHOUSE in Air Indoor Program (A-21)

(External)

Uncontrolled WCS - Carbon Steel - SERVICE Structures WATER COOLING TOWER Structural Air Outdoor lll.A3-12 Steel Loss of Material Monitoring 3.5.1-25 A, 503 Includ ing Switchgear Rooms in Support (External) (T-11 )

Program Air Outdoor WCS - Carbon Steel - SERVIC E Structures Structural Raw Water 11 1.A6-1 1 WATER COOLING TOWER in Steel Loss of Material Monitoring 3.5.1 -47 E, 511 Support (External) (T-2 1)

Raw Water Program WCS - Carbon Steel - SERVICE Structures Structural Raw Water lll. A6-11 WATER COOLING TOWER in Steel Loss of Material Monitoring 3.5.1-47 E, 51 1 Support (External) (T-21 )

Raw Water Program WCS - Carbon Steel - SERVICE Structures Structural Raw Water 111.A6-11 WATER COOLING TOWER in Steel Loss of Material Monitoring 3.5.1-47 H, 511 Support (External) (T-21 )

Raw Water Program

SBK-L-17155 I Enclosure 2/ Page 217 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation

. I NUREG -; 180,111. . ,

Effe~t ~.f~u*,ri~,~ ' *I.' ,* . Agmg .Table .

1 :::,

x*.

Intended Component Type Material "Vol_:_, z_ ltery:i_wi" I . , 3Item*.. ; Note I ' * * ' ' 'II I 1:11:1!11.,. * ,

1*

Function '.A.g__ in_g 1 M_*anagemen_t. *I.*

, "I* l:i:."1 1 1 I... *:1:1:

J, Management

,*1*::1:i:1: *1;1 :1; . " **' * !*

, * '*l:i1' Program

' 1. iii I ,,Ii. *1:. :1 ** " '

1:

1 1 WCS - Carbon Steel - SERVICE Structures Structural Raw Water lll.A6-11 WATER COOLING TOWER in Steel Loss of Material Monitoring 3.5.1-47 I E, 511 Support (External) (T-21)

Raw Water Program WCS - Carbon Steel - SERVICE Air Indoor Structures WATER COOLING TWR Structural lll.A3-12 Steel Uncontrolled Loss of Material Monitoring 3.5.1 -25 I A Including Swgr Rms in Air Support (T-11)

(External) Program Indoor Uncontrolled WCS - Carbon Steel - SERVICE Air Indoor Structures Structural lll.A3-12 WATER PUMPHOUSE in Air Steel Uncontrolled Loss of Material Monitoring 3.5.1-25 I A Support (T-11)

Indoor Uncontrolled (External) Program WCS - Carbon Steel - SERVICE Structures Structural Raw Water lll.A6-11 WATER PUMPHOUSE in Raw Steel Loss of Material Monitoring 3.5. 1-47 I E, 511 Support (External) (T-21)

Water Program WCS - Carbon Steel - SERVICE Structures Structural Raw Water lll.A6-11 WATER PUMPHOUSE in Raw Steel Loss of Material Monitoring 3.5. 1-47 I E, 511 Support (External) (T-21)

Water Program WCS - Carbon Steel - SERVICE Structures Structural Raw Water lll.A6-11 WATER PUMPHOUSE in Raw Steel Loss of Material Monitoring 3.5.1-47 I H, 511 Support (External) (T-21)

Water Program

SBK-L-17 155 I Enclosure 2/ Page 2 18 U. S. Nuc lear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation

,I ,I :j:'J',, ,' ,,, j.11, :t 1:11:, ' I A . I'i: :I ,;lil:il'l'I :1:1 NUREG 11

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1 T

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1;.

, Intended ' Aging Effect Requ irir;ig ,, i,;p,, , mog *l1 aotli 1 Component Type

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1 , Material Function ,' '!:'" ii: ;

Environment Management '

1 Management :::,, ::1ti:**l1

t.1 t'11l**1 'I ,: ' 113.X. 11:1 i' Program. ,. ' 1 NI, ol;1 2 Item ,'

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., I* 1

' '

WCS - Carbon Steel - SERVICE Structures Structural Raw Water lll. A6-11 WATER PUMPHOUSE in Raw Steel Loss of Material Monitoring 3.5. 1-47 E, 511 Support (External) (T-2 1)

W ater Program WCS - Carbon Steel - SERVICE Air Indoor Structures Shelter, lll.A3-12 WATER PUMPHOUSE Siding Steel Uncontrolled Loss of Material Monitoring 3.5. 1-25 A Protection (T- 11) in Air Indoor Uncontrolled (External) Program WCS - Carbon Steel - SERVICE Structures Shelter, Air Outdoor lll.A3- 12 WATER PUMPHOU SE Siding Steel Loss of Material Monitoring 3.5.1-25 A, 503 Protection (External) (T-11) in Ai r Outdoor Program WCS - Concrete - Ground Structu res Structural Cracking, Loss of Bond, Loss 111.A3-4 CIRCULATING WATER Concrete Water/Soil Monitoring 3.5.1-31 A Support of Material (Spalling, Scaling) (T-05)

PU MPHOUSE Below Grade (External) Program Structures Monitoring Program , Alkal i-Silica Reaction W CS - Concrete - Ground (ASR)

Structural ll l.A3-2 A, E, CIRCULATI NG WATER Concrete Water/Soil Expansion and Cracking Monitoring 3.5. 1-27 Support (T-03) 517, 519 PU MPHOUSE Below Grade (External) Program &

Building Deformation Monitoring Proaram

SBK-L-17155 I Enclosure 2/ Page 219 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation J1 lJ 1*1

' Aging :iJ , . :j ,.'"J:,'i l*lll,,1':1 "'1'1'

.1 I I ,;j: 111: il:I, .

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11 Aging Effect Requiring NUREG 1801 t Table l".i:i:' 'I' 'Ii .Iii 1

Component Type Material Environment Management 1 3.X.1 1,Note lil'I

111

Function 1*1 11 ;(:1 :I::. Ah:', I; ,,. Management Vol. 2 Item

'

,1*1 .. 1!' ""'

1

,,,

Program Item t1/m1****.,

1 WCS - Concrete - Ground Increase in Porosity and Structures Structural lll.A3-5 CIRCULATING WATER Concrete Water/Soil Permeability, Cracking, Loss Monitoring 3.5.1-31 A Support (T-07)

PUMPHOUSE Below Grade (External) of Material (Spalling, Scaling) Program WCS - Concrete - Ground Increase in Porosity and Structures Structural lll .A3-7 CIRCULATING WATER Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-32 A, 509 Support (T-02)

PUMPHOUSE Below Grade (External) Strength Program WCS - Concrete - Ground Structures Structural lll.A3-6 CIRCULATING WATER Concrete Water/Soil Loss of Material, Cracking Monitoring 3.5.1-26 A Support (T-0 1)

PUMPHOUSE Below Grade (Externa l) Program WCS - Concrete -

Air Indoor Structures CIRCULATING WATER Structural Cracking, Loss of Bond , Loss lll.A3-9 Concrete Uncontrolled Monitoring 3.5.1-23 A PUMPHOUSE in Air Indoor Support of Material (Spalling, Scaling) (T-04)

(External) Program Uncontrolled Structures Monitoring Program, Alkali-Silica Reaction WCS - Concrete -

Air Indoor (ASR)

CIRCULATING WATER Structural lll.A3-2 A, E, Concrete Uncontrolled Expa nsion and Cracking Monitoring 3.5.1-27 PUMPHOUSE in Air Indoor Support (T-03) 517, 519 (External) Program &

Uncontrolled Building Deformation Monitoring Proqram

SBK-L- 17155 I Enclosure 2/ Page 220 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation ii! I 11m ' 1:1:1,!i I I'll', ' ' ;i.1 Aging Table 111:1 Intended A in 'I Effect Re uirin , NU REG 180,1, Component Type Material Environment . I *,:l.g lg l, l'l.1.1." 1111*. q :* .. 1: *l gl*I: !*1'l1 H1: Management 11 .1: '3.:X. 1 Note H. :I. ' , .,: ' ' ~

V 1

~ 1'1 ~ /Tu:m J~

Function 1 Management 1:1 *1 {

I I 1* !*,:," l1f '

1:1 'I' I J .I . 11:1 1:1!: ~ ~o~ r,am ,, },. ilj ii: ?

I 1 .:1!ji1*.;1:-* ep1 1n1. i' WCS - Concrete -

Air Indoor Increase in Porosity and Structures CIRCULATING WATER Structural lll.A3-10 Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5.1-24 A PUMPHOUSE in Air Indoor Support (T-06)

(External) of Material (Spalling, Scaling) Program Uncontrolled WCS - Concrete - Structures Shelter, Air Outdoor Cracking, Loss of Bond, Loss 111.A3-9 CIRCULATING WATER Concrete Monitoring 3.5.1-23 A Protection (External) of Material (Spalling, Scaling) (T-04)

PUMPHOUSE in Air Outdoor Program Structures Monitoring Program , Alkali-Silica Reaction (ASR)

WCS - Concrete -

Shelter, Air Outdoor Monitoring ll l.A3-2 A, E, CIRCULATING WATER Concrete Expansion and Cracking 3.5.1-27 Protection (External) Program & (T-03) 517, 5 19 PUMPHOUSE in Air Outdoor Building Deformation Monitoring Program WCS - Concrete - Increase in Porosity and Structures Shelter, Air Outdoor lll.A3-10 CIRCULATING WATER Concrete Permeability, Cracking, Loss Monitoring 3.5.1 -24 A Protection (External) (T-06)

PUMPHOUSE in Air Outdoor of Material (Spalling, Scaling) Program WCS - Concrete - Structures Shelter, Air Outdoor lll. A3-6 CIRCULATING WATER Concrete Loss of Material, Cracking Monitoring 3.5.1 -26 A Protection (External) (T-01 )

PUMPHOUSE in Air Outdoor Program

SBK-L-17155 I Enclosure 2/ Page 221 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Stru ctures Summary of Aging Management Evaluation

, Agiri'9 'J, ilt, ,11!1 ,. *11 i:l:1* *1:t::l 1 * ,, +

1 T~b'i'e 1 ii ,I

I Intended Aging Effect Requiring .. NU REG 1801 1 Component Type Material Environment Management 3.X. 1 Note ..

Function Management Vol. 2 Item Program Item WCS - Concrete - Structures Structural Raw Water Cracking , Loss of Bond , Loss lll.A3-4 CIRCULATING WATER Concrete Monitoring 3.5 .1-3 1 A, 509 Support (External) of Material (Spalling, Scaling) (T-05)

PUMPHOUSE in Raw Water Program Structures Monitoring Program , Alka li-Silica Reaction (ASR)

WCS - Concrete -

Structura l Raw Water Monitori ng lll.A3-2 A, E, CIRCULATING WATER Concrete Expansion and Cracking 3.5 .1-27 Support (External) Program & (T-03) 517, 519 PUMPHOUSE in Raw Water Building Deformation Monitoring Program WCS - Concrete - Increase in Porosity and Structures Structural Raw Water lll.A3-7 CIRCULATING WATER Concrete Permeability, Loss of Monitoring 3.5 .1-32 A Support (External) (T-02)

PUMPHOUSE in Raw Water Strength Program WCS - Concrete - Structures Structural Raw Water lll.A6-7 CIRCULATING WATER Concrete Loss of Material Monitoring 3.5.1-45 E, 511 Support (Extern a!) (T-20)

PUMPHOUSE in Raw Water Program WCS - Concrete - SERVICE Gro und Structures WATER COOLING TOWER Structural Cracking, Loss of Bond , Loss lll.A3-4 Concrete Water/Soil Monitoring 3.5.1 -31 A Including Switchgear Rooms Support of Material (Spalling , Scaling) (T-05)

(External) Program Below Grade

SBK-L-17155 I Enclosure 2/ Page 222 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation

,11 Component Type Intended Material Environment Aging Effect Requiring ' 'l *';1::1l'i1 Agin'g

' Management .

II l :i: :li:ll'"' '1:l:::,,:al:111l:1:*1:1::1 1 NLJREG, 1801,

1: .liable ;;*

'* 3.X.1 l'

Management iJ Vol. 2 Item " Note Function

Item Program Structures Monitoring Program , Alkali-Silica Reaction WCS - Concrete - SERVICE (ASR)

Ground WATER COOLING TOWER Structural Monitoring lll.A3-2 A, E, Concrete Water/Soil Expansion and Cracking 3.5.1 -27 Including Switchgear Rooms Support Program & (T-03) 517, 519 (External)

Below Grade Building Deformation Monitoring Program WCS - Concrete - SERVICE Ground Increase in Porosity and Structures WATER COOLING TOWER Structural lll.A3-5 Concrete Water/Soil Permeability, Cracking , Loss Monitoring 3.5.1-31 A Including Switchgear Rooms Support (T-07)

(External) of Material (Spalling , Scaling) Program Below Grade WCS - Concrete - SERVICE Ground Increase in Porosity and Structures WATER COOLING TOWER Structural lll.A3-7 Concrete Water/Soil Permeability, Loss of Monitoring 3.5.1-32 A, 509 Including Switchgear Rooms Support (T-02)

(External) Strength Program Below Grade WCS - Concrete - SERVICE Ground Structures WATER COOLING TOWER Structural lll.A3-6 Concrete Water/Soil Loss of Material, Cracking Monitoring 3.5.1 -26 A Including Switchgear Rooms Support (T-01)

(External) Program Below Grade WCS - Concrete - SERVICE Structures WATER COOLING TOWER Air Outdoor Cracking, Loss of Bond, Loss lll.A3-9 Missile Barrier Concrete Monitoring 3.5.1 -2 3 A Including Switchgear Rooms in (External) of Material (Spalling, Scaling) (T-04)

Program Air Outdoor

SBK-L- 17155 I Enclosure 2/ Page 223 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation

,, I* . ' ' ". *'*I*

Ji. ,::,-:.:Ii l'li'll1 11l:j:il'*1.1:

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Component Type Materi~i ' Environmer:it ,. Management 3.X.1 . Note"Ir t'*i!ii:I Function ii. Jfli] ' Management Vol. 2 Item :I:: :J:1 ljjlll Program Item

'I' WCS - Concrete - SERVICE Structures WATER COOLING TOWER Shelter, Air Outdoor Cracking, Loss of Bond, Loss ll l.A3-9 Concrete Monitoring 3.5.1-23 A Including Switchgear Rooms in Protection (External) of Material (Spalling, Scaling) (T-04)

Program Air Outdoor Structures Monitoring Program , Alkali-Silica Reaction WCS - Concrete - SERVICE (ASR)

WATER COOLING TOWER Air Outdoor Monitoring lll.A3-2 A, E, Missile Barrier Concrete Expansion and Cracking 3.5.1-27 Including Switchgear Rooms in (External) Program & (T-03) 517, 519 Air Outdoor Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction WCS - Concrete - SERVICE (ASR)

WATER COOLING TOWER Shelter, Air Outdoor lll.A3-2 A, E, Concrete Expansion and Cracking Monitoring 3.5.1-27 Including Switchgear Rooms in Protection (External) (T-03) 517, 519 Program &

Air Outdoor Building Deformation Monitoring Proaram WCS - Concrete - SERVICE Increase in Porosity and Structures WATER COOLING TOWER Air Outdoor lll.A3-10 Missile Barrier Concrete Permeability, Cracking, Loss Monitoring 3.5.1-24 A Including Switchgear Rooms in (External) (T-06) of Material (Spa lling , Scaling) Program Air Outdoor

SBK-L-171 55 I Enclosure 2/ Page 224 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation iji '

'*1: Aging Table :1:,

I Aging Effect Requiring NUREG 1801 Intended 11

Component Type Material Environment Management 3.X. 1 Note Function lll!an~gement V ol. 2 Item Program Item WCS - Concrete - SERVICE Increase in Porosity and Structures WATER COOLING TOWER Shelter, Air Outdoor lll.A3-10 Concrete Permeability, Cracking , Loss Monitoring 3.5.1-24 A Including Switchgear Rooms in Protection (External) (T-06) of Material (Spalling , Scal ing) Program Air Outdoor WCS - Concrete - SERVICE Structures WATER COOLING TOWER Air Outdoor lll.A3-6 Missile Barrier Concrete Loss of Material, Cracking Monitoring 3.5. 1-26 A Including Switchgear Rooms in (External) (T-0 1)

Program Air Outdoor WCS - Concrete - SERVICE Structures WATER COOLING TOWER Shelter, Air Outdoor lll.A3-6 Concrete Loss of Material , Cracking Monitori ng 3. 5.1-26 A Including Switchgear Rooms in Protection (External) (T-0 1)

Program Ai r Outdoor WCS - Concrete - SERVI CE Structures Structural Raw Water Cracking, Loss of Bond, Loss lll. A3-4 WATER COOLI NG TOWER in Concrete Mon itoring 3. 5.1-31 A, 509 Support (External) of Material (Spalling, Scaling) (T-05)

Raw Water Program W CS - Concrete - SERVI CE Structures Ultimate Heat Raw Water Cracking, Loss of Bond , Loss lll. A3-4 WATER COOLI NG TOWER in Concrete Mon itoring 3.5.1 -31 A , 509 Sin k (External) of Material (Spalling , Scaling) (T-05)

Raw Water Program Structures Monitoring Program , Alkal i-

.Silica Reaction WCS - Concrete - SERVI CE Structural Raw Water (ASR) lll.A3-2 A , E, WATER COOLING TOWER in Concrete Expansion and Cracking 3. 5.1-27 Support (External) Mon itoring (T-03) 517, 5 19 Raw Water Program &

Building Deformation Monitorina

SBK-L-17155 I Enclosure 2/ Page 225 U.S . Nuclear Regulatory Commission Table 3.5. 2-8 Water Control Stru ctures Summary of Aging Management Evaluation I

~i~lli:,]!1 Aging ' 1, Table rll ll ' Intended 1 Aging Effect Requiring NUREG 1801 Component Type Material *:

1 Environment Management 3.X.1 Functi on 11 Management Vol. 2 Item

',,' ' ' 11111111 111 11*., ':j, " ::i Program Item Program Structures Monitoring Program, Alkali-Silica Reaction (ASR)

WCS - Con creti;! - SE RVICE Ultimate Heat Raw Water Monitoring lll.A3-2 A, E, WATER COOLING TOWER in Concrete Expa nsion and Cracking 3.5.1 -27 Sink (External) Program & (T-03) 517, 519 Raw Water Building Deformation Monitoring Program WCS - Concrete - SERVI CE Increase in Porosity and Structures Structural Raw Water lll.A3-7 WATER COOLING TOWER in Concrete Perm eability, Loss of Monitoring 3.5 .1-32 A Support (External) (T-02)

Raw Water Strength Program WCS - Concrete - SERVICE Increase in Porosity and Structures Ultimate Heat Raw Water lll.A3-7 WATER COOLING TOWER in Concrete Perm eability, Loss of Monitoring 3.5.1 -32 A Sink (External) (T-02)

Raw Water Strength Program WCS - Concrete - SERVI CE Structures Structural Raw W ater lll. A6-7 WATER COOLING TOWER in Concrete Loss of Material Monitoring 3.5.1-45 E, 511 Support (External) (T-20)

Raw Water Program

SBK-L-17 155 I Enclosure 2/ Page 226 U. S. Nuclear Regulatory Commission Table 3.5.2-8 Water Contro l Structures Summary of Aging Management Evaluati on

,, I:' ' l: .1:

t I1 Ag i~ g 1

11 :lb .:I: :i,('

Table '

11 Intended 1:1, I *:

Material, ill , Environment Aging Effect Requiring Management NU REG 1801 3.X. 1 I \I 'I" 'II: :1,1' I' Comppnent Type Fu nction Management Vol. 2 Item , I: Note ' "lI ii*

Program Item '" ' J!1:.ll:

j'I WCS - Concrete - SERVICE Structures Ultimate Heat Raw Water lll.A6-7 WATER COOLI NG TOWER in Concrete Loss of Material Monitoring 3.5. 1-45 E, 511 Sink (External) (T-20)

Raw W ater Program W CS - Concrete -SERVICE Air Indoor WATER COOLI NG TWR Fire Protection Vll.G-29 Fire Barrier Concrete Uncontrolled Loss of Material 3. 3. 1-67 A Including Swgr Rms in Air Program (A-9 1)

(External)

Indoor Uncontrolled W CS - Concrete -SERVICE Air Indoor WATER COOLING TWR Structural Fire Protection Vll. G-29 Concrete Uncontrolled Loss of Material 3.3. 1-67 A Including Swgr Rms in Air Support Prog ram (A-9 1)

(External)

Indoor Uncontrolled WCS - Concrete -SERVICE Air Indoor Structures WATER COOLI NG TWR Cracking , Loss of Bond , Loss lll. A3-9 Fire Barrier Concrete Uncontrolled Monitoring 3.5, 1-23 A Including Swgr Rms in Air of Material (Spalling, Scaling) (T-04)

(External) Program Indoor Uncontrolled WCS - Concrete -SERVICE Air Indoor Structures WATER COOLING TWR Structural Cracking , Loss of Bond , Loss lll.A3-9 Concrete Uncontrolled Monitoring 3.5. 1-2 3 A Including Swgr Rms in Ai r Support of Material (Spalling, Scaling) (T-04)

(External) Program Indoor Uncontrolled W CS - Concrete -SERVICE Ai r Indoor WATER COOLING TWR Concrete Cracking and Fire Protection Vll. G-28 Fire Barrier Concrete Uncontrolled 3.3.1 -65 A Including Swgr Rms in Air Spalling Prog ram (A-90)

(External)

Indoor Uncontrolled

SBK-L-17155 I Enclosure 2/ Page 227 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Stru ctures Summary of Aging Management Evaluation j:i'J:ii1 11 1: l: !;. I .,ii *r:*. ":'

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Component Type Material Environment 11 ,, ' "'

,

Management H'

I 1:

11 V ol. 2 Item ., ':' 3.X. ~ . 1.1 l'I Note '

'

1:1: ;,,,

.Function *

1 1;1; Management ' 1 Program 1

Item 'jl!' 'l'Jlli' f'

1::1:

1:

WCS - Concrete -SERVICE Air Indoor WATER COOLING TWR Structural Concrete Cracking and Fire Protection Vll. G-28 Concrete Uncontrolled 3.3 .1-65 A Including Swgr Rms in Air Support Spalling Program (A-90)

(External)

Indoor Uncontrolled Structures Monitoring Program , Alkali-Silica Reaction WCS - Concrete -SERVICE (ASR)

Air Indoor WATER COOLING TWR Monitoring lll .A3-2 A, E, Fire Barrier Concrete Uncontrolled Expansion and Cra cking 3.5. 1-27 Including Swgr Rms in Air Program & (T-03) 517, 519 (External)

Indoor Uncontrolled Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction WCS - Concrete -SERVICE (ASR)

Ai r Indoor WATER COOLING TWR Structu ral Monitoring lll.A3-2 A, E, Concrete Uncontrolled Expan sion and Cra cking 3.5 .1-27 Including Swgr Rms in Air Support Program & (T-03) 517, 519 (External)

Indoor Uncontrolled Building Deformation Monitoring Program WCS - Concrete -S ERVI CE Air Indoor WATER COOLING TWR Concrete Cracki ng and Fire Protection Vll.G-28 Fire Barrier Concrete Uncontrol led 3.3. 1-65 A Including Swgr Rms in Air Spalling Program (A-90)

(External)

Indoor Uncontrolled

SBK-L-17155 I Enclosure 2/ Page 228 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation l;:l*i .

Aging Table Intended Aging Effect Requiring 1.1 NUREG 1801 Component Type Material Environment Management '" ' 3.X.1 N.ote Function Management ', Program Vol. 2 Item Item WCS - Concrete -SERVICE Air Indoor WATER COOLING TWR Structural Concrete Cracking and Fire Protection Vll.G-28 Concrete Uncontrolled 3.3 .1-65 A Including Swgr Rms in Air Support Spalling Program (A-90)

(External)

Indoor Uncontrolled WCS - Concrete -SERVICE Air Indoor Increase in Porosity and Structures WATER COOLING TWR lll.A3-10 Fire Barrier Concrete Uncontrolled Permeability, Cracking, Loss Monitoring 3.5.1-24 A Including Swgr Rms in Air (T-06)

(External) of Material (Spalling, Scaling) Program Indoor Uncontrolled WCS - Concrete -SERVICE Air Indoor Increase in Porosity and Structures WATER COOLING TWR Structural lll.A3-10 Including Swgr Rms in Air Support Concrete Uncontrolled Permeability, Cracking , Loss Monitoring (T-06) 3.5.1-24 A (External) of Material (Spalling, Scaling) Program Indoor Uncontrolled WCS - Concrete - SERVICE Ground Structures Structural Cracking , Loss of Bond, Loss lll.A3-4 WATER PUMPHOUSE Below Concrete Water/Soil Monitoring 3.5.1-31 A Support of Material (Spalling, Scaling) (T-05)

Grade (External) Program Structures Monitoring Program, Alkali-Silica Reaction (ASR)

WCS - Concrete - SERVICE Ground Structural Monitoring lll.A3-2 A , E, WATER PUMPHOUSE Below Concrete Water/Soil Expansion and Cracking 3.5.1-27 Support Program & (T-03) 517, 519 Grade (External)

Building Deformation Monitoring Program

SBK-L-17155 I Enclosure 2/ Page 229 U. S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation i:lil11l:11111111:1:J;1W jll l; 1 11:1:-r~t;\*~ 1::y. 111:1* 11 ,,, ,..

~~~L ' 1 l 1 il 'i i A~'in~ 1:['lilJli:i1ll'l i 1 ~i:~~~il1'F\::: II:',* :.: 'Management I ,*1 1 1:!:1::'

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'

,Intended Aging Effect [

'1il NU REG 1,11.BO t ' 11 3:X. 1 'Ii '!1 11!1iNote .1' Component Type , I~ ! !'Jlaterial Environment M , t , ,. 1. :

fiuri cti on

anageme~ " p ' , Vol. 2 Item '*1 Item 1 ' l*I 1*i .1t.':iV:

1 1

. , , . rogram * ~ ' . 'lfJl:i;1':::*,1:1*

1+1 *ii' 1 WCS - Concrete - SERVICE Ground Increase in Porosity and Structures Structural 111.A3-5 WATER PUMPHOUSE Below Concrete Water/Soil Permeability, Cracking , Loss Monitoring 3.5.1-31 A Support (T-07)

Grade (External) of Material (Spalling, Scaling) Program WCS - Concrete - SERVICE Ground Increase in Porosity and Structures Structural lll.A3-7 WATER PUMPHOUSE Below Concrete Water/Soil Permeability, Loss of Monitoring 3.5. 1-32 A, 509 Support (T-02)

Grade (External) Strength Program WCS - Concrete - SERVICE Ground Structures Structural lll.A3-6 WATER PUMPHOUSE Below Concrete Water/Soil Loss of Material, Cracking Monitoring 3.5.1-26 A Support (T-01)

Grade (External) Program WCS - Concrete - SERVICE Air Indoor Fire Protection Vll.G-29 WATER PUMPHOUSE in Air Fire Barrier Concrete Uncontrolled Loss of Material 3.3.1-67 A Program (A-9 1)

Ind oor Uncontrolled (External)

WCS - Concrete - SERVICE Air Indoor Structural Fire Protection Vll.G-29 WATER PUMPHOUSE in Air Concrete Uncontrolled Loss of Material 3.3.1-6 7 A Support Program (A-9 1)

Indoor Uncontrolled (Extern al)

WCS - Concrete - SERVICE Air Indoor Structures Cracking, Loss of Bond , Loss lll.A3-9 WATER PUMPHOUSE in Air Fire Barrier Concrete Uncontrolled Monitoring 3.5.1-23 A of Material (Spall ing, Scaling) (T-04)

Indoor Uncontrolled (External) Program

SBK-L-171 55 I Enclosure 2/ Page 23 0 U.S . Nuclear Regulatory Commission Table 3.5.2-8 W ater Control Structures Summary of Ag ing Management Evaluati on Aging Table Intended Aging Effect Requ iring NUREG 1801 Component Type Material Environment Management 3.X. 1 Note Function I' 1F,:i:I Management Vol. 2 Item I', , 1 ,I Program Item W CS - Concrete - SERVICE Air Indoor Structures Structura l Cracking , Loss of Bond , Loss lll.A3-9 WATER PU MPHOUSE in Air Concrete Uncontrol led Monito ring 3.5.1 -23 A Suppo rt of Material (Spalling , Scaling) (T-04)

Ind oor Uncontro lled (External) Program WCS - Concrete - SERVICE Air Indoor Concrete Cracking and Fire Protection Vll. G-28 WATER PU MPHOUSE in Air Fire Barrier Concrete Uncontrolled 3.3.1-65 A Spalling Progra m (A-90)

Indoor Uncontro lled (External)

W CS - Concrete - SERVICE Ai r Indoor Structura l Concrete Cracking and Fire Protecti on Vll. G-28 WATE R PU MPHOUSE in Ai r Concrete Uncontrolled 3.3.1 -65 A Support Spalling Program (A-90)

Indoor Uncontrol led (External)

Structures Monitoring Program, Alkali-Silica Reacti on W CS - Concrete - SERVICE Air Indoor (ASR) lll.A3-2 A , E, WATER PUMPHOUSE in Ai r Fire Barrier Concrete Uncontrolled Expansion and Cracking Monitori ng 3.5. 1-27 (T-03) 517, 519 Indoor Uncontrolled (External) Progra m &

Building Deformation Monitoring Proqram Structures Monitoring Program, Alkali-Silica Reaction W CS - Con crete - SERVICE Ai r Indoo r (ASR)

Structura l lll.A3-2 A, E, WATER PU MPHOUSE in Air Concrete Uncontrolled Expansion and Cracking Monitoring 3.5 .1-27 Support (T-03) 51 7, 519 Indoor Uncontrolled (External) Program &

Building Deform ation Monitorin g Program

SBK-L- 171 55 I Enclosure 2/ Page 231 U. S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation

,., I*

" '1; *'"'1',!I

. 'l Aging Table Intended Aging Effect Requiring NUREG 1801 Component Type Material Environment Management 3.X. 1 Note Function Management Vol. 2 Item Program Item WCS - Concrete - SERVICE Air Indoor Concrete Cracking and Fire Protection Vll. G-28 WATER PUMPHOUSE in Air Fire Barrier Concrete Uncontrolled 3.3. 1-65 A Spalling Program (A-90)

Indoor Uncontrolled (External)

WCS - Concrete - SERVICE Air Indoor Structura l Concrete Cracking and Fire Protection Vll. G-28 WATER PUMPHOUSE in Air Concrete Uncontrolled 3.3. 1-65 A Support Spalling Program (A-90)

Indoor Uncontrolled (External)

WCS - Concrete - SERVICE Air Indoor Increase in Porosity and Structures lll.A3-10 WATER PUMPHOUSE in Air Fire Barrier Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5. 1-24 A (T-06)

Indoor Uncontrolled (External) of Material (Spalling, Scaling) Program WCS - Concrete - SERVICE Air Indoor Increase in Porosity and Structures Structural lll.A3-10 WATER PUMPHOUSE in Air Concrete Uncontrolled Permeability, Cracking , Loss Monitoring 3.5.1-24 A Support (T-06)

Indoor Uncontrolled (External) of Material (Spalling , Scaling) Program WCS - Concrete - SERVICE Structures Air Outdoor Cracking, Loss of Bond, Loss lll. A3-9 WATER PUMPHOUSE in Air Missile Barrier Concrete Monitoring 3.5.1-23 A (External) of Material (Spalling, Scaling) (T-04)

Outdoor Program

SBK-L-17 1SS I Enclosure 2/ Page 232 U. S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Ag ing Management Evaluation

,., , 111'1: 11:1T , , '1:1 11 t , 'I' t* ,,JF111

' , ' 1. Agmg I . , Table ** 11 !I11~ I! 11 'I 1

ii 1NU REG 1ao1 ' 'I**

111:1.

, "I Intended Aging Effect Requi ri ng Management

1 Note 1,:

Compo ~ ent Type 1: 11* Material ,1:1.1 *1 Environment 3.X. 1 1

Function *t *I Management Vol. 2 Item .I*, '.1:1~r .:r i I :11 *:I* 'j,, Program Item W CS - Concrete - SERVICE Structures Shelter, Air Outdoor Cracking , Loss of Bond , Loss 111.A3-9 WATER PUMPHOUSE in Air Concrete Monitoring 3.5.1-23 A Protection (External) of Material (Spalling, Scaling) (T-04)

Outdoo r Prog ram Structures Monitoring Prog ram , Al kali-Silica Reaction (ASR)

WCS - Concrete - SERVICE Air Outdoor Monitoring lll. A3-2 A, E, WATER PUMPHOUSE in Air Missile Barrier Concrete Expansion and Cracking 3.5. 1-27 (External) Prog ram & (T-03) 517, 519 Outdoor Building Deformation Monitoring Program Structures Mon itoring Program , A lkali-Silica React ion (ASR)

WCS - Concrete - SERVICE Shelter, Air Outdoor Monitori ng lll .A3-2 A, E, WATER PUMPHOUSE in Air Concrete Expansion and Cracking 3.5. 1-27 Protection (External) Program & (T-03) 517, 519 Outdoor Building Deform ation Monitoring Program W CS - Concrete - SERVICE Increase in Porosity and Structures Ai r Outdoor lll. A3-10 WATER PUMPHOUSE in Air Missile Barrier Concrete Permeability, Cracking , Loss Monitoring 3.5.1-24 A (External) (T-06)

Outdoo r of Material (Spalling, Scaling) Program

SBK-L-17155 I Enclosure 2/ Page 233 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation

~l~~~~i :R~~am*~9*;1 .* ! }','* "'*A: ...,. .

1:i; 11:!!' 1 Jh~*~'

1 ,J ..

11:!' '"' gmg " 1 l'E ' NUREG l1aofli, ' 'ii' Table ' ,,.,,*j1. '

1 1.* 1,:,", , .,.:

1:1 '1 1,,.1 M ,,,,*1 ... "* .,,,,h t '"j"*' .1... 11i:1t1t1 11kMan~gem~~t 11f' 'jiv.11, 1t Intended , 1!:

Component Type Material Environment 111

,J 1, n11.1. 3:x.1 w* ,

Note

+" 1I**: , ~1 ,:1, 1r ~fH1

1, Function , *

anagemen * :1r 'I 1 1.i ,, 21 .... ,: . . . ,, 1°**."*I 1 11111' :1 Program ''*'l'l:',*:I* !(i~I! '~~.fTI J111 II j:il ,*

11 1

I . y ':i'I fl:!:,. ' ,. ' 'I: I 1* ':'1** ,**,, 1

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WCS - Concrete - SERVICE Increase in Porosity and Structures Shelter, Air Outdoor llLA3-10 WATER PUMPHOUSE in Air Concrete Permeability, Cracking, Loss Monitoring 3.5. 1-24 A Protection (External) (T-06)

Outdoor of Material (Spalling, Scaling) Program WCS - Concrete - SERVICE Structures Air Outdoor lll.A3-6 WATER PUMPHOUSE in Air Missile Barrier Concrete Loss of Material, Cracking Monitoring 3.5.1-26 A (External) (T-01)

Outdoor Program WCS - Concrete - SERVICE Structures Shelter, Air Outdoor lll.A3-6 WATER PUMPHOUSE in Air Concrete Loss of Material, Cracking Monitoring 3.5.1-26 A Protection (External) (T-0 1)

Outdoor Program WCS - Concrete - SERVICE Structures Structural Raw Water Cracking, Loss of Bond, Loss lll.A3-4 WATER PUMPHOUSE in Raw Concrete Monitoring 3.5.1-31 A, 509 Support (External) of Material (Spalling, Scaling) (T-05)

Water Program Structures Monitoring Program, Alkali-Silica Reaction (ASR)

WCS - Concrete - SERVICE Structural Raw Water Monitoring lll. A3-2 A, E, WATER PUMPHOUSE in Raw Concrete Expansion and Cracking 3.5.1 -27 Support (External) Program & (T-03) 517 , 519 Water Building Deformation Monitoring Program

SBK-L-17 155 I Enclosure 2/ Page 234 U. S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures S ummary of Aging Management Evaluation

,,:1:1., \ ,, . . , Aging 1!l!ilj:, ~ging , E;ff~~~1 1 ~.eq \Jm ng ,11f'l 1

'l'I

1' 11

, 1

Table:' . . 1

14'Mi:i'n ~gement ,., Nu ~~G 1 .... ~" '"'l'i' ,. :1,jiP!X*l : i!* l '11."*',

Intended . , * ',,,I , Managem ent }' 801'1'I '"' " '"' Note Component Type Material , . ,

Function Environment ,.,1:1:k!I:

1

1' :I! 'j':',11 l!I* ,1, , P1rogram1 ,'li'l,l;j!1, 1 1, v o1: 2 1tepi ,* *, H lteni li' q:, 'P:Hii

,1:1 ,

1:i ;:. ' ',J1' * ' l:'il' *1:1 ':!:11111 1

' ,1 I ',,

W CS - Concrete - SERVICE Increase in Porosity and Structures Structural Raw Water 111. A3-7 WATER PUM PHOUSE in Raw Concrete Permeability, Loss of Monitorin g 3,5. 1-32 I A Support (External) (T-02)

W ater Strength Program W CS - Concrete - SERVICE Structures Structura l Raw Water lll.A6-7 WATER PUMPHOUSE in Raw Concrete Loss of Material Mon itoring 3.5.1-45 I E, 511 Support (External) (T-20)

Water Program WCS - Fire Penetration Seal -

Air Indoor Increased Hardness ,

SERVICE WATER COOLI NG Fire Protection Vll. G- 1 Fire Barrier Elastomer Uncontrolled Shrinkage and Loss of 3.3 .1 -6 1 I A TWR including Swgr Rms in Air Program (A-19)

(External) Strength Indoor Uncontrolled WCS - Fire Seal - SERVICE Air Indoor Increased Hardness, Fire Protection Vll. G-1 WATER PUMPHOUSE in Air Fi re Barrier Elastomer Uncontrolled Shrinkage and Loss of 3.3. 1-61 I A Program (A-19)

Indoor Uncontrolled (External) Strength W CS - Penetration Seal -

Increased Hardness, Structures SERVICE WATER COOLI NG Shelter, Air Outdoor Vll. G-2 Elastomer Shrinkage and Loss of Monitoring 3.3.1-6 1 I E, 515 TOWER Including Switchgear Protection (External) (A-20)

Strength Program Rooms in A ir Outdoor WCS - Penetration Seal - Increased Hardness, Structures Shelter, Air Outdoor Vll. G-2 SERVICE WATER Elastomer Shrinkage and Loss of Monitoring 3.3. 1-61 I E, 515 Protection (External) (A-20)

PUM PHOUSE in Air Outdoor Strength Program

SBK-L-17155 I Enclosure 2/ Page 235 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation

. '" '. '"' ll' ,1,11 :1:' 111

., Aging 'I' Table Component Type Intended Material Environment Aging Effect 'Requiring J 1;1 Management

NUREG 1801. I 3.X.1 " Note Function Management Vol. 2 Item Program Item Structures Monitoring WCS - Penetration Sea/ - Program, SERVICE WATER COOLING Shelter, Air Outdoor Building Vll.G-2 Elastomer Separation 3.5.1-60 E,520 TOWER Including Switchgear Protection (External) Deformation (A -20)

Rooms in Air Outdoor Monitoring Program Structures Monitoring Program, WCS - Penetration Sea/ -

Shelter, Air Outdoor Building Vll.G-2 E, SERVICE WATER Elastomer Separation 3.5.1-60 Protection (External} Deformation (A -20) 520 PUMPHOUSE in Air Outdoor Monitoring Program Structures Monitoring WCS - Fire Penetration Seal - Program, Air Indoor SERVICE WATER COOLING Building Vll.G-1 Fire Barrier Elastomer Uncontrolled Separation 3.5.1-60 E, 520 TWR including Swgr Rms in Deformation (A -19)

(External)

Air Indoor Uncontrolled Monitoring Program Structures Monitoring Program, WCS - Fire Seal - SERVICE Air Indoor Building Vll.G-1 WATER PUMPHOUSE in Air Fire Barrier Elastomer Uncontrolled Separation 3.5.1-60 E, 520 Deformation (A-19)

Indoor Uncontrolled (External)

Monitoring Program

SBK-L-171 55 I Enclosure 2/ Page 236 U.S. Nuclear Regulatory Commission Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Standard Notes Note Description A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP.

B Consistent with NUREG-1801 item for component, material , environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP .

C Component is different, but consistent with NUREG-1801 item for material , environment, and aging effect. AMP is consistent with NUREG-1801 AMP.

D Component is different, but consistent with NUREG-1801 item for material , environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.

E Consistent with NUREG-1801 for material , environment and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program.

F Material not in NUREG-1801 for this component.

G Environment not in NUREG-1801 for this component and material.

H Aging effect not in NUREG-1801 for this component, material and environment combination.

I Aging effect in NUREG-1801 for this component, material and environment combination is not applicable.

J Neither the component nor the material and environment combination is evaluated in NUREG-1801 .

501 Not used.

502 Ag ing effect includes "Fretting or Lockup" due to wear.

503 Crevice and pitting will be included along with loss of material-corrosion due to a saltwater atmosphere environment.

504 Fatigue analysis exists and TLAA applies.

505 Built-up roofing is not in GALL; lll.A6-12 is for elastomer-material is similar, aging effect is similar, environment is same , and AMP is Structures Monitoring .

506 Component is cementitious fire proofing/i nsulating material and will exhibit similar aging effects as concrete .

507 Spent Fuel Pool temperature< 60°C (<140° F); water chemistry and temperature will be maintained by the Water Chemistry Program .

508 Cracking, loss of bond, and loss of material (spalling, scaling)/corrosion of embedded steel-is not listed in GALL 111.A.6 as an aging effect for concrete in raw water.

Seabrook manages this effect with Structures Monitoring Program .

509 For aging management purposes , buried , below grade, soil, and ground water/ raw & treated water environments are treated the same.

510 Reduction in concrete anchor capacity is an aging effect that is addressed in LRAM-S UPT.

51 1 At Seabrook Station , Xl.S7 RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" and XI.SS "Masonry Wall Program" are combined under Xl.S6 "Structures Monitoring Program".

512 Raw water in lined & unlined concrete sumps.

513 Seabrook Station will age manage this condition through the Fire Protection Program.

514 Seabrook Station will age manage this condition through the Structures Monitoring Program.

515 Increased hardness, shrinkage , or loss of strength of elastomer seals due to weathering is addressed by GALL only for Fire Barrier seals. Seabrook Station will manage such aging effects for non-Fire Barrier elastomer seals with the Structures Monitoring Program.

516 Seabrook Station Structures Monitoring Program will perform concrete testing and rebar inspection to determine the effects of the aggressive groundwater on the concrete. The concrete testing and the rebar inspection will represent all concrete below grade.

517 After initial identification and determination of the presence of alkali-silica reactivity by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Alkali-Silica Reaction (ASR) Monitoring Program.

SBK-L-17155 I Enclosure 21Page237 U.S. Nuclear Regulatory Commission 519 After initial identification of alkali-silica reaction (A SR) induced building deformation by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Alkali-Silica Reaction (A SR) Monitoring Program and the Building Deformation Monitoring Program.

520 After initial identification of alkali-silica reaction (A SR) induced building deformation affecting plant equipment and components by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Building Deformation Monitoring Program.

Enclosure 3 to SBK-L-17155 Supplement 58 - NextEra Energy Seabrook's revised LRA Appendix A - Updated Final Safety Analysis Report Supplement Table A.3, License Renewa l Commitment List

U.S. Nuclear Regulatory Commission SBK-L- 17155 I Enclosure 3/ Page 2 A.3 LICENSE RENEW AL COMMITMENT LIST UFSAR No . PROGRAM or TOPIC COMMITMENT SCHEDULE LOCATION Provide confirmation and acceptability of the implementation ofMRP-227-A by addressing the plant-

1. PWR Vessel Internals A.2 .1.7 Complete specific Applicant/Licensee Action Items outlined in section 4.2 of the NRC SER.

Enhance the program to include visual inspection for Prior to the period of extended

2. Closed-Cycle Cooling Water cracking, loss of material and fouling when the in-scope A.2.1.12 operation.

systems are opened for maintenance.

Inspection of Overhead Enhance the program to monitor general corrosion on the Heavy Load and Light Load Prior to the period of extended

3. crane and trolley structural components and the effects of A.2.1.13 (Related to Refueling) operation.

wear on the rails in the rail system.

Handling Systems Inspection of Overhead Heavy Load and Light Load Enhance the program to list additional cranes for Prior to the period of extended

4. A.2 .1.1 3 (Related to Refueling) monitoring. operation.

Handling Systems Enhance the program to include an annual air quality test Prior to the period of extended

5. Compressed Air Monitoring requirement for the Diesel Generator compressed air sub A.2. 1.1 4 operation.

system.

Enhance the program to perform visual inspection of Prior to the period of extended

6. Fire Protection A.2. 1.1 5 penetration seals by a fire protection qualified inspector. operation.

Enhance the program to add inspection requirements such as spalling, and loss of material caused by freeze -thaw, Prior to the period of extended

7. Fire Protection A.2. 1.1 5 chemical attack, and reaction with aggregates by qualified operation.

inspector.

- **-- - ------

U.S. Nuclear Regulatory Commission SBK-L- 17155 I Enclosure 3/ Page 3 Enhance the program to include the performance of visual Prior to the period of extended

8. Fire Protection inspection of fire-rated doors by a fire protection qualified A.2. 1.1 5 operation .

inspector.

Enhance the program to include NFPA 25 (2011 Edition) guidance for "where sprinklers have been in place fo r 50 Prior to the period of extended

9. Fire Water System years, they shall be replaced or representative samples A.2 .1.1 6 operation.

from one or more sample areas shall be submitted to a recognized testing laboratory for field service testing" .

Enhance the program to include the performance of Prior to the period of extended

10. Fire Water System periodic flow testing of the fire water system in accordance A.2.1.1 6 operation.

with the guidance ofNFPA 25 (2011 Edition).

Enhance the program to include the performance of periodic visual or volumetric inspection of the internal surface of the fire protection system upon each entry to the system for routine or corrective maintenance to evaluate wall thickness and inner diameter of the fire protection piping ensuring that corrosion product buildup will not result in flow blockage due to fouling. Where surface irregularities are detected, follow-up volumetric Within ten years prior to the

11. Fire Water System examinations are performed. These inspections will be A.2 .1.16 period of extended operation.

documented and trended to determine if a representative number of inspections have been performed prior to the period of extended operation. If a representative number of inspections have not been performed prior to the period of extended operation, focused inspections will be conducted. These inspections will commence during the ten year period prior to the period of extended operation and continue through the period of extended operation

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 4 Enhance the program to include 1) In-scope outdoor tanks, except fire water storage tanks, constructed on soil or concrete, 2) Indoor large volume storage tanks (greater than 100,000 gallons) designed to near-atmospheric internal pressures, sit on concrete or soil, and exposed internally to water, 3) Visual, surface, and volwnetric examinations of the outside and inside surfaces for Within 10 years prior to the

12. Aboveground Steel Tanks A.2.1.17 managing the aging effects of loss of material and cracking, period of extended operation.

4) External visual examinations to monitor degradation of the protective paint or coating, and 5) Inspection of sealant and caulking for degradation by performing visual and tactile examination (manual manipulation) consisting of pressing on the sealant or caulking to detect a reduction in the resiliency and pliability.

Enhance the program to perform exterior inspection of the fire water storage tanks annually for signs of degradation and include an ultrasonic inspection and evaluation of the Within ten years prior to the

13. Fire Water System A.2.1.16 internal bottom surface of the two Fire Protection Water period of extended operation.

Storage Tanks per the guidance provided in NFP A 25 (2011 Edition).

Enhance program to add requirements to 1) sample and analyze new fuel deliveries for biodiesel prior to Prior to the period of extended

14. Fuel Oil Chemistry offloading to the Auxiliary Boiler fuel oil storage tank and A.2. 1.18 operation.

2) periodically sample stored fuel in the Auxiliary Boiler fuel oil storage tank.

Enhance the program to add requirements to check for the presence of water in the Auxiliary Boiler fuel oil storage Prior to the period of extended

15. Fuel Oil Chemistry A.2.1.18 tank at least once per quarter and to remove water as operation.

necessary.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 5 Enhance the program to require draining, cleaning and Prior to the period of extended

16. Fuel Oil Chemistry inspection of the diesel fire pump fuel oil day tanks on a A.2.1.18 operation.

frequency of at least once every ten years.

Enhance the program to require ultrasonic thickness measurement of the tank bottom during the 10-year draining, cleaning and inspection of the Diesel Generator Prior to the period of extended

17. Fuel Oil Chemistry A.2.1.18 fuel oil storage tanks, Diesel Generator fuel oil day tanks, operation.

diesel fire pump fuel oil day tanks and auxiliary boiler fuel oil storage tank.

Enhance the program to specify that all pulled and tested Prior to the period of extended

18. Reactor Vessel Surveillance capsules, unless discarded before August 31, 2000, are A.2.1.19 operation.

placed in storage.

Enhance the program to specify that if plant operations exceed the limitations or bounds defined by the Reactor Vessel Surveillance Program, such as operating at a lower Prior to the period of extended

19. Reactor Vessel Surveillance cold leg temperature or higher fluen ce, the impact of plant A.2.1.19 operation.

operation changes on the extent of Reactor Vessel embrittlement will be evaluated and the NRC will be notified.

Enhance the program as necessary to ensure the appropriate withdrawal schedule for capsules remaining in the vessel such that one capsule will be withdrawn at an outage in which the capsule receives a neutron fluence that Prior to the period of extended

20. Reactor Vessel Surveillance meets the schedule requirements of 10 CFR 50 Appendix A.2.1.19 operation.

H and ASTM E 185-82 and that bounds the 60-year fluence, and the remaining capsule(s) will be removed from the vessel unless determined to provide meaningful metallurgical data.

Enhance the program to ensure that any capsule removed, without the intent to test it, is stored in a manner which Prior to the period of extended

21. Reactor Vessel Surveillance A.2.1.19 maintains it in a condition which would permit its future operation.

use, including during the period of extended operation.

U.S. Nuclear Regulatory Commission SBK-L-17 I 55 I Enclosure 3/ Page 6 Within ten years prior to the

22. One-Time Inspection Implement the One Time Inspection Program. A.2.1.20 period of extended operation.

Implement the Selective Leaching of Materials Program.

The program will include a one-time inspection of selected Selective Leaching of Within five years prior to the

23. components where selective leaching has not been A.2.1.2 1 Materials period of extended operation.

identified and periodic inspections of selected components where selective leaching has been identified.

Implement the Buried Piping And Tanks Inspection Buried Piping And Tanks Program. Within ten years prior to the

24. A.2.1 .22 Inspection period of extended operation One-Time Inspection of Implement the One-Time Inspection of ASME Code Class Within ten years prior to the

25. ASME Code Class 1 Small A.2.1 .23 1 Small Bore-Piping Program. period of extended operation.

Bore-Piping Enhance the program to specifically address the scope of the program, relevant degradation mechanisms and effects External Surfaces Prior to the period of extended

26. of interest, the refueling outage inspection frequency, the A.2.1.24 Monitoring operation.

training requirements for inspectors and the required periodic reviews to determine program effectiveness.

Inspection of Internal Surfaces in Miscellaneous Implement the Inspection of Internal Surfaces in Prior to the period of extended

27. A.2.1.25 Piping and Ducting Miscellaneous Piping and Ducting Components Program. operation.

Components Enhance the program to add required equipment, lube oil Prior to the period of extended

28. Lubricating Oil Analysis analysis required, sampling frequency, and periodic oil A.2.1 .26 operation.

changes.

Enhance the program to sample the oil for the Reactor Prior to the period of extended

29. Lubricating Oil Analysis A.2.1.26 Coolant pump oil collection tanks . operation.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 7 Enhance the program to require the performance of a one-time ultrasonic thickness measurement of the lower portion Prior to the period of extended

30. Lubricating Oil Analysis A.2.1.26 of the Reactor Coolant pump oil collection tanks prior to operation.

the period of extended operation.

ASME Section XI, Enhance procedure to include the definition of Prior to the period of extended

31. A.2.1.28 Subsection IWL "Responsible Engineer". operation.

Enhance procedure to add the aging effects, additional Structures Monitoring Prior to the period of extended

32. locations, inspection frequency and ultrasonic test A.2.1 .31 Program operation.

requirements.

Enhance procedure to include inspection of opportunity Structures Monitoring Prior to the period of extended

33. when planning excavation work that would expose A.2.1.31 Program operation.

inaccessible concrete.

Electrical Cables and Connections Not Subject to Implement the Electrical Cables and Connections Not Prior to the period of extended

34. 10 CFR 50.49 Subject to 10 CFR 50.49 Environmental Qualification A.2 .1.32 operation.

Environmental Qualification Requirements program.

Requirements Electrical Cables and Connections Not Subject to Implement the Electrical Cables and Connections Not 10 CFR 50.49 Prior to the period of extended

35. Subject to 10 CFR 50.49 Environmental Qualification A.2 .1.33 Environmental Qualification operation.

Requirements Used in Instrumentation Circuits program.

Requirements Used in Instrumentation Circuits Inaccessible Power Cables Implement the Inaccessible Power Cables Not Subject to Not Subject to 10 CFR 50.49 Prior to the period of extended

36. 10 CFR 50.49 Environmental Qualification Requirements A.2. 1.34 Environmental Qualification operation.

program.

Requirements Prior to the period of extended

37. Metal Enclosed Bus Implement the Metal Enclosed Bus program. A.2 .1.35 operation.

U.S. Nuclear Regulatory Commission SBK-L- l 71SS I Enclosure 3/ Page 8 Prior to the period of extended

38. Fuse Holders Implement the Fuse Holders program. A.2.1.36 operation.

Electrical Cable Connections Implement the Electrical Cable Connections Not Subject to Not Subject to 10 CFR S0.49 Prior to the period of extended

39. 10 CFR S0.49 Environmental Qualification Requirements A.2.1.37 Environmental Qualification operation.

program.

Requirements Prior to the period of extended

40. 34S KV SF6 Bus Implement the 34S KV SF6 Bus program. A.2 .2.1 operation.

Enhance the program to include additional transients Metal Fatigue of Reactor Prior to the period of extended

41. beyond those defined in the Technical Specifications and A.2.3. l Coolant Pressure Boundary operation.

UFSAR.

Enhance the program to implement a software program, to Metal Fatigue of Reactor Prior to the period of extended

42. count transients to monitor cumulative usage on selected A.2 .3.1 Coolant Pressure Boundary operation.

components.

The updated analyses will be Pressure - Temperature Seabrook Station will submit updates to the P-T curves and submitted at the appropriate time Limits, including Low

43. L TOP limits to the NRC at the appropriate time to comply A.2.4.1.4 to comply with l 0 CFR SO Temperature Overpressure with 10 CFR SO Appendix G. Appendix G, Fracture Toughness Protection Limits Requirements.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 9 NextEra Seabrook will perform a review of design basis ASME Class 1 component fatigue evaluations to determine whether the NUREG/CR-6260-based components that have been evaluated for the effects of the reactor coolant environment on fatigue usage are the limiting components for the Seabrook plant configuration. If more limiting components are identified, the most limiting component will be evaluated for the effects of the reactor coolant environment on fatigue usage. If the limiting location identified consists of nickel alloy, the environmentally-assisted fatigue calculation for nickel alloy will be perfonned using the rules ofNUREG/CR-6909.

(1) Consistent with the Metal Fatigue of Reactor Coolant Pressure Boundary Program Seabrook Station will update the fatigue usage calculations using refined fatigue analyses, if necessary, to determine acceptable CUFs (i.e.,

less than 1.0) when accounting for the effects of the reactor water environment. This includes applying the appropriate Environmentally-Assisted At least two years prior to the

44. Fen factors to valid CUFs determined from an existing A.2.4.2.3 Fatigue Analyses (TLAA) period of extended operation.

fatigue analysis valid for the period of extended operation or from an analysis using an NRC-approved version of the ASME code or NRC-approved alternative (e.g., NRC-approved code case).

(2) If acceptable CUFs cannot be demonstrated for all the selected locations, then additional plant-specific locations will be evaluated. For the additional plant-specific locations, if CUF, including environmental effects is greater than 1.0, then Corrective Actions will be initiated, in accordance with the Metal Fatigue of Reactor Coolant Pressure !3oundary Program, B.2.3 .1. Corrective Actions will include inspection, repair, or replacement of the affected locations before exceeding a CUF of 1.0 or the effects of fatigue will be managed by an inspection program that has been reviewed and approved by the NRC (e.g., periodic non-destructive examination of the affected locations at inspection intervals to be determined by a method accepted by the NRC).

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 10 NextEra will obtain additional cores in the vicinity oftffi:ee 20% of the extensometers and perform modulus testing. Using these test results, NextEra will determine At least ;?; 5 years prior to the Alkali-Silica Reaction the change in through-thickness expansion since period of extended operation

45. (ASR) Monitoring Program installation of the extensometers and compare it to change (initial study) and 10 years determined from extensometer readings. Consistency th ereaf ter (follo w-up study).

between these results will provide additional corroboration of the methodology in MPR-4153.

Protective Coating Enhance the program by designating and qualifying an Prior to the period of extended

46. A.2.1.38 Monitoring and Maintenance Inspector Coordinator and an Inspection Results Evaluator. operation.

Enhance the program by including, "Instruments and Equipment needed for inspection may include, but not be Protective Coating limited to, flashlight, spotlights, marker pen, mirror, Prior to the period of extended

47. A.2.1.38 Monitoring and Maintenance measuring tape, magnifier, binoculars, camera with or operation.

without wide angle lens, and self sealing polyethylene sample bags."

Protective Coating Enhance the program to include a review of the previous Prior to the period of extended 48 . A.2.1.38 Monitoring and Maintenance two monitoring reports. operation.

Enhance the program to require that the inspection report is Protective Coating to be evaluated by the responsible evaluation personnel, Prior to the period of extended 49 . A.2.1.38 Monitoring and Maintenance who is to prepare a summary of findings and operation.

recommendations for future surveillance or repair.

Baseline inspections were completed during OR16. Repeat Perform UT of the accessible areas of the containment ASME Section XI, containment liner UT thickness

50. liner plate in the vicinity of the moisture barrier for loss of A.2.1.27 Subsection IWE examinations at intervals of no material. Perform opportunistic UT of inaccessible areas.

more than five (5) refueling outages.

51. Number Not Used

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 11 Implement measures to maintain the exterior surface of the ASME Section XI,

52. Contairunent Structure, from elevation -30 feet to +20 feet, A.2.1.28 Complete Subsection IWL in a dewatered state.

Replace the spare reactor head closure stud(s)

Prior to the period of extended

53. Reactor Head Closure Studs manufactured from the bar that has a yield strength> 150 A.2.1.3 operation.

ksi with ones that do not exceed 150 ksi.

U. S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 12 NextEra will address the potential for cracking of the primary to secondary pressure boundary due to PWSCC of tube-to-tubesheet welds using one of the following two options:

1) Perform a one-time inspection of a representative sample oftube-to-tubesheet welds in all steam generators to determine if PWSCC cracking is present and, if cracking is identified, resolve the condition through engineering evaluation justifying continued operation or repair the condition, as appropriate, and establish an ongoing monitoring program to perfonn routine tube-to-tubesheet Steam Generator Tube

54. weld inspections for the remaining life of the steam A.2.1.10 Complete Integrity generators, or

2) Perform an analytical evaluation showing that the structural integrity of the steam generator tube-to-tubesheet interface is adequately maintaining the pressure boundary in the presence oftube-to-tubesheet weld cracking, or redefining the pressure boundary in which the tube-to-tubesheet weld is no longer included and, therefore, is not required for reactor coolant pressure boundary function.

The redefinition of the reactor coolant pressure boundary must be approved by the NRC as part of a license amendment request.

55. Number Not Used ~

Revise the station program documents to reflect the EPRI Closed-Cycle Cooling Water Prior to the period of extended

56. Guideline operating ranges and Action Level values for A.2.1.12 System operation.

hydrazine and sulfates.

Revise the station program documents to reflect the EPRI Closed-Cycle Cooling Water Prior to the period of extended

57. Guideline operating ranges and Action Level values for A.2.1.12 System operation.

Diesel Generator Cooling Water Jacket pH.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 13 Update Technical Requirement Program 5 .1, (Diesel Fuel Oil Testing Program) ASTM standards to ASTM D2709- Prior to the period of extended

58. Fuel Oil Chemistry A.2.1.1 8 96 and ASTM D4057-95 required by the GALL XI.M30 operation.

Rev 1 The Nickel Alloy Aging Nozzles and Penetrations program Nickel Alloy Nozzles and Prior to the period of extended

59. will implement applicable Bulletins, Generic Letters, and A.2.2.3 Penetrations operation.

staff accepted industry guidelines.

Implement the design change replacing the buried Buried Piping and Tanks Prior to the period of extended

60. Auxiliary Boiler supply piping with a pipe-within-pipe A.2.1.22 Inspection operation.

configuration with leak detection capability.

Replace the flexible hoses associated with the Diesel Compressed Air Monitoring Within ten years prior to the

61. Generator air compressors on a frequency of every 10 A.2.1.1 4 Program period of extended operation.

years.

Enhance the program to include a statement that sampling Prior to the period of extended 62 . Water Chemistry frequencies are increased when chemistry action levels are A.2 .1.2 operation.

exceeded.

Ensure that the quarterly CVCS Charging Pump testing is continued during the PEO. Additionally, add a precaution to the test procedure to state that an increase in the eves Prior to the period of extended

63. Flow Induced Erosion A.2. 1.2 Charging Pump mini flow above the acceptance criteria operation.

may be indicative of erosion of the mini flow orifice as described in LER 50-275/94-023 .

Soil analysis shall be performed prior to entering the period of extended operation to determine the corrosivity of the soil in the vicinity of non-cathodically protected Within ten years prior to the

64. Buried Piping and Tanks A.2.1.22 steel pipe within the scope of this program. If the initial period of extended operation.

Inspection analysis shows the soil to be non-corrosive, this analysis will be re-performed every ten years thereafter.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 31 Page 14 Implement measures to ensure that the movable incore Prior to the period of extended

65. Flux Thimble Tube detectors are not returned to service during the period of NIA operation. - In Progress extended operation.

NextEra will perfonn an integrated review of expansion trends at Seabrook Station by conducting a periodic assessment of ASR expansion behavior to confirm that the MPR/FSEL large-scale test programs remain applicable to plant structures. This review will include the following specific considerations:

Review of all cores removed to date for trends of any indications of mid-plane cracking.

Comparison of in-plane expansion to through- At least 5 years prior to the period Alkali-Silica Reaction thickness expansion of all monitored points by

66. A.2.1.31.A of extended operation and every (ASR) Monitoring Program plotting these data on a graph of min-plane expansion versus through-thickness expansion. 10 years thereafter.

Comparison of in-plane expansions, volumetric expansions, and through-thickness expansions recorded to date to the limits from the MPR/FSEL large-scale test programs and check of margin for future expansion. Alse, the eale1:tlatee! '>'ei1::1metfie ei1:paHsi8f1 ""'ill fie eempafee! te the faHge efisep,*ee!

in the fieam test prngrnms aHEl mafgiH fer future ei<paHsieH .,,,,ill fie eheel<eEl .

Perform one shallow core bore in an area that was continuously wetted from borated water to be examined for concrete degradation and also expose rebar to detect any Structures Monitoring 67 . degradation such as loss of material. The removed core A.2.1.31 Complete Program will also be subjected to petrographic examination for concrete degradation due to ASR per ASTM Standard Practice C856.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 15 Structures Monitoring Perform sampling at the leak off collection points for 68 . A.2.1 .3 1 Complete Program chlorides, sulfates, pH and iron once every three months.

Replace the Diesel Generator Heat Exchanger Plastisol Open-Cycle Cooling Water

69. PVC lined Service Water piping with piping fabricated A.2.1.11 Complete System from AL6XN material.

Inspect the piping downstream of CC-V-444 and CC-V-446 to determine whether the loss of material due to Closed-Cycle Cooling Water Within ten years prior to the

70. cavitation induced erosion has been eliminated or whether A.2.1.12 System period of extended operation.

this remains an issue in the primary component cooling water system.

NextEra has completed testing at the University of Texas Ferguson Structural Engineering Laboratory which demonstrates the parameters being monitored and Alkali-Silica Reaction acceptance criteria used are appropriate to manage the (ASR) Monitoring Program I effects of ASR. A.2.1.3 lA Prior to the period of extended

71. Building Deformation operation.

A.2.l.31B Monitoring Program NextEra !implement the Alkali-Silica Reaction (ASR)

Monitoring Program and Building Deformation Monitoring Program described in B.2 .1.3 lA and B.2.1.3 lB of the License Renewal Application.

Enhance the program to include management of wall Prior to the period of extended

72. Flow-Accelerated Corrosion A.2.1.8 thinning caused by mechanisms other than FAC. operation.

Enhance the program to include performance of focused Inspection of Internal examinations to provide a representative sample of20%, or Surfaces in Miscellaneous

73. a maximum of25, of each identified material, A.2.1.25 Prior to the period of extended Piping and Ducting environment, and aging effect combinations during each operation.

Components 10 year period in the period of extended operation.

U.S. Nuclear Regulatory Commission SBK-L-17155 / Enclosure 3/ Page 16 Enhance the program to perform sprinkler inspections annually per the guidance provided in NFP A 25 (2011 Edition). Inspection will ensure that sprinklers are free of corrosion, foreign materials, paint, and physical damage Prior to the period of extended

74. Fire Water System and installed in the proper orientation (e.g., upright, A.2.1.16 operation.

pendant, or sidewall). Any sprinkler that is painted, corroded, damaged, loaded, or in the improper orientation, and any glass bulb sprinkler where the bulb has emptied, will be evaluated for replacement.

Enhance the program to a) conduct an inspection of piping and branch line conditions every 5 years by opening a flushing connection at the end of one main and by removing a sprinkler toward the end of one branch line for the purpose of inspecting for the presence of foreign organic and inorganic material per the guidance provided in NFPA 25 (2011 Edition) and b) If the presence of sufficient foreign organic or inorganic material to obstruct Prior to the period of extended

75. Fire Water System A.2.1.16 pipe or sprinklers is detected during pipe inspections, the operation.

material will be removed and its source is determined and corrected.

In buildings having multiple wet pipe systems, every other system shall have an internal inspection of piping every 5 years as described in NFPA 25 (2011 Edition), Section 14.2.2.

Enhance the Program to conduct the following activities annually per the guidance provided in NFPA 25 (2011 Edition). Prior to the period of extended

76. Fire Water System A.2.1.16

main drain tests operation.

deluge valve trip tests

fire water storage tank exterior surface inspections

U.S . Nuclear Regulatory Commission SBK-L-17 I 55 I Enclosure 3/ Page 17 The Fire Water System Program will be enhanced to include the following requirements related to the main drain testing per the guidance provided in NFPA 25 (2011 Edition).

The requirement that ifthere is a 10 percent reduction Prior to the period of extended

77. Fire Water System A.2.1.16 in full flow pressure when compared to the original operation.

acceptance tests or previously performed tests, the cause of the reduction shall be identified and corrected if necessary.

Recording the time taken for the supply water pressure to return to the original static (nonflowing) pressure.

Enhance the program to include periodic inspections of in-scope insulated components for possible corrosion under insulation. A sample of outdoor component surfaces that External Surfaces are insulated and a sample of indoor insulated components Prior to the period of extended 78 . A.2.1.24 Monitoring exposed to condensation (due to the in-scope component operation.

being operated below the dew point), will be periodically inspected every 10 years during the period of extended operation.

Enhance the program to include visual inspection of Open-Cycle Cooling Water internal coatings/linings for loss of coating integrity. Within 10 years prior to the

79. A.2.1.11 System period of extended operation.

Enhance the program to include visual inspection of internal coatings/linings for loss of coating integrity. Within 10 years prior to the

80. Fire Water System A.2. 1.1 6 period of extended operation.

Enhance the program to include visual inspection of internal coatings/linings for loss of coating integrity. Within 10 years prior to the

81. Fuel Oil Chemistry A.2. 1.1 8 period of extended operation.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 18 Inspection of Internal Enhance the program to include visual inspection of Surfaces in Miscellaneous internal coatings/linings for loss of coating integrity. Within 10 years prior to the

82. A.2 .1.25 Piping and Ducting period of extended operation.

Components Enhance the ASR AMP to install extensometers in all Tier 3 areas of two dimensional reinforced structures to monitor expansion due to alkali-silica reaction in the out-Alkali-Silica Reaction of-plane direction.

83. A.2.1.31A Complete Monitoring Monitoring expansion in the out-of-plane direction will commence upon installation of the extensometers and continue on a six month frequency through the period of extended operation.

Evaluate the acceptability of inaccessible areas for ASME Section XI, Prior to the period of extended

84. structures within the scope of ASME Section XI, A.2.1.28 Subsection IWL operation.

Subsection IWL Program.

Enhance the program to perform additional tests and inspections on the Fire Water Storage Tanks as specified in 85 . Section 9.2.7 ofNFPA 25 (2011 Edition) in the event that Prior to the period of extended Fire Water System A.2.1.16 it is required by Section 9.2.6.4, which states "Steel tanks operation.

exhibiting signs of interior pitting, corrosion, or failure of coating shall be tested in accordance with 9.2.7."

86. Enhance the program to include disassembly, inspection, Prior to the period of extended Fire Water System A.2.1.16 and cleaning of the mainline strainers every 5 years. operation.

Increase the frequency of the Open Head Spray Nozzle Air 87 . Flow Test from every 3 years to every refueling outage to

Prior to the period of extended Fire Water System A.2.1.16 be consistent with LR-ISG-2012-02, AMP XI.M27, Table operation.

4a.

U.S. Nuclear Regulatory Commission SBK-L-17 I 55 I Enclosure 3/ Page 19 Enhance the program to include verification that a) the drain holes associated with the transformer deluge system are draining to ensure complete drainage of the system after each test, b) the deluge system drains and associated

88. Within five years prior to the Fire Water System piping are configured to completely drain the piping, and A.2.1.16 period of extended operation.

c) normally-dry piping that could have been wetted by inadvertent system actuations or those that occur after a fire are restored to a dry state as part of the suppression system restoration.

Incorporate Coating Service Level III requirements into the Inspection of Internal RCP Motor Refurbishment Specification for the internal Surfaces in Miscellaneous painting of the motor upper bearing coolers and motor air Prior to the period of extended

89. A.2 .1.25 Piping and Ducting coolers. All four RCP motors will be refurbished and operation.

Components replaced using the Coating Service Level III requirements prior to entering the period of extended operation.

Implement the PWR Vessel Internals Program. The program will be implemented in accordance with MRP-Prior to the period of extended PWR Vessel Internals 227-A (Pressurized Water Reactor Internals Inspection and A.2.1.7 90 . operation Evaluation Guidelines) and NEI 03 -08 (Guideline for the Management of Materials Issues).

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 20 Implement the Building Deformation Monitoring Program Enhance the Structures Monitoring Program to require structural evaluations be performed on buildings and components affected by deformation as necessary to ensure that the structural function is maintained. Evaluations of structures will validate structural performance against the design basis, and may use results from the large-scale test programs, as appropriate. Evaluations for structural deformation will also consider the impact to functionality of affected systems and components (e.g., conduit expansion joints). NextEra will evaluate the specific circumstances against the design basis of the affected system or component.

Enhance the Building Defonnation AMP to include Building Deformation additional parameters to be monitored based on the results A.2.l.31B 91 March 15, 2020 Monitoring of the CEB Root Cause, Structural Evaluation and walk downs. Additional parameters monitored will include:

alignment of ducting, conduit, and piping; seal integrity; laser target measurements; key seismic gap measurements; and additional instrumentation.

Develop a design standard to implement Aging Management Program B.2.1.3 lB Building Deformation, Program Element 3 - Parameters Monitored/Inspected. The design standard will clarify the deformation evaluation process and provide an auditable format to assess it. The design standard will include steps for each of the three evaluation stages that include parameters monitored, basis for why the parameter is monitored, and conditions that prompts action for the subsequent step.

Enclosure 4 to SBK-L-17155 NextEra Energy Seabrook, Application for Withholding Proprietary Information from Public Disclosure and Affidavit

U.S. Nuclear Regulatory Comm ission SBK-L-171 55 I Enclosure 4/ Page 2 SEABROOK NextEra Energy Seabrook, LLC AFFIDAVIT IN SUPPORT OF APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE County of Rockingham )

)

State of New Hampshire )

I, Eric McCaiiney, being duly sworn according to law, depose and state the following:

(1) I am the Regional Vice President - No1ihern Region ofNextEra Energy Seabrook, LLC (NextEra Energy Seabrook), and have been delegated the function ofreviewing the information described in paragraph (3) which is sought to be withheld, and have been authorized to apply for its withholding.

(2) I am making this Affidavit in conjunction with NextEra Energy Seabrook's "Application for Withholding Proprietary Information from Public Disclosure" accompanying this Affidavit and in conformance with the provisions of 10 CFR Section 2.390.

(3) The information sought to be withheld is contained in Enclosure 1 of NextEra Energy Seabrook's letter SBK-L-17155, Eric McCartney (NextEra Energy Seabrook) to U.S. Nuclear Regulatory Commission, entitled "Supplement 58 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Building Deformation Analyses Related To Concrete Alkali-Silica Reaction."

(4) The information sought to be withheld is considered to be proprietary and confidential commercial information because alkali-silica reaction (ASR) is a newly-identified phenomenon at domestic nuclear plants. The information requested to be withheld is the result of several years of intensive NextEra Energy Seabrook effort and the expenditure of a considerable sum of money. This information may be marketable in the event nuclear facilities or other regulated facilities identify the presence of ASR. In order for potential customers to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended. The extent to which this information is available to potential customers diminishes NextEra Energy Seabrook's ability to sell products and services involving the use of the information. Thus, public disclosure of the information sought to be withheld is likely to cause substantial harm to NextEra

U. S. Nuc lear Reg ulatory Commi ssion SBK-L- 17155 I Enclosure 4/ Page 3 Energy Seabrook's competitive position and NextEra Energy Seabrook has a rational basis for considering this information to be confidential commercial information.

(5) The information sought to be withheld is being submitted to the NRC in confidence.

(6) The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by NextEra Energy Seabrook, has not been disclosed publicly, and not been made available in public sources.

(7) The information is of a sort customarily held in confidence by NextEra Energy Seabrook, and is in fact so held.

(8) All disclosures to third parties, including any required transmittals to the NRC, have been or will be pursuant to regulatory provisions and/or confidentiality agreements that provide for maintaining the information in confidence.

I declare that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief. Further, the affiant sayeth not.

Regional Vice President - Northern Region NextEra Energy Seabrook, LLC 626 Lafayette Road Seabrook, New Hampshire 03874 Subscribed and sworn to before me this ~ 12 O day of October, 2017.

QAwbw~

Notary Public My commission expires 3/rt;/1,.,7__

v t e Letter Sequence Response to RAI
CAC:MF8260, (Approved, Closed) EPID:L-2016-LLA-0007, Enclosure 3 - Licensee'S Presentation-Seabrook Station, License Amendment Request 16-03 ASR Structural Evaluation Methodology (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance, Acceptance Administration Withholding Request Acceptance Meeting, Meeting, Meeting, Meeting, Meeting Questions 4 August 2017 11 October 2017 14 December 2017 Answers 17 November 2017 3 October 2017 3 October 2017 11 December 2017 7 June 2018 Results Approval, Approval Other: ML17199T383, ML17283A040, ML18135A046, ML18204A242, ML18353A954, ML19044A768, ML19058A216, NRC-2019-0075, Federal Register Notice - License Amendment; Issuance (CAC No. MF8260; EPID L-2016-LLA-0007), SBK-L-16013, License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program, SBK-L-16181, License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program, SBK-L-17101, Update to Reply to a Notice of Violation; EA-16-101 Corrective Action Plan
MONTHYEAR2018-12-14 [Table View]

SBK-L-17155, Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction

Text

References:

Enclosures:

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