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Seabrook, 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)
	v • d • e

Enclosure 1 to this Letter Contains Proprietary Information Withhold Enclosure 1 from Public Disclosure in Accordance with 10 CFR 2.390 October 03, 2017 10 CFR 54 Docket No. 50-443 SBK-L-17155 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station NFXTera SEABROOK 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 ML 101590099). 2. NRC, "Request for Additional Information for the Review of the Seabrook Station License Renewal Application (CAC NO. ME4028)," March 29, 2017 (Accession Number ML 17088A614). In Reference 1, NextEra Energy Seabrook, LLC (NextEra Energy Seabrook) submitted an application 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 application related to Alkali-Silica Reaction (ASR) and Building Deformation Monitoring Programs. Enclosure 1 provides NextEra Energy Seabrook's response to the NRC's Request for Additional Information (RAI) concerning the Alkali-Silica Reaction and Building 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-17155/ Page 2 Enclosure 2 provides the revised License Renewal Application, Section 3.5, as referenced in the response to RAI 3.5-A1-1: AMR within Enclosure 1. 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 Commission and addressing the considerations 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 version of this letter and revised Alkali-Silica Reaction Monitoring Program Aging Management Plan A.2.1.31.A will be submitted under separate cover by November 3, 2017. This letter contains two revised Commitments (45 and 66). Enclosure 3 provides the revised LRA Appendix A -Updated Final Safety Analysis Report Supplement Table A.3, License Renewal Commitment List. If there are any questions or additional information is needed, please contact Mr. Edward J. Carley, Engineering Supervisor -License Renewal, at (603) 773-7957. If you have any questions regarding 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 , 2017. Sincerely, NextEra Energy Seabrook, LLC hem Region U.S. Nuclear Regulatory Commission SBK-L-17155/ Page 3

Enclosures:

Enclosure 1 -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 (Proprietary) Enclosure 2 -Seabrook Station License Renewal Application, Section 3.5 Enclosure 3 -LRA Appendix A -Final Safety Report Supplement Table A.3, License Renewal Commitment List Updated to Reflect Changes to Date Enclosure 4 -NextEra Energy Seabrook, Application for Withholding Proprietary Information from Public Disclosure and Affidavit cc: D. H. Dorman J.C. Poole P. C. Cataldo L. M. James Mr. Perry Plummer NRC Region I Administrator NRC Project Manager NRC Senior Resident Inspector NRC Project Manager, License Renewal 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 to SBK-L-17155 Seabrook Station License Renewal Application, Section 3.5 U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 2/ Page 2 Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components Item Component Aging Management Number Aging Effect I Mechanism Further Evaluation Program Recommended PWR 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 walls, dome, basemat, inaccessible concrete areas examination of representative samples of environment is aggressive ring girder, buttresses. due to aggressive chemical below-grade concrete and periodic monitoring containment (as attack, and corrosion of of groundwater if environment is non-applicable) embedded steel aggressive. A plant-specific program is to be evaluated if environment is aggressive. Discussion :* Seabrook manages accessible and inaccessible concrete components due to corrosion of embedded steel with the ASME Section XI, Subsection IWL Program, and B.2.1.28. Aggressive chemical attack is an applicable aging effect requiring management for Seabrook. Further evaluation is provided in LRA Subsection 3.5.2.2.1.1. The Structures Monitoring Program. B.2.1.31, will perform concrete testing and rebar inspection to determine the effects of the ag.gressive groundwater on the concrete. The concrete 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 . IFi!I ' ,,:11 :1:111: I' ' Item ,, ,Agipg Managerre!lt Further Evaluation Component Aging Effect I Mechanism !: 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 increased stress levels from watering system is relied upon for control of scope of the applicant's settlement settlement, then the licensee is to ensure structures monitoring proper functioning of the de-watering system program or a de-watering through the period of extended operation. system is relied upon 3.5.1-3 Concrete elements: Reduction in foundation Structures Monitoring Program. If a de-Yes, if not within the foundation, strength, cracking, differential watering system is relied upon to control scope of the applicant's subfoundation settlement due to erosion of erosion of cement from porous concrete structures monitoring porous concrete subfoundations, then the licensee is to ensure program or a de-watering subfoundation proper functioning of the de-watering system system is relied upon through the period of extended operation Discussion Seabrook does not rely on a dewatering system for control of settlement. Cracking and distortion due to increased stress levels from settlement is not an aging effect requiring 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. Reduction in foundation strength, cracking, and differential settlement due to erosion of porous concrete subfoundations is not an aging effect requiring management for the Seabrook Containment Structure. Further evaluation is provided in LRA Subsection 3.5.2.2.1.2.

SBK-L-17155 I Enclosure 2/ Page 4 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components t*; ,.f,1, :1: 'I' :I!* 1* "' Item Component Aging Effect I Mechanism Aging '!!I' Further Evaluation Number Program ,ii* *i'l 1+ . ' , 3.5. 1-4 Concrete elements: Reduction of strength and Plant-specific Yes, plant-specific if dome, wall, basemat, modulus due to elevated temperature limits are ring girder, buttresses, temperature exceeded containment, concrete fill-in annulus (as applicable) 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 liner, liner anchors, general, pitting, and crevice significant for inaccessible integral attachments corrosion areas 3.5.1-7 Prestressed Loss of prestress due to TLAA evaluated in accordance with 10 CFR Yes, TLAA containment tendons relaxation, shrinkage, creep, 54.21 (c) and elevated temperature l*l'.1*1 !Ii Discussion ' This item is not applicable to Seabrook. No containment components exceed the specified temperature thresholds. Further evaluation is provided in LRA Subsection 3.5.2.2.1.3. Consistent with NUREG-1801. 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. This item is not applicable to Seabrook. 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 " 1:1 ,, .,, I ' t Item l*I ,,, Aging Management Further Evaluation Number '*1Component Aging Effect I Mechanism Program Recommended 1;1 I '*I' I.I Iii 3.5.1-8 BWRonly. 3.5.1-9 Steel, stainless steel Cumulative fatigue damage TLAA evaluated in accordance with 1 O CFR Yes, TLAA elements, dissimilar (CLB fatigue analysis exists) 54.21 (c) metal welds: penetration sleeves, penetration bellows; suppression pool shell, unbraced down comers 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 penetration sleeves, corrosion cracking additional appropriate examinations I to be evaluated penetration bellows, evaluations for bellows assemblies and dissimilar metal welds dissimilar metal welds 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 elements, dissimilar loading supplemented to detect fine cracks to be evaluated metal welds: penetration sleeves, penetration bellows; suppression pool shell, unbraced downcomers 3.5.1-13 BWRonly. , H . ,,, ,+,:i:ii'JI; Discussion .l*I Consistent with NUREG-1801 for Seabrook containment penetrations that experience significant cyclic loading. Further evaluation is provided in LRA Subsection 3.5.2.2.1.6. Cracking due to stress corrosion cracking is not an aging effect requiring management for these stainless steel components. Further evaluation is provided in LRA Subsection 3.5.2.2.1.7. This item is not applicable to Seabrook. Cracking due to cyclic loading is not an aging effect requiring management for the Seabrook penetration elements. Further evaluation is provided in LRA Subsection 3.5.2.2.1.8.

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 ., f. I '1 .,. Item *I Aging Management Further Evaluation Number Component Aging Effect I P.rogram Recommended ' 3.5.1-14 Concrete elements: Loss of material (scaling, ISi (IWL) Evaluation is needed for plants that Yes, for inaccessible dome, wall, basemat, cracking, and spalling) due to are located in moderate to severe weathering areas of plants located in ring girder, buttresses, freeze -thaw conditions (weathering index >100 day -moderate to severe containment (as inch/yr) (NUREG-1557) weathering conditions applicable) 'I Discussion I , 1J1;11!i1'1ili Loss of material due to freeze-thaw effects is not an aging effect requiring management for Seabrook. 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 :1; ii" ' I '1111 ,., :i ' '"!"'"'II II ,,, Item Component Aging Effect I Mechanism Aging Management Further Evaluation Number Program Recommended 3.5.1-15 Concrete elements: Increase in porosity ISi (IWL) for accessible areas. None for Yes, if concrete was not walls, dome, basemat, permeability due to leaching inaccessible areas if concrete was constructed constructed as stated for ring girder, buttresses, of calcium hydroxide; in accordance with the recommendations of inaccessible areas. containment, concrete cracking due to expansion ACI 201.2R fill-in annulus (as and reaction with aggregate applicable) ,,,,., .,,., . 'i! ,:1:111111*1:1 Discussion +tie AMR Fes<ilts eeAel<iele ttiat eltie le eiq:iaAsieA aAel FeaetieA wi!R a§§Fe§ale is Rel aA a§iA§ Ffl66RaAiSFfl F6f:1tliFiA§ FAaAa§eFAeAI feF !Re eeA!aiAFA6AI S!Ftie!tire at Seal:JFeelc Concrete was constructed equivalent to recommendations in ACI 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 1:1'1111 11'11:111', 11111:1! ll'll11111llt11:1il:i!l'lilil:I !li:I , JI :1:1,11,:j:: Fl Fl ,,.,,. 1:1 *' ii! il'J.111 Item Component Aging Effect I Mechanism Aging Management, ,

Further Evaluation ",. Number Program Recommended 3.5.1-16 Seals, gaskets, and Loss of sealing and leakage ISi (IWE) and 10 CFR Part 50, Appendix J No moisture barriers through containment due to deterioration of joint seals, gaskets, and moisture barriers (caulking, flashing, and other sealants) :11*::11111:1 ,,:J'li1 i'il:1:r1,111r111,1, .1: y1.111, Discussion 1*; 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 evaluation is provided in LRA Subsection 3.5.2.2. 1. 10. Consistent with NUREG-1801. Seabrook manages loss of sealing with the ASME 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 therefore Seabrook manages loss of sealing due to ASR with the Building Deformation Monitoring Program, B.2.1.31B.

SBK-L-17155 I Enclosure 2/ Page 9 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components :" !;, I :j:i:JJ '.!: :1:1 :i: Item Component Aging Effect I Mechanism Agi.ng Management Further Evaluation Number Program Recommended 3.5.1-17 Personnel airlock, Loss of leak tightness in 1 O CFR Part 50, Appendix J and plant No equipment hatch and closed position due to Technical Specifications CRD hatch locks, mechanical wear of locks, hinges, and closure hinges, and closure mechanisms mechanisms 3.5.1-18 Steel penetration Loss of material due to ISi (JWE) and 10 CFR Part 50 Appendix J No sleeves and dissimilar general, pitting, and crevice metal welds; personnel corrosion airlock, equipment hatch, and CRD hatch 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 containment: tendons corrosion and anchorage components Safety Related and Other Structures; and Component Supports I *1;1 :Li. I 1:1 1'.l:.l.11:1; Discussion Consistent with NUREG-1801. The 10 CFR 50 Appendix J Program, B.2.1.30, is used to manage loss of leak tightness. Consistent with NUREG-1801. The ASME Section XI, Subsection IWE, B.2.1.27 manages loss of material due to corrosion, 1 O CFR 50 Appendix J Program, B.2.1.30, manages loss of leak tightness. Not Applicable. Seabrook Station does not have prestressed tendons.

SBK-L-17155 I Enclosure 2/ Page 10 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components ,,,,, .. II ..* ,,:, !! w111 1,n!' 11: , 'il'i m111w111:11:1:111:1i1 i'1111i:111'11 n1 1111w11w1 Item 1;, Component Aging Effect I Mechanism Aging Management Further Evaluation *,, Number Program Recommended 3.5.1-23 All Groups except Cracking, loss of bond, and Structures Monitoring Program Yes, if not within the Group 6: interior and loss of material (spalling, scope of the applicant's above grade exterior scaling) due to corrosion of Structures Monitoring concrete embedded steel Program 3.5.1-24 All Groups except Increase in porosity and Structures Monitoring Program Yes, if not within the Group 6: interior and permeability, cracking, loss of scope of the applicant's above grade exterior material (spalling, scaling) Structures Monitoring concrete due to aggressive chemical Program attack 3.5.1-25 All Groups except Loss of material due to Structures Monitoring Program If protective Yes, if not within the Group 6: steel corrosion coatings are relied upon to manage the effects scope of the applicant's components: all of aging, the structures monitoring program is Structures Monitoring structural steel to include provisions to address protective Program coating monitoring and maintenance i:!!l:i;1:l'!*1,i1:J11:,11 ,, '11' .11111: 'IJ' ii'iii! :11 Discussion , Consistent with NUREG-1801. 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. The Seabrook AMR results conclude that the groundwater is aggressive and chemical attack is 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. Consistent with NUREG-1801. Seabrook manages 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' 11:111 l'I li:h i!iii*I* 1'1.l: 1111 j:I :f'I "", lil'.lh1 j:I Item Component Aging Effect I Mechanism Aging Management Further Evaluation Number Program Recommended 3.5.1-26 All Groups except Loss of material (spalling, Structures Monitoring Program Evaluation is Yes, if not within the Group 6: accessible and scaling) and cracking due to needed for plants that are located in moderate scope of the applicant's inaccessible concrete: freeze-thaw to severe weathering conditions (weathering Structures Monitoring foundation index >100 day-inch/yr) (NUREG-1557) Program or for inaccessible areas of plants located in moderate to severe weathering conditions *ijlj 1;1!1111111: ;1.111; :1 *M1,: Discussion Consistent with NUREG-1801. Seabrook manages Loss of material (spalling, scaling) and cracking due to freeze-thaw with the Structures Monitoring Program, B.2.1.31. Further evaluation is provided in LRA Subsection 3.5.2.2.2.1, Item 4.

SBK-L-17155 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 Evaluation Number Component Aging Effect I Mechanism ' 1 , 1*1 Recommended ' 3.5.1-27 All Groups except Cracking due to expansion Structures Monitoring Program. None for Yes, if not within the Group 6: accessible and due to reaction with inaccessible areas if concrete was constructed scope of the applicant's inaccessible interior I aggregates in accordance with the recommendations in Structures Monitoring exterior concrete AC! 201.2R-77 Program or concrete was not constructed as stated for inaccessible areas ,, Discussiop +Ris iteFA is Aet a1313lieasle te Seasreelc +Re Seasreel' .O.MR Fes\ollts eeAel\o!Ele !Rat FeaetieA wi!R a§§Fe§ates is Ae! si§AifieaA! aAEl !Re eeAoFe!e was oeAstrneteEl oeAsis!eA! wi!R I The recommendations of AC! 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). NeAe!Reless, all Seasreel' Stf1:16l1:1Fal 69FAJ39AeA!S a1313lioasle te !Ris iteFA will se FAeAiteFeEl sy !Re S!F1:10!1:1Fes MeAiteFiA§ Pre§FaFA, Cracking due to expansion and reaction with aggregates is monitored by the Structures Monitoring Program, B.2.1.31, the Alkali-Silica Reaction (ASR) Monitoring 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.: ,, !111111-i'l Iii' '*'"* .,,.1H. ,/11*' Item Component ., Aging Effect I Mechanism Aging Management I*'* Further Evaluation l'I 11'1 Number Program Recommended 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 increased stress levels from watering system is relied upon for control of scope of the applicant's settlement settlement, then the licensee is to ensure Structures Monitoring proper functioning of the de-watering system Program or a de-watering through the period of extended operation system is relied upon 3.5.1-29 Groups 1-3, 5-9: Reduction in foundation Structures Monitoring Program If a de-Yes, if not within the foundation strength, cracking, differential watering system is relied upon for control of scope of the applicant's 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 subfoundation through the period of extended operation system is relied upon Discussion Monitoring Program, B.2.1.318. Further evaluation is provided in LRA Subsection 3.5.2.2.2.1, Item 5. This item is not applicable to Seabrook. The Seabrook AMR results 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 Subsection 3.5.2.2.2.1, Item 6. This item is not applicable to Seabrook. The Seabrook AMR results 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 Subsection 3.5.2.2.2.1, Item 7.

SBK-L-17155 I Enclosure 2/ Page 14 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components 1: ,, i'I Item Component Aging Effect I Mechanism Aging Management Further Evaluation Number Recommended 1:1 Iii 11111:1 1'1 ii, l'I ,, 3.5.1-30 Group 4: Radial beam Lock-up due to wear ISi (IWF) or Structures Monitoring Program Yes, if not within the seats in BWR drywell; scope of ISi of Structures RPV support shoes for Monitoring Program PWR with nozzle support; Steam generator supports 3.5.1-31 Groups 1-3, 5, 7-9: Increase in porosity and Structures Monitoring Program Examination of Yes, plant-specific if below grade concrete permeability, cracking, loss of representative samples of below grade environment is aggressive components, such as material (spalling, scaling) I concrete, and periodic monitoring of 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 loss of material (spalling, evaluated if the environment is aggressive scaling)/ corrosion of embedded steel Discussion ' 11*1 Lubrite materials for nuclear applications are designed to resist deformation, have a low coefficient of friction, resist 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. The Seabrook AMR results conclude that the groundwater is aggressive. The Structures Monitoring Program, B.2.1.31, will manage degradation of 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-17155/Enclosure2/Page15 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components 1; Item Component Aging Effect I Mechanism Aging Management Further Evaluation Number ' Program Recommended 111 111. :I I !I!!' :1: :Ii I :1:* :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 exterior above and permeability, loss of strength areas. None for inaccessible areas if concrete constructed as stated for below grade reinforced due to leaching of calcium was constructed in accordance with the inaccessible areas concrete foundations hydroxide recommendations in ACI 201.2R-77 3.5.1-33 Group 1-5: concrete Reduction in strength and Plant-specific Yes, plant specific if modulus due to elevated temperature limits are temperature exceeded ' Discussion :111:1 Loss of material due to leaching of calcium hydroxide is considered to be an aging effect requiring management for Seabrook. There have been indications of leaching in below grade concrete in Seabrook structures. Further evaluation is provided in LRA Subsection 3.5.2.2.2.2, Item 5. This item is not applicable to Seabrook concrete components do not exceed the temperature limits specified in NUREG-1800. Further evaluation is provided in LRA Subsection 3.5.2.2.2.3.

SBK-L-17155 I Enclosure 2/ Page 16 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components ,,, *I Item Component Aging Effect I Mechanism Aging Management Further Evaluation 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 of material due to corrosion Associated with Nuclear Power Plants and for environment is aggressive of embedded steel, increase inaccessible concrete, examination of in porosity and permeability, representative samples of below grade cracking, loss of material due concrete, and periodic monitoring of to aggressive chemical attack groundwater, if environment is non-aggressive. Plant-specific if environment is aggressive 3.5.1-35 Group 6: exterior above Loss of material (spalling, Inspection of Water Control Structures Yes, for inaccessible and below grade scaling) and cracking due to Associated with Nuclear Power Plants is areas of plants located in concrete foundation freeze-thaw needed for plants that are located in moderate moderate to severe to severe weathering conditions (weathering weathering conditions index >100 day-inch/yr) (NUEG 1557) 'l'l.11ll1:Ej: Discussion Concrete in inaccessible areas is evaluated for increase in Porosity and Permeability, and Loss of Material (Spalling, Scaling), Chemical Attack; Cracking, 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. Consistent with NUREG-1801. Seabrook manages Loss of material (spalling, scaling) and cracking due to freeze-thaw with the Structures Monitoring Program, B.2.1.31. Further evaluation is provided in LRA Subsection 3.5.2.2.2.4, Item 2.

SBK-L-17155 I Enclosure 2/ Page 17 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components 1:1 ,,, ' I: Item Aging Management, Further Evaluation Number Component Aging Effect I Mechanism 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 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 recommendations in ACI 201.2R77 :1; Discussion GeAsisleAI wi!R The concrete was constructed consistent with the recommendations of ACI 201.2R. Seabrook Station Operating Experience has indicated that Alkali-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 for 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,' ,,,,,,,,,: Item Component Aging Effect I Mechanism Aging Management Further Evaluation 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 and below grade permeability, Joss of strength Control Structures Associated with Nuclear constructed as stated for 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 recommendations in ACI 201.2R77 3.5.1-38 Group 7, 8: Tank liners Cracking due to stress Plant-specific Yes, plant-specific corrosion cracking; Joss of material due to pitting and crevice corrosion 3.5.1-39 Support members; Loss of material due to Structures Monitoring Program Yes, if not within the welds; bolted general and pitting corrosion scope of the applicant's connections; support Structures Monitoring anchorage to building Program structure ' 'l",;I Discussion ,"' Consistent with NUREG-1801. The Structures Monitoring 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. There are no components at Seabrook that are subject to this aging effect. Further evaluation is provided in LRA Subsection 3.5.2.2.2.5. Consistent with NUREG-1801. The Structures Monitoring Program, B.2.1.31, will 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 Component ,, Aging Effect I Aging Management Further Evaluation Number

Prog'ram' i ,, Recommended "' 3.5. 1-40 Building concrete at Reduction in concrete anchor Structures Monitoring Program Yes, if not within the locations of expansion capacity due to local scope of the applicant's and grouted anchors; concrete degradation I Structures Monitoring grout pads for support service-induced cracking or Program base plates other concrete aging mechanisms 3.5.1-41 Vibration isolation Reduction or loss of isolation Structures Monitoring Program Yes, if not within the elements function I radiation scope of the applicant's hardening, temperature, Structures Monitoring humidity, sustained vibratory Program loading 3.5. 1-42 Groups 81. 1, 81 .2, and Cumulative fatigue damage TLAA evaluated in accordance with 10 CFR Yes, TLAA 81 .3: support members: (CLB fatigue analysis exists) 54.21(c) anchor bolts, welds '" ,,,,, ,,.,, '!'Discussion l'I 1*1' *" Consistent with NU REG-1801. The Structures Monitoring Program, B.2.1.31, and 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. This item is not applicable to Seabrook. Seabrook does not have any supports with vibration isolation elements which require AMR Further evaluation is provided in LRA Subsection 3.5.2.2.2.6, Item 3. This item is not applicable to Seabrook. 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 Aging Management Evaluations for Structures and Structural Components I 11:+1. I] IJ Item Component Aging Effeet I Mechanism Aging Management Further Evaluation Number Program Recommended 3.5.1-43 Group 1-3, 5, 6: all Cracking due to restraint Masonry Wall Program No masonry block walls shrinkage, creep, and aggressive environment 3.5.1-44 Group 6 elastomer Loss of sealing due to Structures Monitoring Program No seals, gaskets, and deterioration of seals, moisture barriers gaskets, and moisture barriers (caulking, flashing, and other sealants) 3.5.1-45 Group 6: exterior above Loss of material due to Inspection of Water Control Structures No and below ground abrasion, cavitation Associated with Nuclear Power Plants concrete foundation; interior slab 3.5.1-46 Group 5: fuel pool liners Cracking due to stress Water Chemistry and Monitoring of spent fuel No corrosion cracking; loss of pool water level and level of fluid in the leak material due to pitting and chase channel crevice corrosion Discussion Seabrook manages cracking of masonry block walls and 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. Consistent with NUREG-1801. The Structures Monitoring Program, B.2.1.31., and Building Deformation Monitoring Program, B.2.1.318. Consistent with NU REG-1801. The Structures Monitoring Program, B.2.1.31, will confirm the absence of aging effects requiring management. The spent fuel pool is normally maintained less than 140°F, therefore Stress Corrosion Cracking is not an aging effect that requires 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 ll1 :'i: 11!: 11' l:l'ili! "It* ' 1*:: 1*1:ll*l']::*!'I Item Component Aging Effect I Mechanism Aging* Management Further Evaluation Number Program Recommended 3.5.1-47 Group 6: all metal Loss of material due to Inspection of Water Control Structures No structural members general (steel only), pitting, Associated with Nuclear Power Plants. If and crevice corrosion protective coatings are relied upon to manage aging, protective coating monitoring and maintenance provisions should be included 3.5. 1-48 Group 6: earthen water Loss of material, loss of form Inspection of Water Control Structures No control structures -due to erosion, settlement, Associated with Nuclear Power Plants dams, embankments, sedimentation, frost action, reservoirs, channels, waves, currents, surface canals, and ponds runoff, seepage 3.5.1-49 BWRonly. 3.5.1-50 Groups B2 and 84: Loss of material due to pitting Structures Monitoring Program No galvanized steel, and crevice corrosion aluminum, stainless steel support members; welds; bolted connections; support anchorage to building structure 3.5.1-51 Group B1.1: high Cracking due to stress Bolting Integrity No strength low-alloy bolts corrosion cracking; loss of material due to general corrosion :I: ''l:i: !*I .,:1:1> ]: 1F* Discussion Consistent with NU REG-1801. The Structures Monitoring Program, B.2. 1.31, will confirm the absence of aging effects requiring management. Consistent with NUREG-1801. The Structures Monitoring Program, B.2. 1.31 will confirm the absence of aging effects requiring management. Consistent with NUREG-1801. The Structures Monitoring Program, B.2.1.31, will confirm the absence of aging effects requiring management. There are no high strength bolts at Seabrook that are subject to this aging effect.

SBK-L-17155 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 Component Aging Effect I Mechanism Aging Management Further Evaluation Number Fl .,. Ii!, 11111 Pl 'il:I Recommended . *l:i 'Fl

1*1 'i:r* '"' 'i"H"1111r1*1 . 3.5.1-52 Groups 82 and 84: Loss of mechanical function Structures Monitoring Program No sliding support bearings due to corrosion, distortion, and sliding support dirt, overload, fatigue due to surfaces vibratory and cyclic thermal loads 3.5.1-53 Groups 81.1, 81 .2, and Loss of material due to ISl(IWF) No 81 .3: support members: general and pitting corrosion welds; bolted connections; support anchorage to building structure 3.5.1-54 Group 81.1, 81 .2, and Loss of mechanical function ISl(IWF) No 81 .3: Constant and due to corrosion, distortion, variable load spring dirt, overload fatigue due to hangers; guides; stops vibratory and cyclic thermal loads Discussion l'I Jti 1:1 There are no sliding support bearings of surfaces at Seabrook that are subject to this aging effect. Consistent with NUREG-1801. Seabrook manages the aging effect with the ASME Section XI, Subsection IWF Program, 8.2.1.29. Consistent with NUREG-1801. Seabrook manages the aging effect with the ASME Section XI, Subsection IWF Program, 8.2.1.29.

SBK-L-17155 I Enclosure 2/ Page 23 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components ! .. , Im i 1:n' ,_ l!l 1f!i. I , ::1, ,,i1::: 1:11111 .. I,. .. 111 II )ll1!1 Item Aging Management ,J, ' * "Further Evaluation *i;* Number Component Aging Effect I Mechanism Program 1.1:1' Recommended 3.5.1-55 Steel, galvanized steel, Loss of material due to boric Boric Acid Corrosion No and aluminum support acid corrosion members; welds; bolted connections; support anchorage to building structure 3.5.1-56 Groups B1.1, B1 .2, and Loss of material function due ISl(IWF) No B1 .3: Sliding surfaces to corrosion, distortion, dirt, overload, fatigue due to vibratory and cyclic thermal loads 3.5.1-57 Groups B1.1, B1 .2, and Reduction or loss of isolation ISl(IWF) No B1 .3: Vibration isolation function/radiation hardening, elements temperature, humidity, sustained vibratory loading t1*I IF ii ' ' Discussion Consistent with NUREG-1801. Seabrook manages the aging effect of loss of material due to boric acid corrosion in steel, galvanized steel, and aluminum for all types of support members (including safety and non-safety), welds, bolted connections and support anchorage to building structure with the Boric Acid Corrosion Program, B.2.1.4. There are no sliding support bearings of surfaces at Seabrook that are subject to this aging effect. This item is not applicable to Seabrook. The Seabrook AMR results do not include any supports with vibration 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 Item Number 3.5.1-58 3.5.1-59 3.5.1-60 Component Galvanized steel and aluminum support members; welds; bolted connections; support anchorage to building structure exposed to air -indoor uncontrolled Stainless steel support members; welds; bolted connections; support anchorage to building structure Group 6 elastomer seals, gaskets, and moisture barriers Aging Effect I Mechanism Nooe Nooe l\11:.i ,*I ;l:I ,. 'I' 'i:i Aging Management Program Reduction in structural Structures Monitoring Program capacity directly/ indirectly due to the expansion of concrete Nooe I Nooe Reduction in structural Structures Monitoring Program capacity directly/ indirectly due to the expansion of concrete Loss of bound, I Structures Monitoring Program misalignment, distortion, and/or reduction in structural capacity due to expansion of concrete 1iH *i: I Further Evaluation Recommended 11 N/\ Re agiAg effect maAagemeAt or agiAg maAagemeAt 13rogram Yes, if not within the scope of the applicant's Structures Monitoring Program W\ no agiAg effect maAagemeAt er agiAg maAagemeAt 13rogram Yes, if not within the scope of the applicant's Structures Monitoring Program Yes, if not within the scope of the applicant's Structures Monitoring Program 'I' Discussion Consistent with NUREG-1801. The Structures Monitoring Program, B.2.1.31, and Building Deformation Monitoring Program, B.2.1.31B will manage degradation for the aging effects. GoAsistent with NURE;G Plant Specific. The Structures Monitoring Program, B.2.1.31, and Building Deformation Monitoring Program, B.2.1.31B will manage degradation for the aging effects. Plant Specific The Structures Monitoring Program, B.2.1.31, and Building Deformation Monitoring Program, B.2.1.31B will manage degradation for the aging effects.

SBK-L-17155 I Enclosure 2/ Page 25 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components I 1:I, I 1:; '*lli1:1:1:1:1:11 ,11li Ii ,1 t1111M1 l,1:11l!:i1 1il1/'jl11i'1illl' l!j, :1:i:1:1'1::1 Item Component Aging Effect I Mechanism Aging Management *

1* ** ' ' Further.Evaluation' Number Program Recommended 3.5.1-61 Steel, galvanized steel, Reduction/loss in Structures Monitoring Program Yes, if not within the and aluminum support structural capacity due to scope of the members; welds; expansion of concrete applicant's Structures bolted connections; Monitoring Program support anchorage to building structure li1i:lily1n I'! .. 'l'I' , Discussion Plant Specific The Structures Monitoring Program, B.2.1.31, and Building Deformation Monitoring Program, B.2.1.318 will manage degradation for the aging effects.

SBK-L-17155 I Enclosure 2/ Page 26 U.S. Nuclear Regulatory Commission i: ,: Component Type BSAS Carbon Steel FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Carbon Steel FIRE PUMPHOUSE Exposed to Air Outdoor BSAS Carbon Steel NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Carbon Steel NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor BSAS Carbon Steel REVETMENT Exposed to Air Outdoor BSAS Carbon Steel REVETMENT Exposed to Air Outdoor ,,, Intended Function Structural Support Structural Support Structural Support Structural Support Flood Barrier Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Air Indoor Uncontrolled Steel (External) Loss of Material Steel Air Outdoor (External) Loss of Material Air Indoor Uncontrolled Steel (External) Loss of Material Steel Air Outdoor (External) Loss of Material Steel Air Outdoor (External) Loss of Material Steel Air Outdoor (External) Loss of Material Aging NU REG-Table "+' ' Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A Program Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A, 503 Program Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A Program Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A, 503 Program Structures lll.A6-11 3.5.1-E, 503, Monitoring Program (T-21) 47 511 Structures lll.A6-11 3.5.1-E, 503, Monitoring Program (T-21) 47 511 SBK-L-17155 I Enclosure 2/ Page 27 U.S. Nuclear Regulatory Commission Component Type BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water Intended Function Flood Barrier Support Flood Barrier Support Flood Barrier Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item IV Item Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A6-11 3.5.1-Monitoring (T-21) 47 H, 514 Program Structures 111.A6-11 3.5.1-Monitoring (T-21) 47 H, 514 Program SBK-L-17155 I Enclosure 2/ Page 28 U.S. Nuclear Regulatory Commission Component Type BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water SSAS Carbon Steel STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Indoor Uncontrolled SSAS Carbon Steel STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor SSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor SSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor Intended Function Flood Barrier Support Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material I Environment Requiring 1,li!'I II Managemeni Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Air Indoor Uncontrolled Steel Loss of Material (External) Steel Air Outdoor (External) Loss of Material Cracking, Loss of Bond, Loss of Concrete Air Outdoor (External) Material (Spalling, Scaling) Expansion and Concrete Air Outdoor (External) Cracking cc Aging NU REG-Table , Management ,1so1 vor.; 3.X-1 Note 121tem1 * ' :, Program ' Item Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A Program Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A, 503 Program Structures Monitoring lll.A3-9 3.5.1-A (T-04) 23 Program Structures Monitoring Program, lll.A3-2 3.5.1-A, E, Alkali-Silica (T-03) 27 517 Reaction (ASR) Monitoring Proa ram SBK-L-17155 I Enclosure 2/ Page 29 U.S. Nuclear Regulatory Commission Component Type SSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor SSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor SSAS Concrete (Sump) FIRE PUMPHOUSE Exposed to Raw Water BSAS Concrete (Sump) FIRE PUMPHOUSE Exposed to Raw Water SSAS Concrete (Sump) STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Raw Water Intended Function Structural Support Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Concrete Air Outdoor (External) Loss of Material Cracking, Loss of Concrete Raw Water (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Raw Water (External) Cracking Cracking, Loss of Concrete Raw Water (External) Bond, Loss of Material (Spalling, Scaling) Aging NU REG-Table Management 1801 Vol. Note Program 2 Item Item Structures Monitoring 111.A3-10 3.5.1-A (T-06) 24 Program Structures lll.A3-6 3.5.1-Monitoring (T-01) 26 A Program Structures Monitoring lll.A3-4 3.5.1-A Program (T-05) 31 Structures Monitoring Program , Alkali-lll.A3-2 3.5.1-A, E, Silica Reaction (ASR) (T-03) 27 517 Monitoring Program Structures Monitoring lll.A3-4 3.5.1-A (T-05) 31 Program SBK-L-17155 I Enclosure 2/ Page 30 U.S. Nuclear Regulatory Commission Component Type SSAS Concrete (Sump) STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Raw Water SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled Intended Function Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Expansion and Concrete Raw Water (External) Cracking Cracking, Loss of Air Indoor Uncontrolled Bond, Loss of Concrete (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Concrete (External) Cracking Increase In Porosity and Air Indoor Uncontrolled Permeability, Concrete (External) Cracking, Loss of Material (Spalling, Scaling) Aging NU REG-Table Management 1801 Vol. 3.X-1 Nqte Program 2 Item Item Structures Monitoring Program, Alkali-lll.A3-2 3.5.1-A, E, Silica Reaction (T-03) 27 517 (ASR) Monitoring Program Structures 3.5.1-Monitoring lll.A6-1 E, 511 (T-18) 34 Program Structures Monitoring Program, Alkali-lll.A6-2 3.5.1-E, 511, Silica Reaction (T-17) 36 517 (ASR) Monitoring Program Structures lll.A3-10 3.5.1-Monitoring A (T-06) 24 Program SBK-L-17155 I Enclosure 2/ Page 31 U.S. Nuclear Regulatory Commission Component Type SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor Intended Function Missile Barrier Structural Support Missile Barrier Structural Support Missile Barrier Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Air Outdoor (External) Cracking Expansion and Concrete Air Outdoor (External) Cracking Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Aging NU REG-Table '*it' Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-A Program (T-06) 24 SBK-L-17155 I Enclosure 2/ Page 32 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Raw Water BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Raw Water Intended Function Structural Support Missile Barrier Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Managernent Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Loss of Material, Concrete Air Outdoor (External) Cracking Loss of Material, Concrete Air Outdoor (External) Cracking Cracking, Loss of Concrete Raw Water (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Raw Water (External) Cracking Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring 111.A3-10 3.5.1-A (T-06) 24 Program Structures lll.A6-5 3.5.1-Monitoring (T-15) 35 E, 511 Program Structures lll.A6-5 3.5.1-Monitoring (T-15) 35 E, 511 Program Structures Monitoring lll.A3-4 3.5.1-A (T-05) 31 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 33 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Raw Water BSAS Concrete FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Concrete FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Concrete FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Concrete FIRE PUMPHOUSE Exposed to Air Outdoor Intended Function Structural Support Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation ,., .. , Aging Effect Material Environment Requiring Management Increase In Concrete Raw Water (External) Porosity and Permeability, Loss of Strength Cracking, Loss of Concrete Air Indoor Uncontrolled Bond, Loss of (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Concrete (External) Cracking Increase In Porosity and Concrete Air Indoor Uncontrolled Permeability, (External) Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) 'Aging ' NUREG-1 1 Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring lll.A6-6 3.5. 1-E, 511 (T-16) 37 Program Structures Monitoring lll.A3-9 3.5.1-A (T-04) 23 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 3.5.1-A, Monitoring (T-03) 27 517,E, Program & 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-A Program (T-06) 24 Structures Monitoring 111.A3-9 3.5.1-A (T-04) 23 Program SBK-L-17155 I Enclosure 2/ Page 34 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete FIRE PUMPHOUSE Exposed to Air Outdoor BSAS Concrete FIRE PUMPHOUSE Exposed to Air Outdoor BSAS Concrete FIRE PUMPHOUSE Exposed to Air Outdoor BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled Intended Function Structural Support Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Expansion and Concrete Air Outdoor (External) Cracking Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Loss of Material, Concrete Air Outdoor (External) Cracking Cracking, Loss of Concrete Air Indoor Uncontrolled Bond, Loss of (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Concrete (External) Cracking ---------------------Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) 111.A3-2 3.5.1-A, Monitoring (T-03) 27 517,E, Program & 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-A Program (T-06) 24 Structures lll.A3-6 3.5.1-Monitoring (T-01) 26 A Program Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 35 U.S. Nuclear Regulatory Commission Component Type SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor Intended Function Structural Support Missile Barrier Structural Support Missile Barrier Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Increase In Porosity and Concrete Air Indoor Uncontrolled Permeability, (External) Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Air Outdoor (External) Cracking Expansion and Concrete Air Outdoor (External) Cracking Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Prqgram 2 Item Item Structures Monitoring lll.A3-10 3.5.1-A Program (T-06) 24 Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 36 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Raw Water BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Raw Water '1" Intended Function Missile Barrier Structural Support Missile Barrier Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation 1: Aging Effect Material Environment Requiring Management Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Loss of Material, Concrete Air Outdoor (External) Cracking Loss of Material, Concrete Air Outdoor (External) Cracking Cracking, Loss of Concrete Raw Water (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Raw Water (External) Cracking ' *.1 Nl'.IREG-Aging Table. " Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring lll.A3-10 3.5.1-A (T-06) 24 Program Structures Monitoring 111.A3-10 3.5.1-A Program (T-06) 24 Structures lll.A6-5 3.5.1-Monitoring A Program (T-15) 35 Structures lll.A6-5 3.5.1-Monitoring (T-15) 35 A Program Structures Monitoring lll.A3-4 3.5.1-A, 509 (T-05) 31 Program Structures Monitoring Program, Alkali-Silica Reaction E, 511, (ASR) 111.A6-2 3.5.1-Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitorina SBK-L-17155 I Enclosure 2/ Page 37 U.S. Nuclear Regulatory Commission ., Component Type SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Raw Water BSAS Concrete Masonry Units FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Concrete Masonry Units FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Concrete Masonry Units NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete Masonry Units NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor Intended Function Structural Support Fire Barrier Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Increase In Concrete Raw Water (External) Porosity and Permeability, Loss of Strength Concrete Air Indoor Uncontrolled Block (External) Cracking Concrete Air Indoor Uncontrolled Block (External) Cracking Concrete Air Indoor Uncontrolled Cracking Block (External) Concrete Block Air Outdoor (External) Cracking Aging NU REG-Table I Management 1801 Vol. 3.X-1 Note Program 2 Item Item Program Structures Monitoring lll.A6-6 3.5.1-E, 511 Program (T-16) 37 Fire Protection lll.A3-11 3.5.1-Program (T-12) 43 E, 513 Structures lll.A3-11 3.5.1-Monitoring (T-12) 43 E, 511 Program Structures Monitoring lll.A3-11 3.5.1-E, 511 (T-12) 43 Program Structures lll.A3-11 3.5.1-Monitoring (T-12) 43 E, 511 Program SBK-L-17155 I Enclosure 2/ Page 38 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade Intended Function Structural Support Structural Support Structural Support Flood Barrier Support Flood Barrier Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Agin'g Effect Material Environment Requiring Management Cracking, Loss of Concrete Air Indoor Uncontrolled Bond, Loss of (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Concrete (External) Cracking Increase In Porosity and Concrete Air Indoor Uncontrolled Permeability, (External) Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Soil (External) Bond, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Soil (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Soil (External) Cracking I' '" 1'11. ., '. Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Structures Monitoring lll.A3-9 3.5.1-A (T-04) 23 Program Structures Monitoring Program, Alkali-lll.A3-2 3.5.1-A, E, Silica Reaction (T-03) 27 517 (ASR) Monitoring Program Structures Monitoring lll.A3-10 3.5.1-A (T-06) 24 Program Structures Monitoring lll.A3-4 3.5.1-A, 509 (T-05) 31 Program Structures Monitoring lll.A3-4 3.5.1-A, 509 (T-05) 31 Program Structures Monitoring Program, Alkali-lll.A6-2 3.5.1-E, 511, Silica Reaction (T-17) 36 517 (ASR) Monitoring Proo ram SBK-L-17155 I Enclosure 2/ Page 39 U.S. Nuclear Regulatory Commission Component Type I BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Exposed to Air Outdoor Intended Function Support Flood Barrier Support Flood Barrier Support Flood Barrier Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Expansion and Concrete Soil (External) Cracking Increase In Porosity and Concrete Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase In Porosity and Concrete Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase In Concrete Soil (External) Porosity and Permeability, Loss of Strength Increase In Concrete Soil (External) Porosity and Permeability, Loss of Strength Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item I" 1:,1 Structures Monitoring Program, Alkali-lll.A6-2 3.5.1-E, 511, Silica Reaction (T-17) 36 517 (ASR) Monitoring Proqram Structures Monitoring lll.A6-3 3.5.1-E, 511 Program (T-19) 34 Structures Monitoring lll.A6-3 3.5.1-E, 511 Program (T-19) 34 Structures Monitoring lll.A6-6 3.5.1-E, 509, Program (T-16) 37 511 Structures Monitoring lll.A6-6 3.5.1-E, 509, (T-16) 37 511 Program Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program SBK-L-17155 I Enclosure 2/ Page 40 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete REVETMENT Exposed to Air Outdoor BSAS Concrete REVETMENT Exposed to Air Outdoor SSAS Concrete REVETMENT Exposed to Air Outdoor SSAS Concrete REVETMENT Exposed to Air Outdoor SSAS Concrete REVETMENT Exposed to Air Outdoor SSAS Concrete REVETMENT Exposed to Air Outdoor Intended Function Support Flood Barrier Support Flood Barrier Support Flood Barrier Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring I Management Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Air Outdoor (External) Cracking Expansion and Concrete Air Outdoor (External) Cracking Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Loss of Material, Concrete Air Outdoor (External) Cracking Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring lll.A6-1 3.5.1-E, 511 Program (T-18) 34 Structures Monitoring Program, Alkali-lll.A6-2 3.5.1-E, 511, Silica Reaction (T-17) 36 517 (ASR) Monitoring Proqram Structures Monitoring Program, Alkali-lll.A6-2 3.5.1-E, 511, Silica Reaction (T-17) 36 517 (ASR) Monitoring Proqram Structures Monitoring 111.A3-10 3.5.1-A Program (T-06) 24 Structures Monitoring lll.A3-10 3.5.1-A (T-06) 24 Program Structures lll.A6-5 3.5.1-Monitoring (T-15) 35 E, 511 Program SBK-L-17155 I Enclosure 2/ Page 41 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete REVETMENT Exposed to Air Outdoor BSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Indoor Uncontrolled SSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor BSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor Intended Function Support Structural Support Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Loss of Material, Concrete Air Outdoor (External) Cracking Cracking, Loss of Air Indoor Uncontrolled Bond, Loss of Concrete (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Concrete (External) Cracking Increase In Porosity and Air Indoor Uncontrolled Permeability, Concrete (External) Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Concrete Air Outdoor (External) Material (Spalling, Scaling) Expansion and Concrete Air Outdoor (External) Cracking 'I Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures lll.A6-5 3.5.1-Monitoring (T-15) 35 E, 511 Program Structures Monitoring 111.A3-9 3.5.1-A (T-04) 23 Program Structures Monitoring Program, Alkali-lll.A3-2 3.5.1-A, E, Silica Reaction (T-03) 27 517 (ASR) Monitoring Proa ram Structures Monitoring lll.A3-10 3.5.1-A (T-06) 24 Program Structures lll.A3-9 3.5.1-Monitoring (T-04) 23 A Program Structures Monitoring Program, Alkali-lll.A3-2 3.5.1-A, E, Silica Reaction (T-03) 27 517 (ASR) Monitoring Proa ram SBK-L-17155 I Enclosure 2/ Page 42 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor SSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor SSAS Rock (Riprap) REVETMENT Exposed to Air Outdoor SSAS Rock (Riprap) REVETMENT Exposed to Air Outdoor SSAS Roofing For FIRE PUMPHOUSE Exposed to Air Outdoor SSAS Roofing For NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor Intended Function Structural Support Structural Support Flood Barrier Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material II 1, . 11 II Management Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Loss of Material, Concrete Air Outdoor (External) Cracking Loss of Material, Rock Air Outdoor (External) Loss of Form Loss of Material, Rock Air Outdoor (External) Loss of Form Separation, Roofing Air Outdoor (External) Environmental Degradation, Water In-Leakage Separation, Environmental Roofing Air Outdoor (External) Degradation, Water In-Leakage Aging NU REG-Table Management . 1801 Vol. '* 3.X-1 Note ., .. ,,,.HProgram 1tl '* lli'li2'1tem'1'11*1'

ltEim 1:1 H Structures Monitoring lll.A3-10 3.5.1-A (T-06) 24 Program Structures lll.A3-6 3.5.1-Monitoring (T-01) 26 A Program Structures lll.A6-9 3.5.1-Monitoring E, 511 Program (T-22) 48 Structures lll.A6-9 3.5.1-Monitoring E, 511 Program (T-22) 48 Structures Monitoring lll.A6-12 3.5.1-H,505 Program (TP-7) 44 Structures 111.A6-12 3.5.1-Monitoring (TP-7) 44 H,505 Program SBK-L-17155 I Enclosure 2/ Page 43 U.S. Nuclear Regulatory Commission Component Type ' BSAS Roofing For STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor BSAS Slide Bearing (Fluorogold) NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Stainless Steel STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Indoor Uncontrolled Intended Function Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring *I Management Separation, Roofing Air Outdoor (External) Environmental Degradation, Water In-Leakage Fluorogold Air Indoor Uncontrolled Fretting Or (External) Lockup Stainless Air Indoor Uncontrolled None Steel (External) Aging I NU REG-Table Management 1801 Vol. 3.X-1 Note ,Program!!' 1.1 2 ltem:if' ;.1 1; Item* *.. *i Structures Monitoring lll.A6-12 3.5.1-H, 505 (TP-7) 44 Program Structures Monitoring 111.84-2 3.5.1-c Program (TP-1) 52 No Aging Management 111.85-5 3.5.1-A Program (TP-5) 59 Required SBK-L-17155 I Enclosure 2/ Page 44 U.S. Nuclear Regulatory Commission Standard Notes Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation 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 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 "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 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-17155 I Enclosure 2/ Page 46 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Carbon Steel Structural Exposed to Air with Support Borated Water Leakage CNT-CE-Carbon Steel Structural Exposed to Air Indoor Support Uncontrolled CNT-CE-Carbon Steel Structural Exposed to Air Outdoor Support CNT-CE-Fire Penetration Seal Exposed to Air Indoor Fire Barrier Uncontrolled CNT-CE-Reinforced Shelter, Concrete Below Grade Protection CNT-CE-Reinforced Structural Concrete Below Grade Support '1: Material Steel Steel Steel Elastomer Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation +: .** Aging EffectRequiring :Environment Management Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Outdoor (External) Loss of Material ;1, Air Indoor Increased Hardness and Shrinkage Uncontrolled (External) and Loss of Strength Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) 1., Aging 1:i: l'j' I 1 I 1 Table ,, ManagE!ment '

1801Vol.'2 '3.X.1 'Nbte1*1 l'I Program Item Item Boric Acid lll.B2-11 Corrosion (T-25) 3.5. 1-55 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Structures 111.A1-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Fire Protection Vll.G-1 3.3.1-61 A Program (A-19) Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05)

SBK-L-17155 I Enclosure 2/ Page 47 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Shelter, Concrete Below Grade Protection CNT-CE-Reinforced Structural Concrete Below Grade Support CNT-CE-Reinforced Shelter, Concrete Below Grade Protection CNT-CE-Reinforced Structural Concrete Below Grade Support Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation 111,1; Environment Aging 'Effect Requiring Management Soil (External) Expansion and Cracking Soil (External) Expansion and Cracking Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) f. Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item .Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) A, E, Monitoring lll.A1-2 3.5.1-27 Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) A, E, Monitoring lll.A1-2 3.5.1-27 Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A1-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A1-5 Monitoring (T-07) 3.5.1-31 A Program SBK-L-17155 I Enclosure 2/ Page 48 U.S. Nuclear Regulatory Commission Intended Component Type ,Function CNT-CE-Reinforced Shelter, Concrete Below Grade Protection CNT-CE-Reinforced

Structural Concrete Below Grade Support CNT-CE-Reinforced Shelter, Concrete Below Grade Protection CNT-CE-Reinforced Structural Concrete Below Grade Support CNT-CE-Reinforced Shelter, Concrete Exposed to Air Indoor Uncontrolled Protection CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring 111 Managerrl'ent 1:11 Increase in Porosity and Soil (External) Permeability, Loss of Strength Increase in Porosity and Soil (External) Permeability, Loss of Strength Soil (External) Loss of Material, Cracking Soil (External) Loss of Material, Cracking Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Aging NUREG I Table Managef)1Emt 1801 2 ,' 3.X.1 I Note Program ,, lteri\ Item I Structures lll.A1-7 Monitoring 3.5.1-32 A, 509 Program (T-02) Structures lll.A1-7 Monitoring 3.5.1-32 A, 509 Program (T-02) Structures IJl.A1-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A1-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04)

SBK-L-17155 I Enclosure 2/ Page 49 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support CNT-CE-Reinforced Concrete Exposed to Air Shelter, Indoor Uncontrolled Protection CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CE-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management 1. Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) ' Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note *I P.rogram ., .,. ltem-i:'i:i I Item Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E 517, Program & (T-03) 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring 3.5.1-27 Program & (T-03) 517, 519 Building Deformation Monitoring Proqram Structures Monitoring Program, Alkali-Silica Reaction lll.A1-2 A, E, (ASR) 3.5.1-27 Monitoring (T-03) 517, 519 Program & Building Deformation SBK-L-17155 I Enclosure 2/ Page 50 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Shelter, Concrete Exposed to Air Protection Indoor Uncontrolled CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CE-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-CE-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CE-Reinforced Concrete Exposed to Air Missile Barrier Outdoor Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment '" [ll1Aging !=ffect Requiring **11**11 Management* Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) ** Aging NU REG Table II 'ii *I: 1801 Vol. 2 3.X.1 Note Program Item Item Monitoring Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04)

SBK-L-17155 I Enclosure 2/ Page 5 I U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Shelter, Concrete Exposed to Air Outdoor Protection CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier CNT-CE-Reinforced Structural Concrete Exposed to Air Outdoor Support CNT-CE-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CE-Reinforced Concrete Exposed to Air Missile Barrier Outdoor Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management I* Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Air Outdoor Expansion and Cracking (External) Aging NU REG .Table Management 18011Vol. 2 3.X.1 Note Program Item Item :1 Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures 111.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction lll.A1-2 3.5.1-27 A, E, (ASR) (T-03) 517, 519 Monitoring Program & Building SBK-L-17155 I Enclosure 2/ Page 52 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Concrete Exposed to Air Shelter, Protection Outdoor CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier Material Concrete Concrete ' Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management ' F :1:1*1 I I Air Outdoor Expansion and Cracking (External) Air Outdoor Expansion and Cracking (External) <ii Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item *1*,. Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 53 U.S. Nuclear Regulatory Commission Component Type Intended Function CNT-CE-Reinforced Structural Concrete Exposed to Air Support Outdoor CNT-CE-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CE-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CE-Reinforced Shelter, Concrete Exposed to Air Protection Outdoor CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation 1111 " Agiri'g Effect Requiring I Environment Management Air Outdoor (External) Expansion and Cracking Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Aging NU REG Table :" Management 1801 Vol. 2 3.X.1 Note Program Item Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A1-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 54 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Structural Concrete Exposed to Air Support Outdoor CNT-CE-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CE-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CE-Reinforced Shelter, Concrete Exposed to Air Outdoor Protection CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier CNT-CE-Reinforced Structural Concrete Exposed to Air Support Outdoor Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Air Outdoor (External) Loss of Material, Cracking Air Outdoor Loss of Material, Cracking (External) Air Outdoor (External) Loss of Material, Cracking Air Outdoor (External) Loss of Material, Cracking ---*---Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note ' Program .. 1:1: .ltem1 Itel"!' ,,1

I Structures lll.A1-10 Monitoring (T-06) 3.5. 1-24 A Program Structures lll.A1-6 Monitoring (T-01) 3.5. 1-26 A Program Structures lll.A1-6 Monitoring (T-01) 3.5. 1-26 A Program Structures 111.A1-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A1-6 Monitoring (T-01) 3.5. 1-26 A Program Structures lll.A1-6 Monitoring (T-01) 3.5. 1-26 A Program SBK-L-17155 I Enclosure 2/ Page 55 U.S. Nuclear Regulatory Commission , Intended Component Type Function CNT-CE-Stainless Steel Structural Exposed to Air Outdoor Support CNT-CEVA-Built-Up Roofing Exposed to Air Shelter, Outdoor Protection CNT-CEVA-Carbon Steel HELB Door Exposed to Air with Shielding Borated Water Leakage CNT-CEVA-Carbon Steel Shelter, Door Exposed to Air with Borated Water Leakage Protection CNT-CEVA-Carbon Steel Structural Door Exposed to Air with Support Borated Water Leakage CNT-CEVA-Carbon Steel HELB Door Exposed to Air Indoor Shielding Uncontrolled Material Stainless Steel Roofing Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment . Management Air Outdoor (External) Loss of Material Air Outdoor Separation, Environmental (External) Degradation, Water In-Leakage Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External Air w/Borated Water Leakage Loss of Material (External Air Indoor Uncontrolled Loss of Material (External) II , Aging I Management 1*11 NU REG 180'1'1Vol:112 1 ,,, ,,Tabl1e111 3.X.1 Note ,,Program :r Item Item !I Structures lll.B2-7 Monitoring (TP-6) 3.5.1-50 A Program Structures Monitoring Program 111.A6-12 3.5.1-44 505, H, Building (TP-7) E, 520 Deformation Monitoring Proaram Boric Acid lll.B2-11 Corrosion (T-25) 3.5.1-55 A Program Boric Acid 111.82-11 Corrosion 3.5.1-55 A Program (T-25) Boric Acid lll.B2-11 Corrosion (T-25) 3.5.1-55 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program SBK-L-17155 I Enclosure 2/ Page 56 U.S. Nuclear Regulatory Commission Intended Component Type, Function CNT-CEVA-Carbon Steel Shelter, Door Exposed to Air Indoor Uncontrolled Protection CNT-CEVA-Carbon Steel Structural Door Exposed to Air Indoor Support Uncontrolled CNT-CEVA-Carbon Steel Structural Exposed to Air with Pressure Borated Water Leakage Barrier CNT-CEVA-Carbon Steel Structural Exposed to Air with Support Borated Water Leakage CNT-CEVA-Carbon Steel Structural Exposed to Air Indoor Pressure Uncontrolled Barrier CNT-CEVA-Carbon Steel Structural Exposed to Air Indoor Support Uncontrolled Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Re,quiring Environment Management Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Aging NU REG Table Management ,1sq1 3.X.1 Note Prb91.'am n '.I *:11 ,. Item Item Structures lll.A1-12 Monitoring 3.5.1-25 A Program (T-11) Structures 111.A1-12 Monitoring (T-11) 3.5. 1-25 A Program Boric Acid lll.B2-11 Corrosion (T-25) 3.5.1-55 A Program Boric Acid lll.B2-11 Corrosion (T-25) 3.5.1-55 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program SBK-L-17155 I Enclosure 2/Page 57 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Carbon Steel Structural Exposed to Air Outdoor Support CNT-CEVA-Carbon Steel Fire Door Exposed to Air Fire Barrier with Borated Water Leakage CNT-CEVA-Carbon Steel Fire Door Exposed to Air Structural with Borated Water Support Leakage CNT-CEVA-Carbon Steel Fire Door Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CEVA-Carbon Steel Structural Fire Door Exposed to Air Support Indoor Uncontrolled CNT-CEVA-Carbon Steel Fire Door Exposed to Air Fire Barrier Indoor Uncontrolled Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment ' . Air Outdoor (External) Loss of Material Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item 'I Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Boric Acid Corrosion lll.B2-11 3.5.1-55 A Program (T-25) Boric Acid Corrosion lll.B2-11 3.5.1-55 A Program (T-25) Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Fire Protection Vll.G-3 Program (A-21) 3.3.1-63 A SBK-L-17155 I Enclosure 2/ Page 58 U.S. Nuclear Regulatory Commission lnterided Component Type Function CNT-CEVA-Carbon Steel Structural Fire Door Exposed to Air Support Indoor Uncontrolled CNT-CEVA-Carbon Steel Structural Tech Spec Door Exposed Pressure to Air with Borated Water Barrier Leakage CNT-CEVA-Carbon Steel Tech Spec Door Exposed Structural to Air with Borated Water Support Leakage CNT-CEVA-Carbon Steel Structural Tech Spec Door Exposed Pressure to Air Indoor Uncontrolled Barrier CNT-CEVA-Carbon Steel Structural Tech Spec Door Exposed Support to Air Indoor Uncontrolled CNT-CEVA-Elastomeric Structural Pressure Seal and Caulk Pressure Exposed to Air Indoor Uncontrolled Barrier Material Steel Steel Steel Steel Steel Elastomer Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment 111,, w 1:1 :i*ill, ,,, :1:111:: 1'1'11 'l:l'l'il:: ' Aging Effect Requi'ring,ll: J1j::' *. Management :1' '1 1* i,"11 Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Increased Hardness and Shrinkage and Loss of Strength (External) :II 1Aglng :1.* 1 * 'I" 1'1 **'*I I 1' l'i' .* *1111 : : ' : ' : : I ' ' I I 1, ' ' ' :;1Note ::I Managementll:' 1'118011'Voll;121, 1l,11.3.ft1:lt 111:']' 'I 1 l:J'I:, 'Ill '*' 'T'l , i. ,, ''f',,,1:1:: liii:J ,,!11:,i:1 , , Progrc:irn, ,,4, 1 , 1 ll'll*'i1llte1T'l]il:]I:, 1 ,1',11lem,*1,,"1i' Fire Protection Vll.G-3 Program (A-21) 3.3.1-63 A Boric Acid Corrosion lll.B2-11 3.5.1-55 A Program (T-25) Boric Acid Corrosion lll.B2-11 3.5.1-55 A Program (T-25) Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Structures Ill.A 1-12 Monitoring (T-11) 3.5.1-25 A Program Structures Monitoring Vll.G-1 3.3.1-61 E, 515 (A-19) Program SBK-L-17155 I Enclosure 2/ Page 59 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Elastomers Expansion I Exposed to Air Outdoor Separation CNT-CEVA-Fire Penetration Seal Exposed Fire Barrier to Air Indoor Uncontrolled CNT-CEVA-Fire Penetration Seal Exposed Fire Barrier to Air Indoor Uncontrolled CNT-CEVA-Penetration Structural Seal Exposed to Air Indoor Pressure Uncontrolled Barrier CNT-CEVA-Reinforced Shelter, Concrete Below Grade Protection CNT-CEVA-Reinforced Structural Concrete Below Grade Support CNT-CEVA-Reinforced Shelter, Concrete Below Grade Protection Material Elastomer Elastomer Elastomer Elastomer Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Air Outdoor Increased Hardness and Shrinkage (External) and Loss of Strength Air Indoor Increased Hardness and Shrinkage Uncontrolled (External) and Loss of Strength Air Indoor Increased Hardness and Shrinkage Uncontrolled (External) and Loss of Strength Air Indoor Increased Hardness and Shrinkage Uncontrolled (External) and Loss of Strength Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) Soil (External) Expansion and Cracking Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note *

I 1 Item Item ;;I Structures Vll.G-1 Monitoring 3.3.1-61 E, 515 Program (A-19) Fire Protection Vll.G-1 3.3.1-61 A Program (A-19) Structures Vll.G-1 Monitoring 3.3.1-61 E,515 Program (A-19) Structures Vll.G-1 Monitoring 3.3.1-61 E, 515 Program (A-19) Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A1-2 3.5.1-27 A, E, MonitorinQ (T-03) 517, 519 SBK-L-17155 I Enclosure 2/ Page 60 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Structural Concrete Below Grade Support CNT-CEVA-Reinforced Shelter, Concrete Below Grade Protection CNT-CEVA-Reinforced Structural Concrete Below Grade Support CNT-CEVA-Reinforced Shelter, Concrete Below Grade Protection Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring Management 1:1, Soil (External) Expansion and Cracking Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Soil (External) Permeability, Loss of Strength 111 Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note rl* Program *11 Item 1:1

111 *' "' Program, Alkali-Silica Reaction (ASR) Monitoring Program & Building Deformation Monitorina Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring (T-03) 3.5. 1-27 517, 519 Program & Building Deformation Monitoring Structures lll.A1-5 Monitoring (T-07) 3.5. 1-31 A Program Structures lll.A1-5 Monitoring (T-07) 3.5. 1-31 A Program Structures lll.A1-7 Monitoring (T-02) 3.5. 1-32 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 61 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Structural Concrete Below Grade Support CNT-CEVA-Reinforced Shelter, Concrete Below Grade Protection CNT-CEVA-Reinforced Structural Concrete Below Grade Support CNT-CEVA-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Indoor Uncontrolled Protection CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation !,I: 1:1:1 ,!:I ::1 ' ' '" .111:' Aging Effect Requiring Environment Management I*' : I ; j , ' j Increase in Porosity and Soil (External) Permeability, Loss of Strength Soil (External) Loss of Material, Cracking Soil (External) Loss of Material, Cracking Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Aging NUREG, Table Management 1801 Vol. 2 3.X.1 Note 1: Program ,,,, 1ltem Item Structures lll.A1-7 Monitoring 3.5. 1-32 A, 509 Program (T-02) Structures lll.A1-6 Monitoring 3.5. 1-26 A Program (T-01) Structures lll.A1-6 Monitoring (T-01) 3.5. 1-26 A Program Structures lll.A1-9 Monitoring 3.5. 1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures 111.A1-9 Monitoring 3.5.1-23 A Program (T-04)

SBK-L-17155 I Enclosure 2/ Page 62 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support CNT-CEVA-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CEVA-Reinforced Concrete Exposed to Air Shelter, Protection Indoor Uncontrolled CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment rvianagement Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction lll.A1-2 3.5.1-27 A, E, (ASR) (T-03) 517, 519 Monitoring Program & Building SBK-L-171 SS I Enclosure 2/ Page 63 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Concrete Exposed to Air Structural Indoor Uncontrolled Support CNT-CEVA-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Protection Indoor Uncontrolled CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier Material 'i' Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Aging NU REG Table Management 1801 Vol,. 2 ':I: + Note Program Item Item Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 64 U.S. Nuclear Regulatory Commission :*: Intended Component Type j*I F'u11ction l,i i'l I:; l'I CNT-CEVA-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-CEVA-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CEVA-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Outdoor Protection CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier CNT-CEVA-Reinforced Concrete Exposed to Air Flood Barrier Outdoor ii Material,, H* ;: Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation I. " Aging Effect Requiring i'I :Environment Management l*I .. :* Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) I.* :j 1-l1NUREG Table' l.Jl!l1 Management 1801 Vol. 2 3.X.1 Note 1' Program Item Item Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction lll.A1-2 3.5.1-27 A, E, (ASR) (T-03) 517, 519 Monitoring Program & Buildina SBK-L-17155 I Enclosure 2/ Page 65 U.S. Nuclear Regulatory Commission Component Type Intended Function CNT-CEVA-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Protection Outdoor CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier Material Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation :'1:1'] ' :lil:j: ii: :pi ,I: ,, Environment Aging Effect Requiring Management Air Outdoor Expansion and Cracking (External) Air Outdoor (External) Expansion and Cracking Air Outdoor Expansion and Cracking (External) :1: +, , . Aging Table" Management 1801 Vol. 2 3.X.1 Note Program Item Item Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring 111.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) 111.A1-2 A, E, Monitoring (T-03) 3.5. 1-27 517, 519 Program & Building Deformation Monitoring Proqram Structures Monitoring Program, Alkali-Silica Reaction lll.A1-2 A, E, (ASR) 3.5.1-27 Monitoring (T-03) 517, 519 Program & Building Deformation SBK-L-17155 I Enclosure 2/ Page 66 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CEVA-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Protection Outdoor CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier CNT-CEVA-Reinforced Concrete Exposed to Air Flood Barrier Outdoor Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Monitoring Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures Ill.A 1-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A1-6 Monitoring (T-01) 3.5.1-26 A Program SBK-L-17155 I Enclosure 2/ Page 67 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Outdoor Protection CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier CNT-CEVA-Tech Spec Structural Seal Exposed to Air Indoor Pressure Uncontrolled Barrier CNT-CEVA-Tech Spec Structural Seal Exposed to Air Pressure Outdoor Barrier CNT-CEVA-Thermal Insulation Aluminum Structural Jacketing in Air with Support Borated Water Leakage Material Concrete Concrete Concrete Elastomer Elastomer Aluminum Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring 1 Managerrteni1 1'. ' Air Outdoor (External) Loss of Material, Cracking Air Outdoor Loss of Material, Cracking (External) Air Outdoor (External) Loss of Material, Cracking 'l*'l:ill Air Indoor Increased Hardness and Shrinkage Uncontrolled (External) and Loss of Strength Air Outdoor Increased Hardness and Shrinkage (External) and Loss of Strength Air w/Borated Water Leakage Loss of Material (External) Aging NU REG Table 11' 1Management *1:1 1so,1IV01..2 3:x.1 :!. *Note Program Item Item I Structures lll.A1-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A1-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A1-6 Monitoring (T-01) 3.5.1-26 A Program Structures Vll.G-1 Monitoring (A-19) 3.3.1-61 E, 515 Program Structures Vll.G-1 Monitoring (A-19) 3.3.1-61 E, 515 Program Boric Acid Corrosion lll.B2-6 3.5.1-55 A (TP-3) Program SBK-L-17155 I Enclosure 2/ Page 68 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-Cl-Carbon Steel Door Structural Exposed to Air with Support Borated Water Leakage CNT-Cl-Carbon Steel Door Shelter, Exposed to Air Indoor Uncontrolled Protection CNT-Cl-Carbon Steel Structural Exposed to Air with Support Borated Water Leakage CNT-Cl-Carbon Steel Structural Exposed to Air Indoor Support Uncontrolled CNT-Cl-Conduit Fire Wrap Exposed to Air Indoor Fire Barrier Uncontrolled CNT-Cl-Conduit Fire Wrap Exposed to Air with Fire Barrier Borated Water Leakage Material"" Steel Steel Steel Steel Stainless Steel Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring1,1 Management' Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Nooe Air Indoor Deformation/reduction in Uncontrolled structural capacity (External) directly/indirectly due to the expansion of concrete Nooe Air w/Borated Deformation/reduction in Water Leakage structural capacity (External) directly/indirectly due to the expansion of concrete l:f: Aging NUREG, [I 1,,,,,Table,, 1, ,, ,,,1: ::.18011 Vol!l 2 ' 3.X.1 1' "Note Program Item Item Boric Acid lll.B2-11 Corrosion (TP-25) 3.5.1-55 A Program Structures lll.A4-5 Monitoring 3.5, 1-25 A Program (T-11) Boric Acid lll.B2-11 Corrosion (TP-25) 3.5, 1-55 A Program Structures lll.A4-5 Monitoring (T-11) 3,5, 1-25 A Program Nooe Building lll.B1 .2-7 Deformation (TP-5) 3.5.1-59 A, E, 520 Monitoring Program Nooe Building lll.B2-9 Deformation (TP-4) 3.5, 1-59 A, E, 520 Monitoring Program SBK-L-17155 I Enclosure 2/ Page 69 U.S. Nuclear Regulatory Commission Component Type Intended Function CNT-Cl-Heat Shield Exposed to Air with Fire Barrier Borated Water Leakage CNT-Cl-Radiant Heat Shield Exposed to Air Fire Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-Cl-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support Material Stainless Steel Stainless Steel Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation '*1 .: !* .' ,'11 I*/ :i: 'r 1*11*1'1'1 111, " .,, , .

Environment* 11 f1l1l11Aging Effect I' .Iii. .I ' I LI {I ':11 ,*1*1+1 11 '!'1 I ' ' Ii: ' J 1lfl11 l:ii:l 1 Management1lf ll1H11111 J) :Iii;' '* ,. 1:1:1, il:'i, .1:11:: ,,,*I: Nooe Air w/Borated Deformation/reduction in Water Leakage structural capacity (External) directly/indirectly due to the expansion of concrete Nooe Air Indoor Deformation/reduction in Uncontrolled structural capacity (External) directly/indirectly due to the expansion of concrete Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Aging .. NUREG '1. 111 *i:,:Table /i11 1'1 i:i Me1nagerT)el1t, 'j"1'I , 1'ao;1,vo1' .. 12 Iii 'I. 'I" r1:i :1::r ' *:1: !Note 1 ll',:3.x.1:1,,' 11::1!11' p111'J!l111i l'i:ilili:l11tem,11J.l1 1!,,w.1tem111 * '*;i:1J: 11:1: *I""**' * "I.* .,, T Nooe Building lll.B2-9 Deformation (TP-4) 3.5.1-59 A, E, 520 Monitoring Program Nooe Building lll.B1 .2-7 Deformation (TP-5) 3.5.1 -59 A, E, 520 Monitoring Program Structures lll.A4-3 Monitoring 3.5.1 -23 A Program (T-04) Structures lll.A4-3 Monitoring 3.5.1-23 A Program (T-04) Structures 111.A4-3 Monitoring 3.5.1 -23 A Program (T-04) Structures 111.A4-3 Monitoring 3.5.1-23 A Program (T-04)

SBK-L-17155 I Enclosure 2/ Page 70 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-Cl-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-Cl-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) ,, Aging ,, NUREG Table Managell!ent 1801 Vol. 2 3.X.1 Note Program Item Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A4-2 A, E, Monitoring 3.5.1-27 Program & (T-03) 517, 519 Building Deformation Monitoring Proaram Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A4-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A4-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A4-2 A, E, Monitoring 3.5.1-27 Program, Alkali-(T-03) 517, 519 I SBK-L-17155 I Enclosure 2/ Page 71 U.S. Nuclear Regulatory Commission :*1 Intended Component Type Function '1'! CNT-Cl-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-Cl-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-Cl-Stainless Steel Structural Exposed to Air with Support Borated Water Leakage Material Concrete Concrete Concrete Concrete Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation ;I t !ill! . n . , . .. . . {l:.1'1.ir*11:1 11'1 ..... 11. tl'!*i" '" ! . *If' 1 *:*:!**A in Effect Re umn *1:1*1' 1111

Environment , * .***. r11:'i11'iJ1l11I ,*; ,I I ' I :I:,;. 1,f I, Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete

l:11Tableji;,1 *** , Aging 1:i :;l,J:1'MaDagemenf'lil1 1*"t801,:Vol1: 211:1 'I 1 '111 u *.** ,j11'( j'1p I' *lh!*11l'l:H1

Item ' I' 1'1, *:, ,,, I*:; rogp\lm 1 .. "' *** *f:i:. ., ... I Silica Reaction (ASR) Monitoring Program & Building Deformation Monitoring Proaram Structures lll.A4-4 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A4-4 Monitoring (T-06) 3.5.1-24 A Program Structures llJ.A4-4 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A4-4 Monitoring (T-06) 3.5.1-24 A Program Nooe Structures Monitoring lll.B1.29 Program, (TP-4) 3.5.1-59 A, E, 520 Building Deformation SBK-L-17155 I Enclosure 2/ Page 72 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-Cl-Stainless Steel Structural Exposed to Air Indoor Support Uncontrolled CNT-Cl-Stainless Steel Structural Raw Water Support CNT-CS-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-CS-Reinforced HELB Concrete Exposed to Air Indoor Uncontrolled Shielding Material Stainless Steel Stainless Steel Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Nooe Air Indoor Reduction in structural capacity Uncontrolled directly. Indirectly due to (External) expansion and cracking of concrete Raw Water (External) Loss of Material Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Aging NU REG Table Management 1801 VoL 2 3.X.1 Note Program Item Item Monitoring Program Nooe Structures Monitoring Program, lll.B1 .2-7 Building (TP-5) 3.5.1-59 A, E, 520 Deformation Monitoring Proqram Structures V.01-15 Monitoring (E-01) 3.2.1-7 E, 514 Program ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05)

SBK-L-17155 I Enclosure 2/ Page 73 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-CS-Reinforced Shelter, Concrete Exposed to Air Indoor Uncontrolled Protection CNT-CS-Reinforced Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CS-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support CNT-CS-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Loss of Material (External) Aging 'NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item* ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section 11.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A SBK-L-17155 I Enclosure 2/ Page 74 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-CS-Reinforced HELB Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-CS-Reinforced Shelter, Concrete Exposed to Air Indoor Uncontrolled Protection CNT-CS-Reinforced Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Material Environment Aging Effect Requiring 1'1* 'Management 11. ' Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Aging NU REG Table l*I Management 1801 Vol. :2 3,.X.1 Note Program Item *Item Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 3.3.1-67 A Program (A-91) Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 3.3.1-67 A Program (A-91)

SBK-L-17155 I Enclosure 2/ Page 75 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air HELB Indoor Uncontrolled Shielding Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring ' Management Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ll.A1-3 A, E, Monitoring (C-04) 3.5.1-15 517, 519 Program Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ll.A1-3 A, E, Monitoring (C-04) 3.5.1-15 517, 519 Program Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program ll.A1-3 3.5.1-15 A, E, (C-04) 517, 519 Alkali-Silica Reaction (ASR)

SBK-L-17155 I Enclosure 2/ Page 76 U.S. Nuclear Regulatory Commission Component Type Function CNT-CS-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-CS-Reinforced Shelter, Concrete Exposed to Air Protection Indoor Uncontrolled Material Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Req6iring ' Environment Management Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging "I NUREG 'I Table Management1'1 1801 Vol.121'1 3.X.1 Note11 ,,,. Program Item Item Monitoring Program Building Deformation Monitoring Proqram ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ILA1-3 A, E, Monitoring (C-04) 3.5.1-15 517, 519 Program Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ILA1-3 A, E, Monitoring (C-04) 3.5.1-15 517, 519 Program Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 77 U.S. Nuclear Regulatory Commission Component ,J"ype 1 CNT-CS-Reinforced Concrete Exposed to Air Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Indoor Uncontrolled ti. Intended Function Shielding Structural Pressure Barrier Structural Support ,I Material Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment ' 1:1 I I I l'i' Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Aging Effect Requiring Management '* Expansion and Cracking Expansion and Cracking Expansion and Cracking 'Aging .1 Management Program ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Proqram ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring NU REG 1801 Vol. 2 Item ILA1-3 (C-04) ILA1-3 (C-04) ll.A1-3 (C-04) Table 3.X.1 Item* 11'\l 3.5.1-15 3.5.1-15 3.5.1-15 Note A, E, 517, 519 A, E, 517, 519 A, E, 517, 519 SBK-L-17155 I Enclosure 2/ Page 78 U.S. Nuclear Regulatory Commission ,. *I *1 :Ii Intended Component Type Function *I CNT-CS-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-CS-Reinforced HELB Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-CS-Reinforced Shelter, Concrete Exposed to Air Indoor Uncontrolled Protection Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation I Aging Effect Requiring Environment Management *1:1: 'l',1111 1., :i Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Aging NU REG Table *u1:: , Note 1:;1 Management 1801 Vol. 2 3.X.1 Program Item ,Item Program Fire Protection Program Vll.G-28 3.3.1-65 A (A-90) Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 3.3.1-65 A Program (A-90)

SBK-L-17155 I Enclosure 2/ Page 79 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Reinforced Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CS-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-CS-Reinforced HELB Concrete Exposed to Air Shielding Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation ';' Aging Effect Requiring Environment Management Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) .. I Aging NU REG Table Management 1801Vol. 2 3.X.1 Note Program Item Item. Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A ASME Section ll.A1-4 XI, Subsection (C-03) 3.5.1-1 A, 516 IWL Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5.1-1 A, 516 IWL Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5.1-1 A, 516 IWL Program SBK-L-17155 I Enclosure 2/ Page 80 U.S. Nuclear Regulatory Commission Component Type 'Intended Function . ; . I i : : ' . . : . ; ' . ;

I ' I CNT-CS-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-CS-Reinforced Shelter, Concrete Exposed to Air Protection Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CS-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-CS-Airlock Hatch Structural Sight Glass Exposed to Air Pressure Indoor Uncontrolled Barrier .Material 1:k, .: .,,, Concrete Concrete Concrete Concrete Concrete Glass Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation I , '*., l1 l*lil;11'\ *11:111'1' ii lllij!l!il ',1!11111*1!1,:li Environment *Aging' Effect Requiring 1 1 11 :I ' . .1 .I. ' Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Uncontrolled None (External) ,, ,. *1:1 I NURE1G11jj:11 ill .. ':1;;.j',. *r 'I 111*1 Ag,1rig1*:1111llil':1I 1:,1:i11Tabfe.111 ,,:i.,.I "I '11.Fl,::1: ,,:,:,:1* ,, Nbte *,'* I' Management 'II . '1111:1,lil PrograM 111'1"1 u11:l:l11tem ,' *::1 1:::1* I ' I . .I 'I' 1' ASME Section 11.A1-4 XI, Subsection (C-03) 3.5. 1-1 A, 516 IWL Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5. 1-1 A, 516 IWL Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5. 1-1 A, 516 IWL Program ASME Section 11.A1-4 XI, Subsection (C-03) 3.5. 1-1 A, 516 IWL Program ASME Section 11.A1-4 XI, Subsection (C-03) 3.5.1-1 A, 516 IWL Program V.F-6 None 3.2. 1-52 A (EP-15)

SBK-L-17155 I Enclosure 2/ Page 81 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Carbon Steel Structural Electrical Penetration Pressure Exposed to Air with Barrier Borated Water Leakage CNT-CS-Carbon Steel Electrical Penetration Structural Exposed to Air with Support Borated Water Leakage CNT-CS-Carbon Steel Structural Electrical Penetration Pressure Exposed to Air Indoor Barrier Uncontrolled CNT-CS-Carbon Steel Electrical Penetration Structural Exposed to Air Indoor Support Uncontrolled CNT-CS-Carbon Steel Structural Equipment Hatch Exposed Pressure to Air with Borated Water Barrier Leakage CNT-CS-Carbon Steel Equipment Hatch Exposed Structural to Air with Borated Water Support Leakage Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation . n.11 f!, 111 , JiV' ,,, *1 ':;:11r';*1:1,YI , Aging Effect Requiring Environment 11 111 .. 1r1 ', Management ' I 111:-:11:,1"111'1:1':111:1:11: 11:1' jli , 'l*l*I' ' Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) , . Table Aging NU REG + Management 18.01 Vol. 2 3.X.1 Note Program Item 11. Item Boric Acid lll.B2-11 (T-Corrosion 3.5.1-55 A 25) Program Boric Acid 111.B2-11 (T-Corrosion 25) 3.5.1-55 A Program ASME Section ll.A3-1 XI, Subsection (C-12) 3.5.1-18 A IWE Program ASME Section ll.A3-1 XI, Subsection (C-12) 3.5.1-18 A IWE Program Boric Acid 111.B2-11 (T-Corrosion 25) 3.5.1-55 A Program Boric Acid lll.B2-11 (T-Corrosion 25) 3.5.1-55 A Program SBK-L-17155 I Enclosure 2/ Page 82 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Carbon Steel Structural Equipment Hatch Exposed Pressure to Air Indoor Uncontrolled Barrier CNT-CS-Carbon Steel Structural Equipment Hatch Exposed Support to Air Indoor Uncontrolled CNT-CS-Carbon Steel Structural Exposed to Air with Pressure Borated Water Leakage Barrier CNT-CS-Carbon Steel Structural Exposed to Air with Borated Water Leakage Support CNT-CS-Carbon Steel Structural Exposed to Air with Pressure Borated Water Leakage for Barrier HVAC Penetrations CNT-CS-Carbon Steel Exposed to Air with Structural Borated Water Leakage for Support HVAC Penetrations Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation ' r :1: Aging Effect Requiring Environment Management Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Aging NU REG *Table. Management 1801 Vol. 2 3.X.1 Note Program Item Item ASME Section ll.A3-6 XI, Subsection (C-16) 3.5.1-18 A IWE Program ASME Section ll.A3-6 XI, Subsection (C-16) 3.5. 1-18 A IWE Program Boric Acid lll.B2-11 (T-Corrosion 3.5.1-55 A Program 25) Boric Acid lll.B2-11 (T-Corrosion 3.5.1-55 A Program 25) Boric Acid Corrosion lll.B2-11 (T-3.5.1-55 A Program 25) Boric Acid Corrosion lll.B2-11 (T-3.5.1-55 A Program 25)

SBK-L-17155 I Enclosure 2/ Page 83 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Carbon Steel Structural Exposed to Air Indoor Pressure Uncontrolled Barrier CNT-CS-Carbon Steel Structural Exposed to Air Indoor Support Uncontrolled CNT-CS-Carbon Steel Structural Exposed to Air Indoor Pressure Uncontrolled For HVAC Barrier Penetrations CNT-CS-Carbon Steel Exposed to Air Indoor Structural Uncontrolled For HVAC Support Penetrations CNT-CS-Carbon Steel Mechanical (Piping) Structural Penetration Exposed to Air Pressure with Borated Water Barrier Leakage CNT-CS-Carbon Steel Mechanical (Piping) Structural Penetration Exposed to Air with Borated Water Support Leakage I Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management .. Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Aging NU REG Table ,y; Management 1801 Vol. 2 3.X.1 Note

Program Item Item 1. + ASME Section ll.A1-11 XI, Subsection (C-09) 3.5.1-6 A IWE Program ASME Section ll.A1-11 XI, Subsection (C-09) 3.5.1-6 A IWE Program ASME Section XI, Subsection ll.A3-1 3.5.1-18 A IWE Program (C-12) ASME Section XI, Subsection ll.A3-1 3.5.1-18 A IWE Program (C-12) Boric Acid lll.B2-11 (T-Corrosion 3.5.1-55 A Program 25) Boric Acid lll.B2-11 (T-Corrosion 3.5.1-55 A Program 25)

SBK-L-17155 I Enclosure 2/ Page 84 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Carbon Steel Structural Mechanical (Piping) Pressure Penetration Exposed to Air Barrier Indoor Uncontrolled CNT-CS-Carbon Steel Mechanical (Piping) Structural Penetration Exposed to Air Support Indoor Uncontrolled CNT-CS-Carbon Steel Structural Personnel Hatch Exposed Pressure to Air with Borated Water Barrier Leakage CNT-CS-Carbon Steel Personnel Hatch Exposed Structural to Air with Borated Water Support Leakage CNT-CS-Carbon Steel Structural Personnel Hatch Exposed Pressure to Air Indoor Uncontrolled Barrier CNT-CS-Carbon Steel Structural Personnel Hatch Exposed Support to Air Indoor Uncontrolled Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation + . J'I 'lili1, "' 1:1+ Hl1l;ii! *,,. , 1:*' . I' Environment ' 1 ** : ... "1* 1*11.p::.Management.1,1,11,,"," 111 . :L 1-1.I:, *:1 i< , i: ir J ,, ,,, .. ,:,:1,. ir:1:1r ,,1, , ,, Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) . Aging , NU REG Table +, 111Management 1801if\'ol::2j.1:I 1:1nll 3'.x.1 *I "' Npte :1::t1,:, r , *I* ii: :*ii 1111i!l1tem**ji111 :!11 .':Iii, j"J!li!j11111 ltem1l1 '11 I' **,*1*j*I Ill ASME Section XI, Subsection ll.A3-1 3.5.1-18 A IWE Program (C-12) ASME Section XI, Subsection ll.A3-1 3.5.1-18 A IWE Program (C-12) Boric Acid Corrosion lll.B1.1-11 3.5.1-55 A Program (TP-25) Boric Acid Corrosion lll.B1 .1-11 3.5.1-55 A Program (TP-25) ASME Section ll.A3-6 XI, Subsection (C-16) 3.5.1-18 A IWE Program ASME Section ll.A3-6 XI, Subsection (C-16) 3.5.1-18 A !WE Program SBK-L-17155 I Enclosure 2/ Page 85 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Elastomers Structural Electrical Penetration Pressure Assembly Exposed to Air Barrier Indoor Uncontrolled CNT-CS-Mechanical (Piping) Penetration Structural Stainless Steel Flued Head Pressure Exposed to Air Indoor Barrier Uncontrolled CNT-CS-Mechanical (Piping) Penetration Structural Stainless Steel Flued Head Support Exposed to Air Indoor Uncontrolled CNT-CS-Mechanical (Piping) Penetration Structural Stainless Steel Flued Head Pressure Exposed to Air with Barrier Borated Water Leakage CNT-CS-Mechanical (Piping) Penetration Structural Stainless Steel Flued Head Support Exposed to Air with Borated Water Leakage Material Elastomer Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management II ,;: !:1: '" Air Indoor Uncontrolled Loss of Sealing, Leakage Through (External) Containment Air Indoor Uncontrolled Cracking (External) Air Indoor Uncontrolled Cracking (External) Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete . Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item ASME Section XI, Subsection IWE Program, Structures Monitoring ll.A3-7 3.5.1-16 A, E, 520 Program & (C-18) Building Deformation Monitoring Proaram ASME Section ll.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program ASME Section ll.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program Nooe Structures Monitoring lll.B2-9 Program, (TP-4) 3.5.1-59 A, 520 Building Deformation Monitorina SBK-L-17155 I Enclosure 2/ Page 86 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Reinforced Shelter, Concrete Below Grade Protection CNT-CS-Reinforced Structural Concrete Below Grade Support CNT-CS-Reinforced Shelter, Concrete Below Grade Protection CNT-CS-Reinforced Structural Concrete Below Grade Support Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management' Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) Soil (External) Expansion and Cracking Soil (External) Expansion and Cracking Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item *Item Program ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ll.A1-3 A, E, Monitoring (C-04) 3.5.1-15 517, 519 Program Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program ll.A1-3 A, E, (C-04) 3.5.1-15 517, 519 Alkali-Silica Reaction (ASR) Monitorinq SBK-L-17155 I Enclosure 21 Page 87 U.S. Nuclear Regulatory Commission *1: i*'I I* Intended Component Type ' Function ' CNT-CS-Reinforced Shelter, Concrete Below Grade Protection CNT-CS-Reinforced Structural Concrete Below Grade Support CNT-CS-Reinforced Shelter, Concrete Below Grade Protection CNT-CS-Reinforced Structural Concrete Below Grade Support ' Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation 'J:i Aging Effect Requiring 'Environment,,J.I: I *l*M I . Management I*! ' 1 I 111:1 1*1:1n, Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Soil (External) Permeability, Loss of Strength Increase in Porosity and Soil (External) Permeability, Loss of Strength .I I'." I :1:,I Aging1 NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item .,.,. Program Building Deformation Monitoring Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5.1-1 A, 516 IWL Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5. 1-1 A, 516 IWL Program ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ll.A1-6 A, 509, Monitoring 3.5.1-15 516, E, Program (C-02) 517, 519 Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program ll.A1-6 A, 509, (C-02) 3.5.1-15 516, E, Alkali-Silica 517, 519 Reaction (ASR) Monitorinq SBK-L-17155 I Enclosure 21 Page 88 U.S. Nuclear Regulatory Commission :'!' 1.1 Component Type Intended Function CNT-CS-Stainless Steel Electrical Penetration Structural Assembly Exposed to Air Pressure with Borated Water Barrier Leakage CNT-CS-Stainless Steel Electrical Penetration Structural Assembly Exposed to Air Pressure with Borated Water Barrier Leakage CNT-CS-Stainless Steel Structural Electrical Penetration Assembly Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CS-Stainless Steel Electrical Penetration Structural Assembly Exposed to Air Support Indoor Uncontrolled I' ,', Material. Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation 1;1:, 1l1111,l1l*!li:;:1!v ' , .,, Environment11:11;, Aging Effect Requiring *j}l{l'.IH *il'I ,Management ' ,I: ,. :I* ,,, m11'i'1it' .,,,w111:1 :11, :Iii ,,,1,1111"1 "': 11111., *' Nooe Reduction in structural capacity Air w/Borated Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Air Indoor Uncontrolled Cracking (External) Air Indoor Uncontrolled Cracking (External) ,, Table 1:l,p1 Aging NU REG Management 1801 Vol. 2 3.X.1 Note I, + Program 1,1,tel'Tl

Item '* Program Building Deformation Monitoring Program Nooe Structures Monitoring Program, Building lll.B2-9 3.5. 1-59 A, 520 Deformation (TP-4) Monitoring Program Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5. 1-59 A, 520 Deformation Monitoring Program ASME Section ll.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program ASME Section XI, Subsection 11.A3-2 3.5.1-10 A (C-15) IWE Program SBK-L-17155 I Enclosure 2/ Page 89 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Stainless Steel Exposed to Air with Shielding Borated Water Leakage CNT-CS-Stainless Steel Structural Exposed to Air with Support Borated Water Leakage CNT-CS-Stainless Steel Exposed to Air Indoor Shielding Uncontrolled CNT-CS-Stainless Steel Structural Exposed to Air Indoor Support Uncontrolled CNT-CS-Stainless Steel Fuel Transfer Tube Expansion I Bellows Exposed to Air Separation with Borated Water Leakage Material Stainless Steel Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring , Environment Management Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Air Indoor Uncontrolled Cracking (External) Air Indoor Uncontrolled Cracking (External) Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Aging NU REG Table Management 1801 'Vol. 2 3.X.1 Note Program Item Item* Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program ASME Section 11.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program ASME Section ll.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program SBK-L-1715 5 I Enclosure 2/ Page 90 U.S. Nuclear Regulatory Commission , '" I :, Component Type I ,,. Function "' CNT-CS-Stainless Steel Fuel Transfer Tube Structural Bellows Exposed to Air Pressure with Borated Water Barrier Leakage CNT-CS-Stainless Steel Fuel Transfer Tube Expansion I Bellows Exposed to Air Separation Indoor Uncontrolled CNT-CS-Stainless Steel Structural Fuel Transfer Tube Bellows Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CS-Stainless Steel Fuel Transfer Tube Structural Exposed to Air with Pressure Borated Water Leakage Barrier :I ,1*,1,,: ,I, l .. w . . . . 11:-1 Material, '1!11 :l:.::!11 I Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation I Environment Aging Effect Requiring Management Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Air Indoor Uncontrolled Cracking (External) Air Indoor Uncontrolled Cracking (External) Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete " ' 11 I I: 11"1111' II 'ii ":. ,:,11 :1*'1:1 ,'l'I ', Ii IJ}ging i I l . 1w11Table i: ,1JI ;!:1 -11111::*' :i,; "1 1l1ao'111vo1I. 2 Note1*,: Progr,aT ' II ' Item Item' .1:1: 1'1 '111'1;:*!:1!! Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program ASME Section XI, Subsection ll.A3-2 3.5.1-10 A IWE Program (C-15) ASME Section ll.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 91 U.S. Nuclear Regulatory Commission Component Type CNT-CS-Stainless Steel Fuel Transfer Tube Exposed to Air with Borated Water Leakage CNT-CS-Stainless Steel Fuel Transfer Tube Exposed to Air Indoor Uncontrolled CNT-CS-Stainless Steel Fuel Transfer Tube Exposed to Air Indoor Uncontrolled CNT-CS-Thermal Insulation Stainless Steel Jacketing in Air with Borated Water Leakage Intended Function Structural Support Structural Pressure Barrier Structural Support Structural Support Material Stainless Steel Stainless Steel Stainless Steel Stainless Steel CNT-CS-Reinforced Concrete Exposed to Raw Water Missile Barrier I Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation .. ' 1'f1 1**' 1:1." Environment :11 ;j.' if, . Aging ,Effect Requiring 1 ' *1 ' *11 111* 111 1Mariagement i: , ,, 11:1 :1',I! <I; Air w/Borated Water Leakage (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air w/Borated Water Leakage Raw Water (External) Nooe Reduction in structural capacity directly. Indirectly due to expansion and cracking of concrete Cracking Cracking Nooe Reduction in structural capacity directly. Indirectly due to expansion and cracking of concrete Cracking due to expansion/ reaction with aggregates Aging Management Program Nooe Structures Monitoring Program, Building Deformation Monitoring Program ASME Section XI, Subsection !WE Program ASME Section XI, Subsection !WE Program Nooe Structures Monitoring Program, Building Deformation Monitoring Program ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) Monitoring ProQram NU REG 1801 Vol. 2 lll.B2-9 (TP-4) ll.A3-2 (C-15) ll.A3-2 (C-15) lll.B2-9 (TP-4) ll.A1-3 (C-04) Table 3.X.1 Item Note 3.5.1-59 I A, 520 3.5.1-10 I A 3.5.1-10 I A 3.5.1-59 3.5.1-15 A, 520 A E, 517 519 SBK-L-17155 I Enclosure 2/ Page 92 U.S. Nuclear Regulatory Commission Intended Component Function CNT-CS-Reinforced Shelter, Concrete Exposed to Raw Protection Water CNT-CS-Reinforced Structural Concrete Exposed to Raw Pressure Water Barrier CNT-CS-Reinforced Structural Concrete Exposed to Raw Support Water Material Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation ii ,!:i::l!,.,liJ* I '. Aging Effect Requiring I I I ' : I : ' I Environment ,, I Management ., 'I' ill I' Raw Water Cracking due to expansion/ (External) reaction with aggregates Raw Water Cracking due to expansion/ (External) reaction with aggregates Raw Water Cracking due to expansion/ (External) reaction with aggregates I* I

1:i'11:1r1I Aging NU REG Table ;:1"':11::1:: Management 1801 Vol. 2 3.X.1

Note :'HI Program Item Item . 1:1 'i'I Building Deformation Monitoring Program ASME Section XI, Subsection IWL Program A Alkali-Silica Reaction (ASR) ll.A1-3 E, 517 Monitoring 3.5.1-15 Program (C-04) Building E, 519 Deformation Monitoring Program ASME Section XI, Subsection A IWL Program Alkali-Silica Reaction (ASR) ll.A1-3 Monitoring 3.5.1-15 Program (C-04) Building E, 517 Deformation E, 519 Monitoring Proaram ASME Section A XI, Subsection IWL Program ll.A1-3 3.5.1-15 (C-04) Alkali-Silica Reaction (ASR) E, 517 SBK-L-17155 I Enclosure 2/ Page 93 U.S. Nuclear Regulatory Commission :i*i 'i*I :h *1:1:;:111 Intended 1 Component Type. Function I:! ':i Standard Notes ' :ij: Material Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation I! 'i'i!ii:jtl'll 111 :lllt1 :I:' l'i 'II i'!,, Aging Effect Requiring H Environment Management '!:.:i:'.!'.l:;;i:1:::. ' Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Note Description Ii', ,, 'j"I . 11r1' II ' Ill 11 'II 'Aging H li!:111 11:1111NUREGli1,:' I iii ,:1*1 ***:'(I I :. *1 1' :*'*'!'I' Managem,ent '1,1

118011Yio1. 2, Program 1*11tem Monitoring Program Building Deformation Monitoring Program 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. i:llhable1 I 1.,3:x.1 l1 II

Item 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. 1:: 111 Ill di I Note. . J, *Ir r* I ' I 1 1ll':.,;1:li,'I E, 519 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.

SBK-L-17155 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-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. 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. 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 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 95 U.S. Nuclear Regulatory Commission Component Type Intended Function MYS -Aluminum STATION Structural BLACKOUT STRUCTURES Support Exposed to Weather MYS -Aluminum STATION Structural BLACKOUT STRUCTURES Support Exposed to Weather MYS -Carbon Steel CONTROL ROOM MAKEUP Structural AIR INTAKE STRUCTURE Support Air Indoor Uncontrolled MYS -Carbon Steel CONTROL ROOM MAKEUP Structural AIR INTAKE STRUCTURE Support Exposed to Weather MYS -Carbon Steel Door ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Carbon Steel Door ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring Material Environment Management Air Outdoor Aluminum (External) Crack Initiation and Growth Air Outdoor Aluminum Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Structures 111.82-7 Monitoring 3.5.1-50 H, 514 Program (Tp-6) Structures 111.82-7 Monitoring 3.5.1-50 A Program (TP-6) Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11)

SBK-L-17155 I Enclosure 2/ Page 96 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Carbon Steel Door STATION BLACKOUT Structural STRUCTURES Air Indoor Support Uncontrolled MYS -Carbon Steel Door STATION BLACKOUT Structural STRUCTURES Exposed to Support Weather MYS -Carbon Steel ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Carbon Steel ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather MYS -Carbon Steel NON SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Air Indoor Uncontrolled SAFETY RELATED Structural ELECTRICAL MANHOLES Support Exposed to Weather Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation *I *! :i:w 1 * )I; I Requiring :I: Material Environment , 1:1: 11 I II *.I ,, l'i

Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Aging NU REG Table Mar.iagement . ,1801 Vol. 2 F 11 3.X.1 Note ' , 'Item*'* ' Item' **** "I *I Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures Monitoring lll.A3-12 3.5.1-25 A (T-11) Program Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures 111.A3-12 Monitoring 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11)

SBK-L-17155 I Enclosure 2/ Page 97 U.S. Nuclear Regulatory Commission Component Type Intended Function MYS -Carbon Steel SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Air Indoor Uncontrolled MYS -Carbon Steel SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Exposed to Weather MYS -Carbon Steel SERVICE WATER ACCESS Structural VAULT Air Indoor Support Uncontrolled MYS -Carbon Steel STATION BLACKOUT Structural STRUCTURES Air Indoor Support Uncontrolled MYS -Carbon Steel STATION BLACKOUT Shelter, STRUCTURES Exposed to Protection Weather MYS -Carbon Steel STATION BLACKOUT Structural STRUCTURES Exposed to Support Weather Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ' . 1*1 Aging Effect Requiring Material Environment 1" Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Outdoor Steel (External) Loss of Material ' :1:11:'1 Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note',., Program *' Item Item ... , .. Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11)

SBK-L-17155 I Enclosure 2/ Page 98 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Air Support Indoor Uncontrolled MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Air Support Indoor Uncontrolled MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Air Support Indoor Uncontrolled MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Below Support Grade MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Below Support Grade Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ;/j1: :I: 1 '*1*, !I: 111'J11ili . l* 1 :r Material Environment Aging Effect Requiring '11

Management Air Indoor Cracking, Loss of Bond, Concrete Uncontrolled Loss of Material (Spalling, (External) Scaling) Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss Concrete of Material (Spalling, (External) Scaling) Cracking, Loss of Bond, Ground Water/Soil Loss of Material (Spalling, Concrete (External) Scaling) Ground Water/Soil Concrete Expansion and Cracking (External) ,1 Aging*. NU REG 1 Table * 'Managen:ient 1801 Vol. 2 3:X.1 Note Program Item Item Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Program Structures lll.A3-10 Monitoring 3.5.1-24 A (T-06) Program Structures lll.A3-4 Monitoring 3.5.1-31 A (T-05) Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 3.5.1-27 A, E, Monitoring (T-03) 517, 519 Program & Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 99 U.S. Nuclear Regulatory Commission ' Intended Component Type Function Ill. I,',, MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Below Support Grade MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Below Support Grade MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Below Support Grade MYS -Concrete CONTROL ROOM MAKEUP AIR INTAKE STRUCTURE Missile Barrier Exposed to Weather MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Support Exposed to Weather MYS -Concrete CONTROL ROOM MAKEUP AIR Missile Barrier INTAKE STRUCTURE Exposed to Weather Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ,i.,1:1 . n , , i'I '*' I.Ii/Aging Material Environment 11111:1 11:1 l,1[Jl )1:1 1 ifr , II '** " ,.,:1:i,1l:i, 1:1 :IJ :1:1 Increase in Porosity and Ground Water/Soil Permeability, Cracking, Loss Concrete (External) of Material (Spalling, Scaling) Ground Water/Soil Increase in Porosity and Concrete (External) Permeability, Loss of Strength Ground Water/Soil Concrete (External) Loss of Material, Cracking Air Outdoor Cracking, Loss of Bond, Concrete (External) Loss of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Concrete (External) Loss of Material (Spalling, Scaling) Concrete Air Outdoor (External) Expansion and Cracking Aging NUREG Table 1'11 Management 1801 Vol. 2 , :*13.X.1 Note 11' 11 1111* 111lil'1'lteni,ll, :111:i ,I fil,j lteryt1,tll'i Iii ,,1 *i** 111 *1 '.,: **1+ *:I Structures 111.A3-5 Monitoring 3.5.1-31 A Program (T-07) Structures lll.A3-7 Monitoring 3,5.1-32 A, 509 Program (T-02) Structures 111.A3-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitorinq SBK-L-17155 I Enclosure 2/ Page 100 U.S. Nuclear Regulatory Commission i'l":I ' l:i Intended Component Type Function MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Support Exposed to Weather MYS -Concrete CONTROL ROOM MAKEUP AIR Missile Barrier INTAKE STRUCTURE Exposed to Weather MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Support Exposed to Weather MYS -Concrete CONTROL ROOM MAKEUP AIR INTAKE STRUCTURE Missile Barrier Exposed to Weather i'),1 '1:1 Ir Material Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring ' Environment Management 1il1iil 1!1'1.: 11:1J!:i:' "' "'"' lil'*!I' * I Air Outdoor Expansion and Cracking (External) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking ., '* Table' ' l'!J l:!!:!,1 11.i.*:*:f:: I Aging NU REG ill Management 1801 Vol. 2 3.X.1 Note111 , Program Item I.tern ,, :1 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-24 A (T-06) Program Structures Monitoring lll.A3-10 3.5.1-24 A (T-06) Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program SBK-L-17155 I Enclosure 2/ Page 101 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Support Exposed to Weather MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Fire Barrier TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Fire Barrier TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Fire Barrier TANK Air Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation 1: ,1. '* Aging Effect Requiring Environment Management Air Outdoor (External) Loss of Material, Cracking Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Uncontrolled Loss of Material (Spalling, (External) Scaling) Air Indoor Cracking, Loss of Bond, Uncontrolled Loss of Material (Spalling, (External) Scaling) Air Indoor Concrete Cracking and Uncontrolled (External) Spalling I 'I' 1* I 'I* *:1:1* 1:' '1, NUREG1' :I 1Agjng :1: Tablet ,1: Management

1,1801 Vol'. 2 '3.X.1 Note Program Item item Structures Monitoring 111.A3-6 (T-01) 3.5. 1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures Monitoring lll.A3-9 (T-04) 3.5. 1-23 A Program Structures Monitoring lll.A3-9 (T-04) 3.5.1-23 A Program Fire Protection Vll.G-28 Program (A-90) 3.3. 1-65 A SBK-L-17155 I Enclosure 2/ Page 102 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Fire Barrier TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Fire Barrier TANK Air Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation . Environment Aging Effect Requiring Management Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) 'l'I I I ' FAging NU REG Table . Management 1801 Vol. 2 3.X.1 Note Program Item Item Fire Protection Vll.G-28 Program (A-90) 3.3. 1-65 A Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 A, E, Program & (T-03) 3.5.1-27 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 A, E, Program & (T-03) 3.5. 1-27 517, 519 Building Deformation Monitoring Program Fire Protection lll.A3-10 Program (T-06) 3.5. 1-24 E, 513 SBK-L-17155 I Enclosure 2/ Page 103 U.S. Nuclear Regulatory Commission Component Type Intended Function' MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Structural TANK Air Indoor Support Uncontrolled MYS -Concrete ENCLOSURE FOR Fire Barrier CONDENSATE STORAGE TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Below Grade MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation I ' 'l'!'I: I <I l:ji ,:i:' I'* ,1;!111f1:':!il Environment

Aging 1

I Management

11 ', ;* ,1 :rl:1*1 Increase in Porosity and Air Indoor Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of Material (Spalling, (External) Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of Material (Spalling, (External) Scaling) Cracking, Loss of Bond, Ground Water/Soil (External) Loss of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) I ;1,l!'FA '. I' . rlilt NUREd1l:11'w 'I' !*I I * ,,jll' "I' I '*I". *I l:1:i }'4ote *** ,Managemer:it 2111. , 1: 1 1'1, 111 1'11,11'+11'11 ,,. 'Hill . 'ltem'I;;. . "i ' ),. 1* 1* ' *:1* I .L,.I*, 1:1!,f,l:.:!1, ', ,* "'I I *:I* 11fili Fire Protection lll.A3-10 3.5. 1-24 E, 513 Program (T-06) Structures Monitoring lll.A3-10 3.5. 1-24 A (T-06) Program Structures Monitoring lll.A3-10 3.5. 1-24 A (T-06) Program Structures lll.A3-4 Monitoring (T-05) 3.5. 1-31 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5. 1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 104 U.S. Nuclear Regulatory Commission Component Type Intended Function MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Below Grade MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Below Grade MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Below Grade MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Missile Barrier TANK Exposed to Weather MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather MYS -Concrete ENCLOSURE FOR Missile Barrier CONDENSATE STORAGE TANK Exposed to Weather Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation l*I *'* ,I, Aging Effect Requiring Environment Management Increase in Porosity and Ground Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Water/Soil Increase in Porosity and Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Air Outdoor Cracking, Loss of Bond, Loss of Material (Spalling, (External) Scaling) Air Outdoor Cracking, Loss of Bond, Loss of Material (Spalling, (External) Scaling) Air Outdoor (External) Expansion and Cracking Aging* NU REG' Table I: Management 1801 Vol. 2 3.X:1' Note Program Item Item Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring 3.5. 1-32 A, 509 (T-02) Program Structures lll.A3-6 Monitoring 3.5. 1-26 A Program (T-01) Structures 111.A3-9 Monitoring 3.5. 1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5. 1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5. 1-27 517, 519 Program & Building Deformation Monitorinq SBK-L-17155 I Enclosure 2/ Page 105 U.S. Nuclear Regulatory Commission I 'I ,,, Intended Component Type Function MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather MYS -Concrete ENCLOSURE FOR Missile Barrier CONDENSATE STORAGE TANK Exposed to Weather MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather MYS -Concrete ENCLOSURE FOR Missile Barrier CONDENSATE STORAGE TANK Exposed to Weather :j' Materia1i'I ii , Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring , Environment " Mana,gement ' ii! ni 11: Air Outdoor Expansion and Cracking (External) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) : :, I l*I;! NU REG Table 1'1'fI:' Aging '"'Ti Management 1801 Vol. 2 3.X.1 Note1',:: ,: Program Item Item ,*,i:,: Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-24 A (T-06) Program Structures Monitoring lll.A3-10 3.5.1-24 A Program (T-06) Stru'ctu res Monitoring lll.A3-6 3.5.1-26 A (T-01) Program SBK-L-17155 I Enclosure 21 Page 106 U.S. Nuclear Regulatory Commission '.;, l'i' .' 1.ntended 1 Component I ',Function MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather MYS -Concrete Masonry Unit (CMU) STATION BLACKOUT Fire Barrier STRUCTURES Exposed to Weather MYS -Concrete Masonry Unit (CMU) STATION BLACKOUT Structural STRUCTURES Exposed to Support Weather MYS -Concrete Masonry Unit (CMU) STATION BLACKOUT Fire Barrier STRUCTURES Exposed to Weather MYS -Concrete Masonry Unit (CMU) STATION BLACKOUT Structural STRUCTURES Exposed to Support Weather MYS -Concrete NON SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Air Indoor Uncontrolled Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effe.ct Requiring Material Environment Management . I i ' Concrete Air Outdoor Loss of Material, Cracking (External) Concrete Air Outdoor Cracking Block (External) Concrete Air Outdoor Cracking BLOCK (External) Concrete Air Outdoor Cracking Block (External) Concrete Air Outdoor Cracking BLOCK (External) Air Indoor Cracking, Loss of Bond, Concrete Uncontrolled Loss of Material (Spalling, (External) Scaling) ' " '"*l'J ,' ,: 111*.111'1.1.1.JiT ,:i:i:,:.: 1:lf'l11NUREG Table '* 1'u"' ]Y'*. n1:,lf1 , *)Aging i<:: Management I . 1801 Vol. 2 3.X.1 Note"'i'. Program Item Item ';i:: Structures Monitoring 111.A3-6 3.5. 1-26 A (T-01) Program Fire Protection lll.A3-11 3.5.1-43 E, 513 Program (T-12) Fire Protection lll.A3-11 3.5.1-43 E,513 Program (T-12) Structures Monitoring lll.A3-11 3.5.1-43 A, 511 (T-12) Program Structures Monitoring lll.A3-11 3.5.1-43 A, 511 (T-12) Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program SBK-L-17155 I Enclosure 2/ Page 107 U.S. Nuclear Regulatory Commission Intended Component Ty,pe Function MYS -Concrete NON SAFETY RELATED ELECTRICAL DUCT Structural BANKS/MANHOLES Air Support Indoor Uncontrolled MYS -Concrete NON SAFETY RELATED ELECTRICAL DUCT Structural BANKS/MANHOLES Air Support Indoor Uncontrolled MYS -Concrete NON SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Below Grade MYS -Concrete NON SAFETY RELATED ELECTRICAL DUCT Structural BANKS/MANHOLES Below Support Grade MYS -Concrete NON SAFETY RELATED ELECTRICAL DUCT Structural BANKS/MANHOLES Below Support Grade MYS -Concrete NON SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Below Grade Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ' Ir I IJ 1;fi i"1111 J:ij\1111+1,, Agirig Effect Requiring .Material Management ;,J;I: ' I l'i Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Increase in Porosity and Air Indoor Concrete Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Water/Soil Cracking, Loss of Bond, Concrete (External) Loss of Material (Spalling, Scaling) Concrete Ground Water/Soil Expansion and Cracking (External) Increase in Porosity and Concrete Ground Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Water/Soil Increase in Porosity and Concrete (External) Permeability, Loss of Strength iwi,I . , '1 i 11:1: 'l'I ','":I: Wrable'r 'j, :11!, I I J}ging I.: ii ;j: : 1 1r: NURE!3* !Ii Management ' r1801Vol.2* 3.X.1 Note Program Item Item ., . r Structures Monitoring Program, Alkali-Silica Reaction lll.A3-2 3.5. 1-27 A, E, (ASR) (T-03) 517 Monitoring Program Structures Monitoring IIl.A3-10 3.5.1-24 A Program (T-06) Structures lll.A3-4 Monitoring (T-05) 3.5. 1-31 A Program Structures Monitoring Program, Alkali-Silica Reaction IIl.A3-2 3.5. 1-27 A, E, (ASR) (T-03) 517 Monitoring Program Structures Monitoring lll.A3-5 3.5. 1-31 A Program (T-07) Structures lll.A3-7 Monitoring (T-02) 3.5. 1-32 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 108 U.S. Nuclear Regulatory Commission Cpmponent Type Intended Function MYS -Concrete NON SAFETY RELATED Structural ELECTRICAL DUCT BANKS/MANHOLES Below Support Grade MYS -Concrete NON SAFETY RELATED Structural MANHOLES Exposed to Support Weather MYS -Concrete NON SAFETY RELATED Structural MANHOLES Exposed to Support Weather MYS -Concrete NON SAFETY RELATED Structural MANHOLES Exposed to Support Weather MYS -Concrete NON SAFETY RELATED Structural MANHOLES Exposed to Support Weather MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Air Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment i'I'" 1l'l1 Management 1:1.,,, '" l:i Ground Water/Soil (External) Loss of Material, Cracking Air Outdoor Cracking, Loss of Bond, Loss of Material (Spalling, (External) Scaling) Air Outdoor Expansion and Cracking (External) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Air Indoor Cracking, Loss of Bond, Uncontrolled Loss of Material (Spalling, (External) Scaling) Aging NU REG Table Management 1801 Vol. 2 1 Note* .. , Program .Item 1,: ' Item 1.* Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures 111.A3-9 Monitoring 3.5.1-23 (T-04) A Program Structures Monitoring Program, Alkali-lll.A3-2 Silica Reaction 3.5.1-27 A, E, (ASR) (T-03) 517 Monitoring Proqram Structures lll.A3-10 Monitoring 3.5.1-24 A (T-06) Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures Monitoring lll.A3-9 3.5.1-23 (T-04) A Program SBK-L-17155 I Enclosure 2/ Page 109 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Air Indoor Uncontrolled MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Air Indoor Uncontrolled MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Below Grade MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Below Grade Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation +Fl"" 111!1 A'gi'ng Effect Requiring Material Environment Management Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Concrete Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Cracking, Loss of Bond, Ground Water/Soil Concrete (External) Loss of Material (Spalling, Scaling) Concrete Ground Water/Soil Expansion and Cracking (External) 1, Aging 1 .. 'I *+ ,1 111 Management 1

18011Vol. 2 3.X.1 Note , Program *1 *Item Item ,*1:11 Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring 111.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring 111.A3-10 3.5. 1-24 A Program (T-06) Structures 111.A3-4 Monitoring (T-05) 3.5. 1-31 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5. 1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 110 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Below Grade MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Below Grade MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Below Grade MYS -Concrete SAFETY RELATED MANHOLES Missile Barrier Exposed to Weather MYS -Concrete SAFETY Structural RELATED MANHOLES Support Exposed to Weather MYS -Concrete SAFETY RELATED MANHOLES Missile Barrier Exposed to Weather Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring , Environment Management Increase in Porosity and Ground Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Increase in Porosity and Ground Water/Soil (External) Permeability, Loss of Strength Ground Water/Soil (External) Loss of Material, Cracking Air Outdoor Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) ,f Aging NU REG Table 1ITll *N.ole'I: I Management' 1801 Vol. 2 3.X.1 Program Item Item Structures Monitoring lll.A3-5 3.5.1-31 A (T-07) Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 3.5.1-27 A, E, Monitoring (T-03) 517, 519 Program & Building Deformation Monitoring SBK-L-17155 I Enclosure 2/ Page 111 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete SAFETY RELATED MANHOLES Structural Exposed to Weather Support MYS -Concrete SAFETY RELATED MANHOLES Missile Barrier Exposed to Weather MYS -Concrete SAFETY RELATED MANHOLES Structural Exposed to Weather Support MYS -Concrete SAFETY RELATED MANHOLES Missile Barrier Exposed to Weather Material Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor Expansion and Cracking (External) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-24 A Program (T-06) Structures Monitoring lll.A3-10 3.5.1-24 A Program (T-06) Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program SBK-L-17155 I Enclosure 2/ Page 112 U.S. Nuclear Regulatory Commission Intended Type Function MYS -Concrete SAFETY Structural RELATED MANHOLES Support Exposed to Weather MYS -Concrete SERVICE Structural WATER ACCESS VAULT Air Support Indoor Uncontrolled MYS -Concrete SERVICE WATER ACCESS VAULT Air Structural Support Indoor Uncontrolled MYS -Concrete SERVICE WATER ACCESS VAULT Air Structural Indoor Uncontrolled Support MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment 'I* '*:1:'1!1 Management Air Outdoor (External) Loss of Material, Cracking Air Indoor Cracking, Loss of Bond, Uncontrolled Loss of Material (Spalling, (External) Scaling) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Water/Soil Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) Aging NU REG Table II Management 1801 Vol. 2 3.X.1 ,. Note Program Item Item Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring 111.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-24 A Program (T-06) Structures 111.A3-4 Monitoring (T-05) 3.5.1-31 A Program SBK-L-17155 I Enclosure 2/ Page 113 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Below Grade MYS -Concrete SERVICE WATER ACCESS VAULT Structural Below Grade Support MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Below Grade MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Below Grade MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Exposed to Raw Water Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation :1; :1: Environment Aging Effect Requiring ' Management Ground Water/Soil (External) Expansion and Cracking Increase in Porosity and Ground Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Water/Soil Increase in Porosity and (External) Permeability, Loss of Strength Ground Water/Soil (External) Loss of Material, Cracking Raw Water Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) 'I. , ,,, , 'NUREG 1Table *I 18011\(ol. 2 3.X.1 Note Program Item Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A,E517, Monitoring (T-03) 3.5. 1-27 519 Program & Building Deformation Monitoring Proqram Structures Monitoring lll.A3-5 3.5. 1-31 A Program (T-07) Structures lll.A3-7 Monitoring (T-02) 3.5. 1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 114 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Exposed to Raw Water MYS -Concrete STATION Structural BLACKOUT STRUCTURES Support Below Grade MYS -Concrete STATION BLACKOUT STRUCTURES Structural Below Grade Support MYS -Concrete STATION BLACKOUT STRUCTURES Structural Below Grade Support Material Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation II I Aging Effect Requiring Environment Management Raw Water (External) Expansion and Cracking Ground Water/Soil Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) Increase in Porosity and Ground Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item r1 Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Proqram Structures 111.A3-4 Monitoring (T-05) 3.5.1-31 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-5 3.5.1-31 A Program (T-07) ---

SBK-L-17155 I Enclosure 2/ Page 115 U.S. Nuclear Regulatory Commission Intended Component Type *Function MYS -Concrete STATION Structural BLACKOUT STRUCTURES Support Below Grade MYS -Concrete STATION Structural BLACKOUT STRUCTURES Support Below Grade MYS -Concrete STATION Structural BLACKOUT STRUCTURES Support Exposed to Weather MYS -Concrete STATION BLACKOUT STRUCTURES Structural Exposed to Weather Support MYS -Concrete STATION BLACKOUT STRUCTURES Structural Exposed to Weather Support MYS -Concrete STATION Structural BLACKOUT STRUCTURES Support Exposed to Weather Material 1* Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ':l"!i' I r I h1.';i:I:!, 11 I'. 1<'lill' ill1 I Aging Effect Requiring Environment . ) .I. Managemeht1 : 'i'l'I <:i r, t l'j T I ; , 1 . ,f, .' ,,i 'TI i" I Ground Water/Soil Increase in Porosity and (External) Permeability, Loss of Strength Ground Water/Soil (External) Loss of Material, Cracking Air Outdoor Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking 1,n'jil 111Aging {*' i1.11 1!'i1*11 INtJREGl' I 1111:* . t I. , .. ,, . ' *, 11'*1

Table ' I : I ' I : I , * * '

I' 1181011i110L 2. '* 1 *" Note . ' ' "'" 11 l 'fl' Item .,. I , . :11 111 Program iii ii i', *.iii! Item' '!',: I ,j.

Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures Monitoring Program, Alkali-Silica lll.A3-2 3.5.1-27 A, E, Reaction (ASR) (T-03) 517 Monitoring Program Structures Monitoring lll.A3-10 3.5.1-24 A Program (T-06) Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program SBK-L-17155/Enclosure2/Page 116 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete Sump CONTROL ROOM MAKEUP Structural AIR INTAKE STRUCTURE Support Exposed to Raw Water MYS -Concrete Sump CONTROL ROOM MAKEUP Structural AIR INTAKE STRUCTURE Support Exposed to Raw Water MYS -Concrete Sump NON SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Exposed to Raw Water MYS -Concrete Sump NON SAFETY RELATED ELECTRICAL DUCT Structural BANKS/MANHOLES Support Exposed to Raw Water MYS -Concrete Sump SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Exposed to Raw Water Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ' Aging Effect Requiring ,1 Material Environment Management Cracking, Loss of Bond, Raw Water Concrete (External) Loss of Material (Spalling, Scaling) Concrete Raw Water Expansion and Cracking (External) Raw Water Cracking, Loss of Bond, Concrete (External) Loss of Material (Spalling, Scaling) Concrete Raw Water Expansion and Cracking (External) Raw Water Cracking, Loss of Bond, Concrete (External) Loss of Material (Spalling, Scaling) . Aging * *:; NUREG ' Table T Management ,, 1801 Vol. 2 3.X.1 Note., Program Item Item Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A, 509 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A, 509 Program Structures Monitoring Program, Alkali-Silica Reaction lll.A3-2 3.5.1-27 A, E, (ASR) (T-03) 517 Monitoring Program Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 117 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete Sump SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Exposed to Raw Water MYS -EPDM Roof ENCLOSURE FOR Shelter, CONDENSATE STORAGE Protection TANK Exposed to Weather MYS -EPDM Roof STATION Shelter, BLACKOUT STRUCTURES Protection Exposed to Weather MYS -Penetration Seal ENCLOSURE FOR Shelter, CONDENSATE STORAGE Protection TANK Exposed to Weather MYS -Seismic Isolation Joint SAFETY RELATED Expansion/ ELECTRICAL DUCT BANKS/MANHOLES Air Separation Indoor Uncontrolled Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring Material Environment Management Raw Water Concrete (External) Expansion and Cracking Separation, Environmental Roofing Air Outdoor Degradation, Water In-(External) Leakage Air Outdoor Separation, Environmental Roofing (External) Degradation, Water In-Leakage Increased Hardness and Elastomer Air Outdoor Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness and Elastomer Uncontrolled Shrinkage and Loss of (External) Strength Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program It.em Item I' Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Proqram Structures Monitoring Program, Building lll.A6-12 3.5.1-44 A, 505, Deformation (TP-7) 520 Monitoring Program Structures lll.A6-12 Monitoring (TP-7) 3.5.1-44 A, 505, Program Structures Monitoring Vll.G-2 3.3.1-61 E, 515 Program (A-20) Structures Vll.G-1 Monitoring 3.3.1-61 E, 515 Program (A-19)

SBK-L-17155 I Enclosure 2/ Page 118 U.S. Nuclear Regulatory Commission ,Intended Component Type,. I*: .. , Function :1' 1*1 " MYS -Stainless Steel ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather Standard Notes 11 1: Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation " ri'.', 1 11:1 i:1' *11 1*, \I:!** Agihg Effect Requiring Material Environment Management Stainless Air Outdoor Loss of Material Steel (External) Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Note Description , 1, , *.* 111r1: 11 illil1t.JuFi.EG I Management 1801 Vol. 2 Program Item Structures Monitoring 111.82-7 (TP-6) Program 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. Table 3.X.1 Item 3.5.1-50 D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. 1,.: .i, 1:11111::J 111 1:1 r Note11:.,.i A 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-17155 /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 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. 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 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 120 U.S. Nuclear Regulatory Commission I*; I' Intended ,*I Component Type ,1.I' Function " PST -(Structural) Fire Proofing -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -(Structural) Fire Proofing -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -(Structural) Fire Proofing -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -(Structural) Fire Proofing -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Built-Up Roofing -COG-Shelter, Exposed to Air Outdoor Protection PST -Built-Up Roofing -EFP-Shelter, Exposed to Air Outdoor Protection Material Non-Metallic Fire-Proofing Non-Metallic Fire-Proofing Non-Metallic Fire-Proofing Non-Metallic Fire-Proofing Roofing Roofing Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation , I i ' 1 11: ifr'*'* iii'.,,,,, ' .. :, l1iil'Agjng Environmerit, ,.i:J, ,11'l'ill'1'i:Jlil1Management I'**** I'll' *fl t*:1:*]!!1'j:!1!" l'l'l'I' ,, .. ij* .11:1 .IJ;l,H!,:ii*1ll 1*l*1u*.::* *i:i *;'::1:1:. ,!:11*'. '.i:l*1 :':1:1:' I l:':'I Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage ,,Aging , ...*. Table NUREG 1801. ' . Management .. , w vo1n:ltemji'.': 111*13.x;1 Note *"I' **

T *Ir .1:11111111 i;;1:111: l!I ,* 1:11.*1111::1 n 11fr1:1ii:;i:1.th1I !;:*: Item 1;<i :';T I:*: ;:t 1:** Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 C, 506 Structures Vll.G-29 Monitoring (A-91) 3.3.1-67 C, 506 Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 C, 506 Structures Vll.G-29 Monitoring (A-91) 3.3.1-67 C, 506 Program Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Program Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505,E, (TP-7) 520 Building Deformation Monitoring SBK-L-17155 I Enclosure 2/ Page 121 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Built-Up Roofing -FSB-Shelter, Exposed to Air Outdoor Protection PST -Built-Up Roofing -PAB-Shelter, Exposed to Air Outdoor Protection PST -Built-Up Roofing -PCEW-Shelter, Exposed to Air Outdoor Protection PST -Built-Up Roofing -PHA-Shelter, Exposed to Air Outdoor Protection Material Roofing Roofing Roofing Roofing Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation " Aging Effect Requiring Environment Management Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Aging Table NUREG 1801 Management Vol. 2 Item 3.X.1 Note Program Item Program Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Program Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Proaram Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E,520 Deformation Monitoring Program Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 122 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Built-Up Roofing -TFA-Shelter, Exposed to Air Outdoor Protection PST -Built-Up Roofing -WPS-Shelter, Exposed to Air Outdoor Protection PST -Carbon Steel -COG-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -COG-Structural Exposed to Air Outdoor Support PST -Carbon Steel -CEHMS-Structural Exposed to Air Outdoor Support PST -Carbon Steel Door -COG-Structural Exposed to Air Indoor Support Uncontrolled Material Roofing Roofing Steel Steel Steel Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Air Indoor Uncontrolled Loss of Material (External) Air Outdoor (External) Loss of Material Air Outdoor (External) Loss of Material Air Indoor Uncontrolled Loss of Material (External) Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note 1 .' Program Item Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Proqram Structures Monitoring Program 111.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Proqram Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program SBK-L-17155 I Enclosure 2/ Page 123 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Carbon Steel Door -COG-Structural Exposed to Air Outdoor Support PST -Carbon Steel Door -EFP-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel Door -EFP-Structural Exposed to Air Outdoor Support PST -Carbon Steel Door -FSB-HELB Exposed to Air Indoor Shielding Uncontrolled PST -Carbon Steel Door -FSB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel Door -FSB-Structural Exposed to Air Outdoor Support Material* Steel Steel Steel Steel Steel Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor (External) Loss of Material Air Indoor Uncontrolled Loss of Material (External) Air Outdoor (External) Loss of Material Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Outdoor (External) Loss of Material Aging NUREG 1801 Table ':1: t1: Management Vol. 2 Item 3.X.1 Note Program Item Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A5-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A5-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A5-12 Monitoring (T-11) 3.5.1-25 A, 503 Program SBK-L-17155 I Enclosure 21 Page 124 U.S. Nuclear Regulatory Commission I' I Intended 1, I Component Type Function ,, '1*T PST -Carbon Steel Door -FSB-HELB in Air with Borated Water Shielding Leakage PST -Carbon Steel Door -FSB-Structural in Air with Borated Water Support Leakage PST -Carbon Steel Door -PAB-HELB Exposed to Air Indoor Shielding Uncontrolled PST -Carbon Steel Door -PAB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel Door -PAB-Structural Exposed to Air Outdoor Support PST -Carbon Steel Door -PAB-HELB in Air with Borated Water Shielding Leakage Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' 1] 1,1 l.j , ,,1, , ,1:rl , Aging Effect Requiring Material 1' i*ll , 11'1 'Iii' Management " Jiii, I'll ':' ",:, 1y1 I !*Ill I 1111111'1"11 I, li1'1 1111 ,,,, Air w/Borated Steel Water Leakage Loss of Material (External) Air w/Borated Steel Water Leakage Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air w/Borated Steel Water Leakage Loss of Material (External) Aging Table NUREG 1801 Management Vol. 2 Item:, 3.X.1 Note Program Jtem " '"r:!* Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Boric Acid 111.82-11 Program (T-25) 3.5.1-55 A SBK-L-17155 I Enclosure 2/ Page 125 U.S. Nuclear Regulatory Commission Component Type Intended Function PST -Carbon Steel Door -PAB-Structural in Air with Borated Water Support Leakage PST -Carbon Steel Door -HELB PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Carbon Steel Door -Structural PCEW-Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel Door -Structural PCEW-Exposed to Air Outdoor Support PST -Carbon Steel Door -WPB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel Door -WPB-Structural Exposed to Air Outdoor Support Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Material Environment Aging Effect Requiring Management Air w/Borated Steel Water Leakage Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Aging " Table i'I Management NUREG 1801 3.X.1 Note Program Vol. 2 Item Item Boric Acid 111.82-11 Program (T-25) 3.5.1-55 A Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures 111.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12

Monitoring (T-11) 3.5.1-25 A, 503 Program SBK-L-17155 I Enclosure 2/ Page 126 U.S. Nuclear Regulatory Commission Component Type Intended Function PST -Carbon Steel Door -WPB-Structural in Air with Borated Water Support Leakage PST -Carbon Steel -EFP-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -EFP-Shelter, Exposed to Air Outdoor Protection PST -Carbon Steel -EFP-Structural Exposed to Air Outdoor Support PST -Carbon Steel Fire Door -CDG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Carbon Steel Fire Door -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled Material Steel Steel Steel Steel Steel Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,:1* I* Environment Aging Effect Requiring Management Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Outdoor Loss of Material (External) Air Outdoor (External) Loss of Material Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Aging Table Management NUREG 1801 3.X.1 Note Program Vol. 2 Item Item Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures lll.A3-12 Monitoring (T-11) 3.5. 1-25 A, 503 Program Fire Protection Vll.G-3 Program (A-21) 3.3.1-63 A Fire Protection Vll.G-3 Program (A-21) 3.3.1-63 A SBK-L-17155 I Enclosure 2/ Page 127 U.S. Nuclear Regulatory Commission Component Type PST -Carbon Steel Fire Door -FSB-Exposed to Air Indoor Uncontrolled PST -Carbon Steel Fire Door -FSB-in Air with Borated Water Leakage PST -Carbon Steel Fire Door -PAB-Exposed to Air Indoor Uncontrolled PST -Carbon Steel Fire Door -PAB-in Air with Borated Water Leakage PST -Carbon Steel Fire Door -PCEW-Exposed to Air Indoor Uncontrolled PST -Carbon Steel Fire Door -WPB-Exposed to Air Indoor Uncontrolled Intended Function Fire Barrier Fire Barrier Fire Barrier Fire Barrier Fire Barrier Fire Barrier Material Steel Steel Steel Steel Steel Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 'II Environment '11 , ' 1"111 '1*1*11:, Table111 l'I 11n11 Ir j;i ,,, 1 '. Jl*li:11: ',, ' l'I 1: !i b.x.11:111 'I '1,; 1,,1,,li;girig pffect fl.equ,1.rin.g '1,1,,1 *Iii* 1,1vol'Y2]*1*t em l:!,11 Ii lil!11tem'111111, ',, r. , Managementill' 111 :1! , "11111 Program l:j:j' , *ti 1*i:l.1*1*'1*11l1111 , , * * 'i*i' {] 1 l!I: ' I ,, , i;1 Air Indoor Uncontrolled (External) Air w/Borated Water Leakage (External) Air Indoor Uncontrolled (External) Air w/Borated Water Leakage (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Loss of Material Loss of Material Loss of Material Loss of Material Loss of Material Loss of Material Fire Protection Program Boric Acid Program Fire Protection Program Boric Acid Program Fire Protection Program Fire Protection Program Vll.G-3 (A-21) lll.B2-11 (T-25) Vll.G-3 (A-21) lll.B2-11 (T-25) Vll.G-3 (A-21) Vll.G-3 (A-21) 3.3.1-63 A 3.5.1-55 A 3.3.1-63 A 3.5.1-55 A 3.3.1-63 A 3.3.1-63 A SBK-L-17155 I Enclosure 2/ Page 128 U.S. Nuclear Regulatory Commission I Intended Component Type I Function PST -Carbon Steel Fire Door -WPB-in Air with Borated Water Fire Barrier Leakage PST -Carbon Steel -FSB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -FSB-in Air Structural with Borated Water Leakage Support PST -Carbon Steel -PAB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -PAB-Structural Exposed to Air Outdoor Support PST -Carbon Steel -PAB-in Air Structural with Borated Water Leakage Support Material Steel Steel Steel Steel Steel Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation r . . *:r!!ll 1"'.ill Environment'!: I 'I' ' ' ' * "111: ' Management. " 111 I I* .°1!11 11: /11'1 'I* *1il!l*lll: '11i::l'1!1ili11* *:1:1' Air w/Borated Water Leakage Loss of Materfal (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Outdoor (External) Loss of Material Air w/Borated Water Leakage Loss of Material (External) Aging, *:1: Table NUREG 1801 Management voi. 211tem : :1 3:X.1 11' Note * '*' ,': ;;j1tehi , '! I iii! ' ::i1:' \1: Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Structures lll.A5-12 Monitoring (T-11) 3.5.1-25 A Program Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A SBK-L-17155 I Enclosure 2/ Page 129 U.S. Nuclear Regulatory Commission ;11 Intended Component Type 'l1r 'Function *I* I I '*. ' PST -Carbon Steel -PCEW-Exposed to Air Indoor Flood Barrier Uncontrolled PST -Carbon Steel -PCEW-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -PCEW-Structural Exposed to Air Outdoor Support PST -Carbon Steel -PHA-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -PHA-Shelter, Exposed to Air Outdoor Protection PST -Carbon Steel -PHA-Structural Exposed to Air Outdoor Support Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Material Environment Management .*1, Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Outdoor Steel (External) Loss of Material Aging, ' Table

I' I: 'I{ NUREG 1801 ' ... 'I Management Vol. 2 Item 3.X.1 Note1, 1 Program Item ' l 1 ':l: Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures 111.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program SBK-L-17155 I Enclosure 2/ Page 130 U.S. Nuclear Regulatory Commission ' Component Type " 'Intended Function PST -Carbon Steel -TFA-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -TFA-Shelter, Exposed to Air Outdoor Protection PST -Carbon Steel -TFA-Structural Exposed to Air Outdoor Support PST -Carbon Steel -TFA-in Air Structural with Borated Water Leakage Support PST -Carbon Steel -WPB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -WPB-Shelter, Exposed to Air Outdoor Protection ' Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Material Environment Aging Effect Requiring Management Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air w/Borated Steel Water Leakage Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Aging Table :11 Management NUREG 1801 .,. 3.X.1 Note Program Vol. 2 Item Item Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Boric Acid 111.82-11 Program (T-25) 3.5.1-55 A Structures 111.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program SBK-L-17155 I Enclosure 2/ Page 131 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Carbon Steel -WPB-Structural Exposed to Air Outdoor Support PST -Carbon Steel -WPB-in Structural Air with Borated Water Leakage Support PST -Conduit Fire Wrap -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Conduit Fire Wrap -PAB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Conduit Fire Wrap -PAB-in Air with Borated Water Fire Barrier Leakage PST -Conduit Fire Wrap -WPB-Exposed to Air Indoor Fire Barrier Uncontrolled Material1 Steel Steel Aluminum Aluminum Aluminum Aluminum Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor (External) Loss of Material Air w/Borated Water Leakage Loss of Material (External) Air Indoor Nef\e Uncontrolled Deformation/reduction in (External) structural capacity Air Indoor Nef\e Uncontrolled Deformation/reduction in (External) structural capacity Air w/Borated Water Leakage Loss of Material (External)) Nef\e Air Indoor Deformation/reduction in Uncontrolled structural capacity (External) Aging 1:1 Table NUREG 1801 Management Vol. 2 Item I* 3.X.1 Note Program Item :*j*I Structures lll.A3-12 Monitoring (T-11) 3.5. 1-25 A, 503 Program Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Nef\e Building lll.B2-4 Deformation (TP-8) 3.5. 1-58 A, E, 520 Monitoring Program Nef\e Building lll.B2-4 Deformation (TP-8) 3.5. 1-58 A, E, 520 Monitoring Program Boric Acid lll.B2-6 Program (TP-3) 3.5. 1-55 A Nef\e Building lll.B2-4 Deformation (TP-8) 3.5. 1-58 A, E, 520 Monitoring Program SBK-L-17155 I Enclosure 2/ Page 132 U.S. Nuclear Regulatory Commission Component Type PST -Conduit Fire Wrap -in Air with Borated Water Leakage PST -Elastomers Exposed to Air Indoor Uncontrolled PST -Elastomers Exposed to Air Indoor Uncontrolled PST -Elastomers Exposed to Air Outdoor PST -Elastomers Exposed to Air Outdoor PST -Elastomers Exposed to Air Outdoor Intended Function Fire Barrier Control Bldg Habitability Flood Barrier Expansion/ Separation Shelter, Protection Expansion/ Separation Material Aluminum Elastomer Elastomer Elastomer Elastomer Elastomer Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Air w/Borated Water Leakage (External)) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) 111 1:1+ ' *l'l'i'I . *I: .,, :I ilAging Effect'Requiring 1'* 1: Management 1:'; Loss of Material Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Aging Management Program Boric Acid Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program NUREG 1801 Vol. 2 Item lll.B2-6 (TP-3) Vll.G-1 (A-19) Vll.G-1 (A-19) Vll.G-2 (A-20) Vll.G-2 (A-20) Vll.G-2 (A-20) I Table 3.X.1 Item 3.5.1-55 3.3. 1-61 3.3. 1-61 3.3.1-61 3.3. 1-61 3.3.1-61 Note A E, 515 E, 515 E, 515 E, 515 E, 515 SBK-L-17155 I Enclosure 2/ Page 133 U.S. Nuclear Regulatory Commission Component Type PST -Elastomers Exposed to Air Outdoor PST -Elastomers Exposed to Air Outdoor PST -Elastomers Exposed to Air Outdoor PST -Elastomers Exposed to Air Outdoor PST* Elastomers -Exposed to Air Outdoor PST* Elastomers -Exposed to Air Outdoor Intended Function Shelter, Protection Expansion/ Separation Shelter, Protection Expansion/ Separation Shelter, Protection Expansion/ Separation Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation , fl . 'i'I Material 1 Elastomer Elastomer Elastomer Elastomer Elastomer Elastomer ,Environment jl:, :111:1 " *I* Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) Aging Effect Requiring Management Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength ::I" ':l:1:1'.""*l' .. '*h1*1:1' "'1*1*1*," . " 1 :* I'

Table" Program Vol. 2* 1tem 1 3.X.1

Item Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Vll.G-2 (A-20) Vll.G-2 (A-20) Vll.G-2 (A-20) Vll.G-2 (A-20) Vll.G-2 (A-20) Vll.G-2 (A-20) 3.3.1-61 3.3.1 -61 3.3.1-61 3.3.1-61 3.3.1-61 3.3.1-61 11 :11*1 I j!' 1:1' 1Note.1 *, 'I . , E, 515 E, 515 E, 515 E, 515 E, 515 E, 515 SBK-L-17155 I Enclosure 2/ Page 134 U.S. Nuclear Regulatory Commission Intended Com'ponent Type Function PST -Elastomers -PCEW-Shelter, Exposed to Air Outdoor Protection PST -Elastomers -PHA-Expansion/ Exposed to Air Outdoor Separation PST -Elastomers -PHA-Shelter, Exposed to Air Outdoor Protection PST -Elastomers -TFA-Expansion/ Exposed to Air Outdoor Separation PST -Elastomers -TFA-Shelter, Exposed to Air Outdoor Protection PST -Elastomers -WPB-Expansion/ Exposed to Air Outdoor Separation Material Elastomer Elastomer Elastomer Elastomer Elastomer Elastomer Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,1'1'1' Environment . Aging Effect Requiring I, Air Outdoor Increased Hardness, (External) Shrinkage and Loss of Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Aging I Table I ' I ' I : I ; I : ' I ; Management NUREG 1801 3.X.1 II ,ff . Vol. 2 Item Note .. r' Program Item Structures Vll.G-2 Monitoring 3.3. 1-61 E, 515 Program (A-20) Structures Vll.G-2 Monitoring 3.3. 1-61 (A-20) E, 515 Program Structures Vll.G-2 Monitoring 3.3.1-61 Program (A-20) E, 515 Structures Vll.G-2 Monitoring 3.3. 1-61 Program (A-20) E, 515 Structures Vll.G-2 Monitoring 3.3.1-61 E, 515 Program (A-20) Structures Vll.G-2 Monitoring 3.3. 1-61 E, 515 Program (A-20)

SBK-L-17155 I Enclosure 2/ Page 135 U.S. Nuclear Regulatory Commission I I :j* Intended Component Type Function PST -Elastomers -WPB-Shelter, Exposed to Air Outdoor Protection PST -Fire Penetration Seal -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Fire Penetration Seal -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Fire Penetration Seal -FSB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Fire Penetration Seal -PAB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Fire Penetration Seal -PCEW-Exposed to Air Indoor Fire Barrier Uncontrolled I Material Elastomer Elastomer Elastomer Elastomer Elastomer Elastomer Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation *1 1* 11Y*, ; ' ! ' Aging Effect Requiring "111 1 Environment Management I ' l*I* I I I' 'ii T .( 1j: "'I' :l"lli* :1 Air Outdoor Increased Hardness, (External) Shrinkage and Loss of Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength I ,.,., I Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 P.rogram Item I Structures Vll.G-2 Monitoring (A-20) 3.3.1-61 E, 515 Program Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A SBK-L-17155 I Enclosure 2/ Page 136 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Fire Penetration Seal -WPB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Lubrite Plate -PAB-Structural Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Flood Barrier COG-Below Grade PST -Reinforced Concrete -Structural COG-Below Grade Support PST -Reinforced Concrete -COG-Below Grade Flood Barrier Material Elastomer Lubrite Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,. ' 111. ,, Aging Effect Requiring Environment Management Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Uncontrolled Loss of Mechanical Function (External) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) .Table' I Aging NUREG 1801 Management 3.X.1 Note Program Vol. 2 Item Item Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A Structures 111.82-2 Monitoring (TP-1) 3.5.1-52 A Program Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 137 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural COG-Below Grade Support PST -Reinforced Concrete -Flood Barrier COG-Below Grade PST -Reinforced Concrete -Structural COG-Below Grade Support PST -Reinforced Concrete -Flood Barrier COG-Below Grade PST -Reinforced Concrete -Structural COG-Below Grade Support ' Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' Environment Aging Effect Requiring Management Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength ' Aging* 1,,

1*Table1, .. :'I' ' Vol. 2 lteni 3.X.1 Note Program *item Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A1-2 AE, 517, Monitoring (T-03) 3.5.1-27 519 Program Building Deformation Monitoring Proaram Structures lll.A1-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A1-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A1-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A1-7 Monitoring (T-02) 3.5.1-32 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 138 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -COG-Below Grade Flood Barrier PST -Reinforced Concrete -Structural COG-Below Grade Support PST -Reinforced Concrete -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural COG-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural COG-Exposed to Air Indoor Uncontrolled Support :. Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 11 I

Ii II :I l,' I I '. '.' l,f*j:i:;: Environment Agmg Eft'.ect Requmng Management Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) li 1Hi'!1 Aging ' ,, 111Table '"ti I" I 'l'*r,t .*!< j NUREG 1801 . I Management vo1. 21tem'1 .3.X.1 Note Program Item Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04)

SBK-L-17155 I Enclosure 2/ Page 139 U.S. Nuclear Regulatory Commission Component Type ' " Intended Iii Function ij' I ' PST -Reinforced Concrete -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural COG-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural COG-Exposed to Air Indoor Support Uncontrolled Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation , ,, **. l .. , , l {'"'II Material Environment *'Aging I Management ' 11" ' ' ' i ' "I' Air Indoor Concrete Cracking and Concrete Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Concrete Uncontrolled (External) Spalling Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Air Indoor Concrete Uncontrolled Expansion and Cracking (External) I' 'j'l'l'I' ,,1 :!1.1i:!1J:i.11. ::!:*:1:1 1';1;1*::1; [T ,,. , .. 1! I ',, ' Note 'i 1.Management11.j,1 '1111 'vb1t1 '1 1ili:l3.X.tl:i1;' Program'1

1teln * T **,. 'l , :.;1t,:c1,1.1.,:1:*:11, Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring 111.A1-2 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) 111.A1-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 140 U.S. Nuclear Regulatory Commission ,, Intended Component Type Function PST -Reinforced Concrete -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural COG-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Missile Barrier COG-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, COG-Exposed to Air Outdoor Protection PST -Reinforced Concrete -COG-Exposed to Air Outdoor Missile Barrier Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation l , I ' : i'i ,I Aging' Effect Requiring Environment Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking !l ' I 'i' jq ;i':1: ,:hi. .pl:1:1:1:r:*1 .,1 1.1. ti I II Agirig'1:1'!1:1,,11 Tablei:I ,, 'I' ' ,j, ' NUREG '1801 ,, Management ,:, Vol. 2 Item' '\ 3;x.1 * Note Program Item' ,;:1. Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5. 1-24 A Program Structures lll.A1-9 Monitoring 3.5. 1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5. 1-23 A Program (T-04) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring (T-03) 3.5. 1-27 517, 519 Program Building Deformation Monitoring Program SBK-L-17155 /Enclosure2/Page 141 U.S. Nuclear Regulatory Commission I I Component Type Intended Function PST -Reinforced Concrete -Shelter, COG-Exposed to Air Outdoor Protection PST -Reinforced Concrete -COG-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, COG-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier COG-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, COG-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,,,,, I 1l *111 ;.J. *1*1 Environment " Aging Effect Requiring Management Air Outdoor (External) Expansion and Cracking Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) Air Outdoor Loss of Material, Cracking (External) ,j;, 1:. Aging NUREG 1801 Table Management 3.X.1 Note Program Vol. 2 Item Item Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Proa ram Structures lll.A1-10 Monitoring 3.5.1-24 (T-06) A Program Structures lll.A1-10 Monitoring 3.5.1-24 A Program (T-06) Structures lll.A1-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A1-6 Monitoring 3.5.1-26 A Program (T-01)

SBK-L-17155 I Enclosure 2/ Page 142 U.S. Nuclear Regulatory Commission 1:1; / Component Type Intended Function PST -Reinforced Concrete -Structural CDG-Exposed to Raw Water Support PST -Reinforced Concrete -Structural CDG-Exposed to Raw Water Support PST -Reinforced Concrete -Structural CEHMS-Below Grade Support PST -Reinforced Concrete -Structural CEHMS-Below Grade Support Material " Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' Environment Aging Effect Requiring Management ' ' Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water (External) Expansion and Cracking Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) 1

Agir\g' I 'I;: '1111:/'i'lil'*l"I . 'l!I.' ,!1' ti'; 11:11'1 I! r Table' Management , NUREG 1801 3.X.1 Vol. 2 Item Note: .. 1 '/',:l:j: I Program Item ... : *I Structures 111.A1-4 Monitoring 3.5.1-31 A, 512 Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A1-2 A, 512, E Monitoring (T-03) 3.5.1-27 '517, Program 519 Building Deformation Monitoring Proqram Structures 111.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) 111.A3-2 A, E, Monitoring (T-03) 3.5.1 -27 517, 519 Program Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 143 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural CEHMS-Below Grade Support PST -Reinforced Concrete -Structural CEHMS-Below Grade Support PST -Reinforced Concrete -Structural CEHMS-Below Grade Support PST -Reinforced Concrete -CEHMS-Exposed to Air Missile Barrier Outdoor PST -Reinforced Concrete -CEHMS-Exposed to Air Missile Barrier Outdoor Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking 1:1 Ag/ng1 );111: I 1:1 1;; i!li I 111 Table. NUREG 1801 Management Vol. 2 Item 3.X.1 ' Note Program Item Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-9 Monitoring 3.5.1-23 A (T-04) Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-27 (T-03) 517, 519 Program Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 144 U.S. Nuclear Regulatory Commission ! Component "f;ype Intended II', Function " :1 ! PST -Reinforced Concrete -CEHMS-Exposed to Air Missile Barrier Outdoor PST -Reinforced Concrete -CEHMS-Exposed to Air Missile Barrier Outdoor PST -Reinforced Concrete -Flood Barrier EFP-Below Grade PST -Reinforced Concrete -Structural EFP-Below Grade Support PST -Reinforced Concrete -Flood Barrier EFP-Below Grade !1.11' Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation iil:1: IT 11111'1' ['111'1"1' 1'l'l"IT1"1' ! 'llfl :: 11 ,,,,+ 1 * ! : 111:11:+1 .. '1*1<<1'"';1 l'i!l:if'I: Environment Ag1,ng Efl'.ect1Req\J1m'lg'11 fl Management ,, *, Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) 111 11 NUREG'[1sot ii . , : ' I 1'1* 1' Aging .. r I '1:1i:Taplei; . !' ' ],Ill,,, 111 IJl"I fl Note 1*k,Management '1:i 1:*1:i,vol'.:1211i0ln'mJ1, 1 '111P,r6gram,!!l':)l1! 1l1vHl:11111,. "n:u11j::!'1 '"':11:1 : 11 :1:1:1' 1f:.1.,J*i:; Structures lll.A3-10 Monitoring (T-06) 3.5. 1-24 A Program Structures 111.A3-6 Monitoring (T-01) 3.5, 1-26 A Program Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 145 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural EFP-Below Grade Support PST -Reinforced Concrete -Flood Barrier EFP-Below Grade PST -Reinforced Concrete -Structural EFP-Below Grade Support PST -Reinforced Concrete -Structural EFP-Below Grade Support PST -Reinforced Concrete -Structural EFP-Below Grade Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring Management Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength {jAging ':1: .Ii 1*1'1 Table ,, 'I I NUREG 1801 Management Vol. 2 Item 3.X.1 Note Program Item Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proa ram Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program SBK-L-17155 /Enclosure2/Page 146 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -EFP-Below Grade Flood Barrier PST -Reinforced Concrete -Structural EFP-Below Grade Support PST -Reinforced Concrete -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural EFP-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural EFP-Exposed to Air Indoor Uncontrolled Support Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note Program Item .. , Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04)

SBK-L-17155 I Enclosure 2/ Page 147 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural EFP-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural EFP-Exposed to Air Indoor Support Uncontrolled Material ,,, Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,, Aging Effect Requiring Environment Management Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging Table ,,, NUREG 1801 Management Vol. 2 Item 3.X.1 Note Program Item Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 148 U.S. Nuclear Regulatory Commission 1:1 Intended Component Type **Function 'I: PST -Reinforced Concrete -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural EFP-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Missile Barrier EFP-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, EFP-Exposed to Air Outdoor Protection PST -Reinforced Concrete -EFP-Exposed to Air Outdoor Missile Barrier I ,,, Material ii' Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation }I ' 111 1lli ' 1:1 . i:I Ill Jil Aging Effect* Requiring 11i,lll Environment *:I ',11.11 'I" *:1*1

n Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking Aging I I* NUREG 1801 *** Table Management 'Jr3cX; 1 Note * ,, program'l'1iil:1M* . VoL 21itemjj1*1 il'ljl * i.1,I,,., *I L1 .. , iii'] :J!l:ll'I :: 1:IJlil :* iH ltem,)!I' i' Structures lll.A3-10 Monitoring (T-06) 3.5, 1-24 A Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5, 1-23 A Program (T-04) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5, 1-27 517, 519 Program Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 149 U.S. Nuclear Regulatory Commission Intended Component Type, Function PST -Reinforced Concrete -Shelter, EFP-Exposed to Air Outdoor Protection PST -Reinforced Concrete -EFP-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, EFP-Exposed to Air Outdoor Protection PST -Reinforced Concrete -EFP-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, EFP-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' ' ' '"11 ,, ti : ,j1l':11'!! ' Effect Requiring ljj' Environment Management Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Air Outdoor Loss of Material, Cracking (External) 1 ,l*I :li.,4_'i' ,. 'I' , !j:I 1: ,,, Table\' 1:11 ' lI I gmg NUREG 1801 1' 11 Manage'ment ' *Ir 3.x.1 Note Program Vol. 2 Item Item Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring 111.A3-2 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures ll\.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01)

SBK-L-17155 I Enclosure 2/ Page 150 U.S. Nuclear Regulatory Commission ",,,1;, 'I Intended Component Type Function PST -Reinforced Concrete -Structural EFP-Exposed to Raw Water Support PST -Reinforced Concrete -Structural EFP-Exposed to Raw Water Support PST -Reinforced Concrete -Flood Barrier FSB-Below Grade PST -Reinforced Concrete -Structural FSB-Below Grade Support PST -Reinforced Concrete -Flood Barrier FSB-Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ii',' 1:i: ,:1111 1, ' :1;1:* *j*I* ;.:.I*;* . ,:1:: :f*' I:' ' ' i: Environmeht11:1 ,, , i:i,,,l:v:1, 111 g Ji,, 1:1.*," Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water (External) Expansion and Cracking Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) , Aging , ':, _,!11_i:1,,,, 1111:1': Management , ,,.NUREG , ,, ' Iii }I Note ,,,i, ,,:Vol. 2 Item :h ,, Ii' 1:1: ':1111it, 1il'jli1!lli;1 111: Item **' Structures lll.A3-4 Monitoring 3.5.1-31 A, 512 Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) 111.A3-2 A, 512, Monitoring (T-03) 3.5.1-27 E, 517, Program 519 Building Deformation Monitoring Proqram Structures lll.A5-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A5-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program lll.A5-2 A, E, Alkali-Silica 3.5.1-27 Reaction (ASR) (T-03) 517, 519 Monitoring Program SBK-L-17155 I Enclosure 2/ Page 151 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural FSB-Below Grade Support PST -Reinforced Concrete -Flood Barrier FSB-Below Grade PST -Reinforced Concrete -Structural FSB-Below Grade Support PST -Reinforced Concrete -Structural FSB-Below Grade Support Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,, , Aging Effect Requiring Environment Management Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength ': Table :1: Aging ' ' Management

NUREG 1801 3.X.1 Note Vol. 2 Item Program Item Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) 111.A5-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proa ram Structures lll.A5-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A5-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A5-7 Monitoring (T-02) 3.5.1-31 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 152 U.S. Nuclear Regulatory Commission '* Intended Component Type Function I* PST -Reinforced Concrete -Structural FSB-Below Grade Support PST -Reinforced Concrete -FSB-Below Grade Flood Barrier PST -Reinforced Concrete -Structural FSB-Below Grade Support PST -Reinforced Concrete -FSB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural FSB-Exposed to Air Indoor Support Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1:: ', Aging Effect Requiring Environment* ' : , Management ;:I 1:1 . 111'1 .'li'l!I l*11:'"11l:ff 'I *'1'tl1ii' 111 Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Aging NUREG 1801 Table Management Vol .. 2.ltem I 3.X.1 Note ,., ,,,, .,1 Pr9gram , : :j:I I ;' 1 ::::p,., 111:1'i'*'l}*!,:!:1 Structures Ill.AS-? Monitoring (T-02) 3.5.1-31 A, 509 Program Structures 111.AS-6 Monitoring (T-01) 3.5.1-26 A Program Structures 111.AS-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 3.3.1-67 A Program (A-91) Fire Protection Vll.G-29 3.3.1-67 A Program (A-91) Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A SBK-L-17155 I Enclosure 2/ Page 153 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -FSB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural FSB-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -FSB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural FSB-Exposed to Air Indoor Uncontrolled Support Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation :: Aging Effect Requiring ***' ;.;Environment Management Air Indoor Cracking, Loss of Bond, Loss Uncontrolled of Material (Spalling, Scaling) (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled of Material (Spalling, Scaling) (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Concrete Cracking and Uncontrolled Spalling (External) Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Aging NUREG 1801 Table Management 3.X.1 Note ; Program Vol. 2 Item Item Structures lll.A5-9 Monitoring (T-04) 3.5.1-23 A Program Structures lll.A5-9 Monitoring (T-04) 3.5.1-23 A Program Structures lll.A5-9 Monitoring 3.5.1-23 A Program (T-04) Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90)

SBK-L-17155 I Enclosure 2/ Page 154 U.S. Nuclear Regulatory Commission .Intended Component Type h function . :1:1 :* PST -Reinforced Concrete -FSB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural FSB-Exposed to Air Indoor Support Uncontrolled Material I,' Concrete Concrete Concrete 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: ,11 {'-gir:i,9 Environment 11* 1'::1 " Manageinen't" '!;, 1"*11 I ' Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) 111 Ag'ing1 , . i]li.,. * :111 *** I I 'I: I ilil 11f N:u 1 I !I !f:;, I' Management{I' ,: . 'Vc'I' 211tehl 1" : '1* :,.!, ,I, I l,j1j::: :** ii! J.il:, .i:I',,' :l\J'.:11' 1111111!11: I: **1 1: l r . : , . . i Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A5-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Proqram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A5-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A5-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 155 U.S. Nuclear Regulatory Commission Component Type PST -Reinforced Concrete -FSB-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Outdoor PST -Reinforced Concrete -FSB-Exposed to Air Outdoor Intended Function Fire Barrier Shielding Structural Support Missile Barrier Shelter, Protection Material Concrete Concrete Concrete Concrete Concrete PST -Reinforced Concrete -FSB-Exposed to Air Outdoor Missile Barrier I Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) I . Aging Effect Requiring Management Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) Expansion and Cracking I *Aging ' Management Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Buildinq **I I I NUREG 1801 Vol. 2 Item lll.A5-10 (T-06) lll.A5-10 (T-06) lll.A5-10 (T-06) lll.A5-9 (T-04) lll.A5-9 (T-04) lll.A5-2 (T-03) Table 3.X.1 Item 3.5.1-24 3.5.1-24 3.5.1-24 3.5.1-23 3.5.1-23 3.5.1-27 Note A A A A A A, E, 517, 519 SBK-L-17155 I Enclosure 2/ Page 156 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Shelter, FSB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier FSB-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, FSB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier FSB-Exposed to Air Outdoor Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1, Environment Aging Effect Requiring Man'agement Air Outdoor (External) Expansion and Cracking Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) Aging l'I ,11 " :1:1', /', ' Table Management 11 NUREG'1801 " 3.X.1 ;, ,, Vol. 2 Item Note Program Item Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A5-2 Monitoring 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Proaram Structures lll.A5-10 Monitoring 3.5.1-24 (T-06) A Program Structures lll.A5-10 Monitoring 3.5.1-24 A Program (T-06) Structures lll.A5-6 Monitoring 3.5.1-26 A Program (T-01)

SBK-L-17155 I Enclosure 2/ Page 157 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Shelter, FSB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Structural FSB-Exposed to Raw Water Support PST -Reinforced Concrete -Structural FSB-Exposed to Raw Water Support PST -Reinforced Concrete -Flood Barrier PAB-Below Grade PST -Reinforced Concrete -Structural PAB-Below Grade Support 1:1 *1:' ii' .J Material 111 ,,: I Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging .Effect Requiring *11 Environment Management I!! :, ', ::11:, :j11 .I* Air Outdoor Loss of Material, Cracking (External) Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water (External) Expansion and Cracking Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Aging Table I *l*I NUREG 1801 .i:I: Management Vol. 2 Item 3.X.1 Note I Program Item Structures lll.A5-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A5-4 Monitoring 3.5.1-31 A, 512 Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A5-2 A, 512, Monitoring (T-03) 3.5.1-27 E, 517, Program 519 Building Deformation Monitoring Proaram Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05)

SBK-L-17155 I Enclosure 2/ Page 158 U.S. Nuclear Regulatory Commission I Intended Com.ponent Type Function PST -Reinforced Concrete -Flood Barrier PAB-Below Grade PST -Reinforced Concrete -Structural PAB-Below Grade Support PST -Reinforced Concrete -Flood Barrier PAB-Below Grade PST -Reinforced Concrete -Structural PAB-Below Grade Support :I :* , I Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation I ' I lili Aging Effect Requiring :ii 11 '" Management 11i11 i.1 Iii' rilil 11: ,;;;: :11 Ground Water/Soil Expansion and Cracking (External) Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Aging Table ni1 NUREG 1801 Management 3.X.1 Note Vol. 2 Item :item Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proqram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures 111.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program SBK-L-17155 I Enclosure 2/ Page 159 U.S. Nuclear Regulatory Commission I 1:,*, Intended 'I Component Type Function PST -Reinforced Concrete -Structural PAB-Below Grade Support PST -Reinforced Concrete -Structural PAS-Below Grade Support PST -Reinforced Concrete -PAB-Below Grade Flood Barrier PST -Reinforced Concrete -Structural PAS-Below Grade Support PST -Reinforced Concrete -PAS-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PAS-Exposed to Air Indoor Support Uncontrolled ,, Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' I ':i!!:'f I '!:::': I: 1 I :IJtFil" :1;, I 'I' ,11 , Aging .E:ttei;t Requiring ,:, Environment I, 1::1 * '11*i1[,:lil .. ,1:1f I Ii 11 11 , , ,, : , "1'h Hi!: '.11:i,I. 1'1 H1i:1 i'I::'"' !ll:i11il l'i:l*Jili iJ

Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) ,,,. Aging , , NUREG 1B01iil: lt'"'Mahage'ment ' 't + Note i'I' 'V i '21,{1' ,i,'iji I', o,. em: 11'*,1tem'1:, ' I R ' ' ' 11' lfl ,1111*1il111l1;1ilil1,1111l*,:1:1111111i:ll111 di* ,:i"'ii . iH : :1:, , 1:l.1:1JI "I ,,, ,,,**h:1., Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A SBK-L-17155 I Enclosure 2/ Page 160 U.S. Nuclear Regulatory Commission 1: Intended Component Type Function PST -Reinforced Concrete -PAB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PAS-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -PAS-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PAS-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -PAS-Exposed to Air Indoor Fire Barrier Uncontrolled I Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation I Aging Effect Requiring Environment Management Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Uncontrolled Expansion and Cracking (External) Aging Table 1, 1;1:1:1,:1: NUREG 1801 Management Vol. 21tem 3.X.1 Note Program Item Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 161 U.S. Nuclear Regulatory Commission " Intended Component Type Funetion I :I: PST -Reinforced Concrete -Structural PAB-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -PAS-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PAB-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Missile Barrier PAB-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, PAB-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation I ,J, '\" *1 , 1:1 !i1,,:f ;I ilA 11ii11'* 1:111111:1ili1:1: , ';Ir'. '1, 1Jjj ,;li'1:1 Environment , {'-gang Effect Requmr;ig 'I' 11: , Management

11. '1' k Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) 'I' . . 'A . ' ,,,,. 1::* ;J:i ili1ili! 1::' 'f ,111::J'i 1'1,.;gmg :ii1*1,( l:JI 1 'Ii NUREG.i1801':jil '1'1 j:i. I' Note : 111111v<:m 2. 1t0r.T{' . * *, .. 3,.X.1 iJi1. I* 'j:' '1'*:1 .:;11,ti:, :1 *I' 'Item. *Ii\ ** I ';I Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures 111.A3-9 Monitoring 3.5.1-23 A Program (T-04)

SBK-L-17155 I Enclosure 2/ Page 162 U.S. Nuclear Regulatory Commission Component Type Intended Function PST -Reinforced Concrete -Missile Barrier PAB-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, PAB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier PAB-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, PAB-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Management I*' **: Air Outdoor (External) Expansion and Cracking Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 Monitoring 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Proqram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 Monitoring 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Proaram Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-10 Monitoring 3.5.1-24 A Program (T-06)

SBK-L-17155 I Enclosure 2/ Page 163 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -PAB-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, PAB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -PCEW-Below Grade Flood Barrier PST -Reinforced Concrete -Structural PCEW-Below Grade Support PST -Reinforced Concrete -PCEW-Below Grade Flood Barrier Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation II f:J 1:1. l:i', ' ,.1 Environment 1.Aging1Effect Requiring Management Air Outdoor (External) Loss of Material, Cracking Air Outdoor (External) Loss of Material, Cracking Ground Cracking, Loss of Bond, Loss Water/Soil of Material (Spalling, Scaling) (External) Ground Cracking, Loss of Bond, Loss Water/Soil of Material (Spalling, Scaling) (External) Ground Water/Soil Expansion and Cracking (External) Aging NUREG 1so11: Table Management 3.X.1 Note Progra.m Vol. 2 Item Item Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures 111.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A Program Structures 111.A3-4 Monitoring (T-05) 3.5.1-31 A Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 164 U.S. Nuclear Regulatory Commission 1: ,, Intended Component Type Function PST -Reinforced Concrete -Structural PCEW-Below Grade Support PST -Reinforced Concrete -Flood Barrier PCEW-Below Grade PST -Reinforced Concrete -Structural PCEW-Below Grade Support PST -Reinforced Concrete -Structural PCEW-Below Grade Support PST -Reinforced Concrete -Structural PCEW-Below Grade Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation , II'::,,,,, 1:1 ,, 'Aging Effect Requiring 111 1 1 .ji11ManagelT)ent ll,,iij' 111 " ,1, 1:1l::,:r*"'l',.'j1'***I*, :l1l *!:1J11l*1, *:* 1,+ Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Table '*11*1* Aging NUREG 1801 Management Vol. 2 ., , 3.X.1 Note J1,1 1:1('1 ' "H 11111',' 1l*i'IFl'I ' Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program ----

SBK-L-17155 I Enclosure 2/ Page 165 U.S. Nuclear Regulatory Commission Component Type Intended Function ,, 1:1' PST -Reinforced Concrete -PCEW-Below Grade Flood Barrier PST -Reinforced Concrete -Structural PCEW-Below Grade Support PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -HELB PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural PCEW-Exposed to Air Indoor Support Uncontrolled Material ::* Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1; I II I T1 ' II' Ill ,, 1' , ,', ,, 1!1:1:1: ,, . ,*ii ' l'l,,,,1'.' ,,, l'I Environment , , :11 1 Management111 :111 ,, ' ' Ii Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) 1'1 I!' 1Aging r:I I*' ji!I {j ; :1:l*l*l'i1*1 1:, ' ' 'I' :Table ;: ,,,, ,1 ,,, " I' ,, NUREG'1:?B0111Fi 111'1'11'3)<!:1,,:, { 111:, Note 1:1 'Management** I' i:i_:r1*I '1 I i'I :*,**r1 :. '.*;I 11 .1,11,.1.:11 .*l:i 1'.11 ,,:'1'1tem1' I: 11111Rrogram111'11:1.1 '1:1'11'1:, '* I ' , ,, r*: 'Ti*l*I ... , .. ,,I"'* .. l.,j . ' Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A SBK-L-17155 I Enclosure 2/ Page 166 U.S. Nuclear Regulatory Commission Intended Cornponent Type Function PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -HELB PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural PCEW-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -HELB PCEW-Exposed to Air Indoor Uncontrolled Shielding l'i Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Material Environment Management Air Indoor Cracking, Loss of Bond, Loss Concrete Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Concrete Uncontrolled of Material (Spalling, Scaling) (External) Air Indoor Cracking, Loss of Bond, Loss Concrete Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Concrete Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Concrete Cracking and Concrete Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Concrete Uncontrolled (External) Spalling Aging i: Table NUREG 1801 Management Vol. 2 Item 3.X.1 Program Item 1:, Structures 111.A3-9 Monitoring 3.5. 1-23 A Program (T-04) Structures lll.A3-9 Monitoring (T-04) 3.5. 1-23 A Program Structures lll.A3-9 Monitoring 3.5. 1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5. 1-23 A Program (T-04) Fire Protection Vll.G-28 3.3. 1-65 A Program (A-90) Fire Protection Vll.G-28 3.3. 1-65 A Program (A-90)

SBK-L-17155/Enclosure2/Page167 U.S. Nuclear Regulatory Commission ,.!: 1:: Component Type PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled Intended Function Shielding Structural Support Fire Barrier HELB Shielding Mate'rial Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) I*!; Aging Effect Requiring Management Concrete Cracking and Spalling Concrete Cracking and Spalling Expansion and Cracking Expansion and Cracking Aging Management Program Fire Protection Program Fire Protection Program Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program 1*11;1 NUREG 1801 Vol. 2 Item Vll.G-28 (A-90) Vll.G-28 (A-90) lll.A3-2 (T-03) lll.A3-2 (T-03) Table 3.X.1 Item 3.3.1-65 3.3.1-65 3.5.1-27 3.5.1-27 ;i:!:11::i:, Note',:,, A A A, E, 517, 519 A, E, 517, 519 SBK-L-17155 I Enclosure 2/ Page 168 U.S. Nuclear Regulatory Commission Component Type PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled Intended Function Shielding Structural Support Fire Barrier HELB Shielding Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) 111' I* I ' ,!; ,I,,' :1 Aging Effect Requiring 111 Management-* '

I Expansion and Cracking Expansion and Cracking Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Aging Management Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program Structures Monitoring Program Structures Monitoring Program NUREG 1801 Vol. 2 Item lll.A3-2 (T-03) lll.A3-2 (T-03) lll.A3-10 (T-06) lll.A3-10 (T-06) 'Table I 3.X.1 Item 3.5.1-27 3.5.1-27 3.5.1-24 3.5.1-24 Note A, E, 517, 519 A, E, 517, 519 A A SBK-L-17155 I Enclosure 21 Page 169 U.S. Nuclear Regulatory Commission *1:* Intended Component Type Function PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural PCEW-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Missile Barrier PCEW-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, PCEW-Exposed to Air Outdoor Protection PST -Reinforced Concrete -PCEW-Exposed to Air Outdoor Missile Barrier Material ' Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment I , :1:1:1.l!f!il; !l'it l![i ****. ' :l!I , *,11 * *1*1 Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking Aging NUREG 1801 Table 1:1 Management 3.X.1 Note " ,Program Vol. 2 Item Item I: I Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 170 U.S. Nuclear Regulatory Commission 'I Component Type Intended Function PST -Reinforced Concrete -Shelter, PCEW-Exposed to Air Outdoor Protection PST -Reinforced Concrete -PCEW-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, PCEW-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier PCEW-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, PCEW-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) Air Outdoor Loss of Material, Cracking (External) Ag'ing NUREG 1801 Table ,, 'Iii Management 3.X.1 , I : , , Program Vol. 2 Item Item Note i: *: ' Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-2( Program (T-03) 517, 519 Building Deformation Monitoring Proqram Structures lll.A3-10 Monitoring 3.5.1-24 (T-06) A Program Structures lll.A3-10 Monitoring 3.5.1-24 A Program (T-06) Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01)

SBK-L-17155 I Enclosure 2/ Page 171 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural PCEW-Exposed to Raw Water Support PST -Reinforced Concrete -Structural PCEW-Exposed to Raw Water Support PST -Reinforced Concrete -Flood Barrier PHA-Below Grade PST -Reinforced Concrete -Structural PHA-Below Grade Support PST -Reinforced Concrete -Flood Barrier PHA-Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,,,,,, 111,::111, Aging Req'uiring ,:,. Environment I!:* 11 , ,11 '!:1 Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water Expansion and Cracking (External) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) 'Aging Table NUREG 1801 Management Vol. 2 lfom J;X.1 Note Pr9g,ram, 1,'"*: " , ".:!': l:!*l'i]JI 1;:11:11.,!tem.,, Structures lll.A3-4 Monitoring 3.5.1-31 A, 512 Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) A, 512, Monitoring 111.A3-2 3.5.1-27 E, 517, Program (T-03) 519 Building Deformation Monitoring Program Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program lll.A3-2 3.5.1-27 A, E, Alkali-Silica (T-03) 517, 519 Reaction (ASR) Monitoring ProQram SBK-L-17155 I Enclosure 2/ Page 172 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural PHA-Below Grade Support PST -Reinforced Concrete -Flood Barrier PHA-Below Grade PST -Reinforced Concrete -Structural PHA-Below Grade Support PST -Reinforced Concrete -Structural PHA-Below Grade Support Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment. Aging Effect Requiring Management Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength i' Aging NUREG 1801 Table :r Management Vol. 2 Item 3.X.1 Note Program Item. Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures 111.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 173 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural PHA-Below Grade Support PST -Reinforced Concrete -PHA-Below Grade Flood Barrier PST -Reinforced Concrete -Structural PHA-Below Grade Support PST -Reinforced Concrete -PHA-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PHA-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -PHA-Exposed to Air Indoor Fire Barrier Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' ' I : ' 1i:1:1111N!l ' 11:1,11 : I I:' 1:1:1'11:1' Aging Effect Requiring Environment Management Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) I, !11;1,1:!Aging . 1,:11,,, ,1; I Table NUREG.'1801 Management Vol. 2 Item 3.X.1 Note Program Item Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01). 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04)

SBK-L-17155 I Enclosure 2/ Page 174 U.S. Nuclear Regulatory Commission Intended Comphnent Type Function PST -Reinforced Concrete -Structural PHA-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -PHA-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PHA-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -PHA-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PHA-Exposed to Air Indoor Uncontrolled Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation I I iF *I* ' Effect Requiring, . J M *Aging t 1 Environmenrl 11 Ii! : 'l!F .1i:q. ! Mdnagement 1 1il'111 . . anagemen 1 * '.i 'I' .,1,11 *1111 IJ l1',uf!f!l:l'l11:i:'l't:1111 1,1:1:W':1:,,-, .,. , '!f!:l.1 I ,!I :1!!:*1 I* Air Indoor Cracking, Loss of Bond, Loss Structures Uncontrolled Monitoring (External) of Material (Spalling, Scaling) Program Air Indoor Concrete Cracking and Fire Protection Uncontrolled (External) Spalling Program Air Indoor Concrete Cracking and Fire Protection Uncontrolled (External) Spalling Program Structures Monitoring Program Alkali-Silica Air Indoor Reaction (ASR) Uncontrolled Expansion and Cracking Monitoring (External) Program Building Deformation Monitoring Proqram Structures Monitoring Program Air Indoor Uncontrolled Expansion and Cracking Alkali-Silica (External) Reaction (ASR) Monitoring Program NUREG 1801 Table I 'I Vol. 2 Item 1, , 3.X.1. Note ,,,1, 1'1:i:* :1: :l:1!l*i: ,,,1,,!: ' .. 111.A3-9 3.5. 1-23 A (T-04) Vll.G-28 3.3. 1-65 A (A-90) Vll.G-28 3.3. 1-65 A (A-90) lll.A3-2 A, E, 3.5. 1-27 (T-03) 517, 519 lll.A3-2 A, E, 3.5. 1-27 (T-03) 517, 519 SBK-L-17155 I Enclosure 2/ Page 175 U.S. Nuclear Regulatory Commission Component Type PST -Reinforced Concrete -PHA-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PHA-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PHA-Exposed to Air Outdoor PST -Reinforced Concrete -PHA-Exposed to Air Outdoor Intended Function Fire Barrier Structural Support Shelter, Protection Shelter, Protection Material Concrete Concrete I Concrete I Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1:1:' :111 ',1111 .,11: Environment1 ** :i!li 1A. g .* g. f:iHect Requiring, I .I 'I' 'l'l'il: ,: Management. ., :::1*:: II :l:H:l1 <j11I: : *l:'":i: ' 'I Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor I Expansion and Cracking (External) Aging , Management 11 Program Building Deformation Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program NUREG 1801 I Table Vol. 2 Item 3.X.1 *i :i, 'I* , ,,,:1111j.ltem Note lll.A3-10 (T-06) I 3.5.1-24 IA I lll.A3-10 (T-06) I 3.5.1-24 IA 111.A3-9 I 3.5.1-23 IA (T-04) 111.A3-2 I 3.5.1-27 A, E, (T-03) 517, 519 SBK-L-17155 I Enclosure 2/ Page 176 U.S. Nuclear Regulatory Commission Intended ' Component Type Function PST -Reinforced Concrete -Shelter. PHA-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Shelter, PHA-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Flood Barrier TFA-Below Grade PST -Reinforced Concrete -Structural TFA-Below Grade Support PST -Reinforced Concrete -Flood Barrier TFA-Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,1, l:' 'l:'I" ' i' ,,, ' 1:. , Aging' Effect Requiri'ng 1 Environment Management ! ' I ' ' Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) Table ,,1 Aging NUREG 1801 ,Management Vol. 2 Item 3.X.1 Note' Program Item Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 177 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural TFA-Below Grade Support PST -Reinforced Concrete -Flood Barrier TFA-Below Grade PST -Reinforced Concrete -Structural TFA-Below Grade Support PST -Reinforced Concrete -Structural TFA-Below Grade Support PST -Reinforced Concrete -Structural TFA-Below Grade Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ;1: 'I Aging Effect Requiring Environment Management Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Aging Table NUREG 1801 Management Vol. 2 Item 3.X.1 Note Program Item Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 178 U.S. Nuclear Regulatory Commission Intended Component Type '" , 1,111 Function . " 1, PST -Reinforced Concrete -TFA-Below Grade Flood Barrier PST -Reinforced Concrete -Structural TFA-Below Grade Support PST -Reinforced Concrete -TFA-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -TFA-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural TFA-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -TFA-Exposed to Air Indoor Fire Barrier Uncontrolled :r* Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation t t 111 11[:'.1 Material Environment ' Management 1:11.1:'11 11 :1111 I ' * ,,, .,, ;i'l;,1 JI Ground Concrete Water/Soil Loss of Material, Cracking (External) Ground Concrete Water/Soil Loss of Material, Cracking (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Loss Concrete Uncontrolled (External) of Material (Spalling, Scaling) + ,,* I t!l:1: Aging i; :1, 1'1i11[ :1: I 1:, 1:1,Manager:nrnt,1,1, NUREG 180,11'n ;111 11.1, ... :111 ,1.,1 Program* t11 'llllJ1'1:1!1l111111 *'*l:i!ll11f:I::,,, '.: :; :\Item 'l1,1 lij: 11*1 .' ' * ,I.' I :: *I; Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3. 1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04)

SBK-L-171 SS I Enclosure 2/ Page 179 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -TFA-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural TFA-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -TFA-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -TFA-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural TFA-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -TFA-Exposed to Air Indoor Fire Barrier Uncontrolled I I Material ' Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 'I i+i ' ' Effect ,*11 Environment 1 l'l:!Jli; 111 '1 I, I I :I: * :':1:j:1 *l111:l:,:i:p11fDitl ,11 *1111: ':11 'I' , , Air Indoor Cracking, Loss of Bond, Loss Uncontrolled of Material (Spalling, Scaling) (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled of Material (Spalling, Scaling) (External) Air Indoor Concrete Cracking and Uncontrolled Spa I ling (External) Air Indoor Concrete Cracking and Uncontrolled Spa I ling (External) Air Indoor Concrete Cracking and Uncontrolled Spalling (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging Table 1lil,j1:jll*.::1:1; NUREG 1801 Management 3.X.1 Vol. 2 Item Program Item ' Structures lll.A3-9 Monitoring 3.5.1-23 A (T-04) Program Structures lll.A3-9 Monitoring 3.5.1-23 A (T-04) Program Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 A 3.3.1-65 Program (A-90) Structures Monitoring Program Alkali-Silica lll.A3-2 A, E, Reaction (ASR) (T-03) 3.5.1-27 517, 519 Monitoring Program Building SBK-L-17155 I Enclosure 2/ Page 180 U.S. Nuclear Regulatory Commission Component Type Intended Function PST -Reinforced Concrete -TFA-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural TFA-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -TFA-Exposed to Air Indoor Fire Barrier Uncontrolled Material Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation !.t I H ,,, Environment Aging Effect,Requiripg Management Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Aging Management NUREG 1801 3.X.1 Note Vol. 2 Item Program ,,, Item Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proqram Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 181 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -TFA-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural TFA-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Missile Barrier TFA-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, TFA-Exposed to Air Outdoor Protection PST -Reinforced Concrete -TFA-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, TFA-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' II 1:! Aging Effect Requiring Environment Management Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking Air Outdoor Expansion and Cracking (External) ,,, Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note Program Item Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) . Structures lll.A3-2 Monitoring (T-03) 3.5.1-27 A Program Structures Monitoring Program Alkali-Silica lll.A3-2 3.5.1-27 A, E, Reaction (ASR) (T-03) 517, 519 Monitoring Program Building SBK-L-17155 I Enclosure 2/ Page 182 U.S. Nuclear Regulatory Commission Component Type Intended Function PST -Reinforced Concrete -Missile Barrier TFA-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, TFA-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier TFA-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, TFA-Exposed to Air Outdoor Protection PST -Reinforced Concrete -WPB-Below Grade Flood Barrier Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation II ' I*; 1::1:.i:* "' :[:i: IJ'* Aging Effect Requiring 111 Environment Management Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) Air Outdoor Loss of Material, Cracking (External) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) n1 1*,,111:11 , , 1:1, ' ' II' 11! rl I ll *

I !"'* 1 >r" l'I '

11] *:,f ,. :: 'l' 111'r Table 1:k Managementi*ll , , NUREC?;,1,so11, ' 3.X.1

Note Program 111Nol. 2' Item Item Deformation Monitoring Program Structures lll.A3-10 Monitoring 3.5.1-24 A Program (T-06) Structures lll.A3-10 Monitoring 3.5.1-24 A Program (T-06) Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01) Structures Monitoring lll.A3-4 3.5.1-31 (T-05) A Program SBK-L-17155 I Enclosure 2/Page 183 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural WPB-Below Grade Support PST -Reinforced Concrete -WPB-Below Grade Flood Barrier PST -Reinforced Concrete -Structural WPB-Below Grade Support PST -Reinforced Concrete -WPB-Below Grade Flood Barrier Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation :1: T *I Aging Effect Requiring Environment Management Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note Program Item Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proa ram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program SBK-L-17155 I Enclosure 2/ Page 184 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural WPS-Below Grade Support PST -Reinforced Concrete -Structural WPS-Below Grade Support PST -Reinforced Concrete -Structural WPB-Below Grade Support PST -Reinforced Concrete -Flood Barrier WPS-Below Grade PST -Reinforced Concrete -Structural WPS-Below Grade Support PST -Reinforced Concrete -WPS-Exposed to Air Indoor Fire Barrier Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,,,, , 'l 'I'll:( i' ::1 Environment Aging Effect Requiring 11' ,,, ' llMana,gemen.t 1:1 ,,,, Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Agir;ig ,,, ::IJ, fr,j:I ,,,,, ITable, Management *NU REG 1,801 ix.1 Note Program Vol. 2 Item , Item '1;:;, Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures 111.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 3.3.1-67 A Program (A-91)

SBK-L-17155 I Enclosure 2/ Page 185 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -WPB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural WPB-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -WPB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -WPB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural WPB-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -WPB-Exposed to Air Indoor Fire Barrier Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' ' ' Aging Effect Requiring Environment 1: 1* Management Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Aging NUREG 1801 Table Management 1 Note Program Vol. 2 Item 11tem Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90)

SBK-L-17155 I Enclosure 2/ Page 186 U.S. Nuclear Regulatory Commission Component Type * ' ' Intended Function'!' PST -Reinforced Concrete -WPS-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural WPS-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -WPS-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -WPS-Exposed to Air Indoor Shielding Uncontrolled "Material " :1: Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 11111:,,111 qi, ,1111 it.l,.11'111111111 Environment Agmg Effect , 1 Management Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) 1il1 i1'!11i*1 111111-lillllillllll"llllli llr 11*11lirab11e/1 1[:1i

Management I '13 x I" .*, 1. Note 1yo1.l 21tem t * *111111 111,1_ !], .. 'I' . ' Program Item' Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 187 U.S. Nuclear Regulatory Commission Component Type PST -Reinforced Concrete -WPS-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -WPS-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -WPS-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -WPS-Exposed to Air Indoor Uncontrolled Intended Function 1::. Structural Support Fire Barrier Shielding Structural Support Material Concrete Concrete Concrete Concrete PST -Reinforced Concrete -I Missile Barrier I Concrete WPS-Exposed to Air Outdoor Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation I'. + . :1: 1: .I I j' ,I" I I ' ' ' : I ! Environment ,., .. " .. '.I ,,. ,1'1!1;:11 {Ir Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) I Air Outdoor (External) Expansion and Cracking Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) I Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) Aging . NURE. G '1801-,' : '131x 11'.i' : . Note ')' . I ... ' *. '1:1'1 'I'll * ' *; *: r: I ,, ln1:1Table l'l*I*.* M .. a. nager:nent1ll'i, Item *I.Ii lte' m :1*111i:"*\ 1*l!l1i:.1. , ::.1 I '.,,, I '"1:1**1:: 'I' *1*1*1* :1 I. . '::. "," ' ::* *'1.:.'Program 1" 111 i 11* '-!-,,,,,,11111 "' I* , .1 ... I*):'.**} ,1 I ., !,,* Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program lll.A3-2 (T-03) lll.A3-10 (T-06) lll.A3-10 (T-06) lll.A3-10 (T-06) lll.A3-9 (T-04) 3.5.1-27 3.5.1-24 3.5.1-24 3.5. 1-24 3.5.1-23 A, E, 517, 519 A A A A SBK-L-17155 I Enclosure 2/ Page 188 U.S. Nuclear Regulatory Commission ;*I Component Typ,e Intended Function PST -Reinforced Concrete -Shelter, WPS-Exposed to Air Outdoor Protection PST -Reinforced Concrete -WPS-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, WPS-Exposed to Air Outdoor Protection PST -Reinforced Concrete -WPS-Exposed to Air Outdoor Missile Barrier ,;1 Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation IH' :;* Environment Aging Effect Requiring ' Management \l l'i' 111 Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) '1*'Aging 'l ;1: 'y, i'I, li' . ' ' Table *, *!::t1!1: Management NUREG 1801 3.X.1 Note.i11:il:f'! Vol. 2 Item ' :II Program Item '

1:1:1 Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program Alkali-Silica Reaction (ASR) 111.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 189 U.S. Nuclear Regulatory Commission ,. *intended Component Type Function 1:1 PST -Reinforced Concrete -Shelter, WPB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -WPB-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, WPB-Exposed to Air Outdoor Protection PST -Stainless Steel -COG-Structural Exposed to Air Indoor Support Uncontrolled PST -Stainless Steel -COG-Shelter, Exposed to Raw Water Protection PST -Stainless Steel -CEHMS-Structural Exposed to Air Outdoor Support Material ,, Concrete Concrete Concrete Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation : Aging Effect Requiring Environment Management .* :. Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Air Outdoor Loss of Material, Cracking (External) Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Raw Water Loss of Material (External) Air Outdoor (External) Loss of Material II '1:1,l:J:,. '. 111:1 l'I *. *l.1 *:* NUREG11ao1 * .** Tabre. Management Vol. 2 Item 3.X.1 Note I( Program Item 1" I Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01) Nooe Building 111.82-8 Deformation (TP-5) 3.5.1-59 C, E, 520 Monitoring Program Structures Vll.H2-18 Monitoring 3.3.1-80 E, 512 Program (Ap-55) Structures 111.82-7 Monitoring (TP-6) 3.5.1-50 c Program SBK-L-17155 I Enclosure 2/ Page 190 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Stainless Steel -FSB-Structural Exposed to Air Indoor Support Uncontrolled PST -Stainless Steel -FSB-Shelter, Exposed to Raw Water Protection PST -Stainless Steel -FSB-Shelter, Exposed to Treated Borated Water Protection PST -Stainless Steel -FSB-Shelter, Exposed to Treated Borated Water Protection PST -Stainless Steel -FSB-Structural Fuel Transfer Tube in Air with Support Borated Water Leakage PST -Stainless Steel -FSB-Structural Fuel Transfer Tube in Air Indoor Support Uncontrolled Material Stainless Steel Stainless Steel Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,; ::':1!.j !*1:1 'l:I Environment Aging Effect Requiring Management' Air Indoor Nooe Uncontrolled Deformation/reduction in (External} structural capacity Raw Water (External) Loss of Material Treated Borated Cracking Water (External) Treated Borated Loss of Material Water (External) Air w/Borated Nooe Water Leakage Deformation/reduction in (External) structural capacity Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity h Aging 'i::' 1.l,:1*1 :1:1 I' ,, NUREG 1801 Table , Managemept 111 Vol. 21tem 3.X.1 Note Program lt!'!m Nooe Building lll.B2-8 Deformation (TP-5) 3.5.1-59 C, E, 520 Monitoring Program Structures Vll.H2-18 Monitoring (Ap-55) 3.3.1-80 E, 512 Program Water Chemistry lll.A5-13 A, 3.5.1-46 Program (T-14) 507,518 Water Chemistry 111.A5-13 3.5.1-46 A,518 Program (T-14) Nooe Building lll.B2-9 Deformation (TP-5) 3.5.1-59 A, E, 520 Monitoring Program Nooe Building lll.B2-8 Deformation (TP-5) 3.5.1-59 C, E, 520 Monitoring Program SBK-L-17155 /Enclosure2/Page 191 U.S. Nuclear Regulatory Commission Intended Component Type l'I ,., ,Function,, 'I I 1:1 ' 1:. PST -Stainless Steel -FSB-in Structural Air with Borated Water Leakage Support PST -Stainless Steel -PAB-Structural Exposed to Air Indoor Support Uncontrolled PST -Stainless Steel -PAB-Shelter, Exposed to Raw Water Protection PST -Stainless Steel -PAB-in Structural Air with Borated Water Leakage Support PST -Stainless Steel -WPB-Structural Exposed to Air Indoor Support Uncontrolled PST -Stainless Steel -WPB-Shelter, Exposed to Raw Water Protection Material Stainless Steel Stainless Steel Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1, 11 1Jff 1'1' 'l'i '1'1 , 1" ' 11". , "' , Aging Effect It Environment

Management: 1.,li *1 , Air w/Borated Nooe Water Leakage Deformation/reduction in (External) structural capacity Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Raw Water (External) Loss of Material Air w/Borated Nooe Water Leakage Deformation/reduction in (External) structural capacity Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Raw Water (External) Loss of Material '\ 11:1 nr' , ,1'j:'W':1:111'i'k ; 11:1 NUREG:,1so11:i:I 111 , VoJ.',2 1tMm1'" :( 1,1111 :1: Note item 11i' V ,.,,1,, ,,,, , Program IJ11111 '1111:! ' ,,, "'1 ' Hii: Nooe Building lll.B2-9 Deformation (TP-5) 3.5.1-59 A, E, 520 Monitoring Program Nooe Building lll.B2-8 Deformation (TP-5) 3.5.1-59 C, E, 520 Monitoring Program Structures Vll.H2-18 Monitoring (Ap-55) 3.3.1-80 E, 512 Program Nooe Building lll.B2-9 Deformation (TP-5) 3.5.1-59 A, E, 520 Monitoring Program Nooe Building lll.B2-8 Deformation (TP-5) 3.5.1-59 C, E, 520 Monitoring Program Structures Vll.H2-18 Monitoring (Ap-55) 3.3.1-80 E, 512 Program SBK-L-17155 I Enclosure 2/ Page 192 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Stainless Steel -WPB-in Structural Air with Borated Water Leakage Support PST -Tech Spec CEVA Seal -Structural EFP-Exposed to Air Indoor Pressure Uncontrolled Barrier PST -Tech Spec CEVA Seal -Structural EFP-Exposed to Air Outdoor Pressure Barrier PST -Tech Spec CEVA Seal -Structural FSB-Exposed to Air Indoor Pressure Uncontrolled Barrier PST -Tech Spec CEVA Seal -Structural PAB-Exposed to Air Indoor Pressure Uncontrolled Barrier PST -Tech Spec CEVA Seal -Structural PAB-Exposed to Air Outdoor Pressure Barrier Material Stainless Steel Elastomer Elastomer Elastomer Elastomer Elastomer Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 'I: Aging Effect Requidng Environment Management Air w/Borated NeRe Water Leakage Deformation/reduction in (External) structural capacity Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, (External) Shrinkage and Loss of Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, (External) Shrinkage and Loss of Strength *1 *' ' Aging NUREG 1801 Table Management 3.X.1 Note Program Vol. 2 Item Item NeRe Building lll.B2-9 Deformation (TP-5) 3.5.1-59 A, E, 520 Monitoring Program Structures Vll.G-1 Monitoring (A-19) 3.3.1-61 E, 515 Program Structures Vll.G-2 Monitoring (A-20) 3.3.1-61 E, 515 Program Structures Vll.G-1 Monitoring (A-19) 3.3.1-61 E, 515 Program Structures Vll.G-1 Monitoring (A-19) 3.3.1-61 E, 515 Program Structures Vll.G-2 Monitoring (A-20) 3.3.1-61 E, 515 Program SBK-L-17155 I Enclosure 2/ Page 193 U.S. Nuclear Regulatory Commission Intended* Component Type Function PST -Tech Spec CEVA Seal -Structural PCEW-Exposed to Air Indoor Pressure Uncontrolled Barrier PST -Tech Spec CEVA Seal -Structural Pressure PCEW-Exposed to Air Outdoor Barrier PST -Tech Spec Control Room Control Bldg Seal -CDG-Exposed to Air Habitability Indoor Uncontrolled PST -Tech Spec Fuel Storage Structural Building Seal -FSB-Exposed to Pressure Air Indoor Uncontrolled Barrier PST -Thermal Insulation Structural Aluminum Jacketing -FSB-in Air Support with Borated Water Leakage PST -Thermal Insulation Structural Aluminum Jacketing -PAB-in Support Air with Borated Water Leakage ' Material Elastomer Elastomer Elastomer Elastomer Aluminum Aluminum Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring Management Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Aging NUREG 1801 Table Management 3.X.1 Note' Program Vol. 2 Item Item Structures Vll.G-1 Monitoring (A-19) 3.3. 1-61 E, 515 Program Structures Vll.G-2 Monitoring 3.3. 1-61 E, 515 Program (A-20) Structures Vll.G-1 Monitoring (A-19) 3.3. 1-61 E, 515 Program Structures Vll.G-1 Monitoring (A-19) 3.3. 1-61 E, 515 Program Boric Acid lll.B2-6 Program (TP-3) 3.5. 1-55 A Boric Acid lll.B2-6 Program (TP-3) 3.5.1-55 A SBK-L-17155 I Enclosure 2/ Page 194 U.S. Nuclear Regulatory Commission *intended* Component Type Function PST -Thermal Insulation Structural Aluminum Jacketing -TFA-in Air Support with Borated Water Leakage PST -Thermal Insulation Structural Aluminum Jacketing -WPB-in Support Air with Borated Water Leakage Material Aluminum Aluminum Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) *I* ,1,,1, ,1 Aging

NUREG 1801 Table. Management 3.X.1 Note Program Vol. 2 Item . Item Boric Acid lll.B2-6 Program (TP-3) 3.5.1-55 A Boric Acid lll.B2-6 Program (TP-3) 3.5.1-55 A 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 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. 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 "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.

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 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. 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 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 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 197 U.S. Nuclear Regulatory Commission Intended Component Type Function ASME Class 1 -Constant & Variable Load Spring Hangers -Structural Exposed to Air Indoor Support Uncontrolled ASME Class 1 -Constant & Variable Load Spring Hangers -Structural in Air with Borated Water Support Leakage ASME Class 1 -Lubrite -Structural Exposed to Air Indoor Uncontrolled Support ASME Class 1 -Pipe Supports -Structural Concrete -Exposed to Air Indoor Support Uncontrolled ASME Class 1 -Stainless Steel -Exposed to Air Indoor Structural Uncontrolled Support Material Steel Steel Lubrite Concrete Stainless Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation Aging 'Effect Requiring Environment Management Air Indoor Uncontrolled Loss of Mechanical Function (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Mechanical Function (External) Air Indoor Reduction in Concrete Anchor Uncontrolled Capacity (External) Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Aging .. NUREG I Table Management, 1801 2

3.X.1 Note Program Item Item ASME Section XI, Subsection 111.81 .1-2 3.5.1-54 A IWF Program (T-28) Boric Acid Corrosion 111.81 .1-14 3.5.1-55 A Program (T-25) ASME Section 111.81 .1-5 XI,, Subsection 3.5.1-56 A IWF Program (T-32) Structures Monitoring Program, Alkali-111.81 .1-1 Silica Reaction (T-29) 3.5.1-40 A, E, 517 (ASR) Monitoring Program Nooe Structures Monitoring Program, 111.81 .1-9 3.5.1-59 A, E, 520 Building (TP-5) 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 Evaluation 1 1 t d d 1: . f:I 1 / 1 . A . . Eff t R . . Aging

NUREG Table Component Type Fn ent.e Material 1Environ1ment:!11il 11,il' gingM. ec equtmng Management 1801 Vol. *2 .3.X.1 Note unc ion 1 :i , .. iJil!, anagemen ,, . , p ,*1t . i* <<"'It 'I' . I' ,.. ,., .... ', :1:.1,1.1, * .i 1.,

T * .rogram 111. . .e(Tl ,1,1:: 1::1: .. , em * :1:11* I iii *1* ,,l,1 I . ,, ,!.;, .I. ,, I * ,I, Id Nooe Structures . . Monitoring ASME Class 1 -Stam less Steel St t 1 St . 1 Air w/Borated Nooe p 111 B1 1 10 -in Air with Borated Water ess Water Leakage Deformation! in (T.P-4) -3.5. 1-59 A, E, 520 Leakage PP (External) structural capacity 0 & gt* e1orma ion Monitoring Program ASME Class 1 Support -Carbon St t 1 Air Indoor ASME Section 111 B1 1 _13 Steel -Exposed to Air Indoor Steel Uncontrolled Loss of Material XI, Subsection 3.5.1-53 A Uncontrolled PP (External) IWF Program ASME Class 1 Support -Carbon St t 1 Air w/Borated Boric Acid 111 B1 1_14 Steel -in Air with Borated Steel Water Leakage Loss of Material Corrosion 3.5. 1-55 A Water Leakage PP (External) Program ASME Class 2/3 -.constant and Air Indoor ASME Section Variable Load Spring Hangers -Structural . . . lll.B1 .2-2 E d t A 1 d S rt Steel Uncontrolled Loss of Mechanical Function XI, Subsection (T 28) 3.5. 1-54 A xpose o 1r n oar uppo (External) IWF Program -Uncontrolled ASME Class 2/3 -.constant & Air w/Borated Boric Acid Variable Load Spring Hangers -Structural St 1 W t L k L f M t . 1 C . 111.B1 .2-11 3 5 1 55 A . A' 'th B t d W t S rt ee a er ea age ass o a eria orros1on (T 25) . . -Lin ktr wt ora e a er uppo (External) Program -ea age ASME Class 2/3 -Lubrite -St t I Air Indoor ASME Section Ill B1 2_3 Exposed to Air Indoor Lubrite Uncontrolled Loss of Mechanical Function XI, Subsection 3.5.1-56 A Uncontrolled PP (External) IWF Program SBK-L-17155 I Enclosure 2/ Page 199 U.S. Nuclear Regulatory Commission Component Type Intended Function ASME Class 2/3 Pipe Supports Structural -Concrete -Exposed to Air Support Indoor Uncontrolled ASME Class 2/3 -Stainless Steel -Exposed to Air Indoor Structural Uncontrolled Support ASME Class 2/3 -Stainless Structural Steel -in Air with Borated Support Water Leakage ASME Class 2/3 -Stainless Structural Steel -in Raw Water Support ASME Class 2/3 -Stainless Structural Steel -in Raw Water Support Material Concrete Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation 'i'i Environment . Aging 'Effe.c:t Management Air Indoor Reduction in Concrete Anchor Uncontrolled Capacity (External) Air Indoor Nooe Uncontrolled Deformation/ reduction in (External) structural capacity Air w/Borated Water Leakage None (External) Raw Water Loss of Material (External) Raw Water (External) Loss of Material Aging NU REG Table Management 1801*Vol.2 1:13.X.1 '"1: Note Program Item Item Structures Monitoring Program, Alkali-111.81 .2-1 Silica Reaction (T-29) 3.5.1-40 A, E, 517 (ASR) Monitoring Program Nooe Structures Monitoring Program, 111.81 .2-7 3.5.1-59 A, E, 520 Building (TP-5) Deformation Monitoring Program Boric Acid 111.81 .2-11 Corrosion (TP-25) 3.5.1-55 A Program ASME Section 111.81.1-11 H, 509, XI, Subsection 3.5.1-49 IWF Program (TP-10) 514 ASME Section 111.81 .1-11 XI, Subsection (TP-10) 3.5.1-49 A, 509 IWF Program SBK-L-17155 I Enclosure 2/ Page 200 U.S. Nuclear Regulatory Commission Intended Component Type Function l*j .:1: ASME Class 2/3 -Stainless Structural Steel -in Treated Water Support ASME Class 2/3 Support -Structural Carbon Steel -Exposed to Air Support Indoor Uncontrolled ASME Class 2/3 Support Structural Carbon Steel -in Air with Support Borated Water Leakage Baral Poison Sheet in Spent Absorb Fuel Racks -in Treated Water Neutrons Emergency Diesel Generator Structural (EOG) -Concrete -Exposed to Support Air Indoor Uncontrolled Emergency Diesel Generator Structural (EOG) -Lubrite -Exposed to Support Air Indoor Uncontrolled Material Ii Stainless Steel Steel Steel Bora I Concrete Lubrite Table 3.5.2-6 Supports Summary of Aging Management Evaluation :I; ;1:1:!i 11 Environment ' 1 Management .,. 1 .1: .i: . , I . . " ::: Treated Borated Loss of Material Water (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Treated Borated Reduction of Neutron Absorbing Water (External) Capacity and Loss of Material Air Indoor Reduction in Concrete Anchor Uncontrolled Capacity (External) Air Indoor Uncontrolled Loss of Mechanical Function (External) , *f *"' . *11 ., 1111'1INUREG i1: I 1:1* 1:1:1 ijAging '" i .1:j1;1 " I I *.:, 'I ::Note :111, ' ' ':Ii 1 ao1 lv;o1.;.2, . 3.X.1 , .. ,, 'I I 1 Item' ,, *1:.: ' .. 11 ,. I',,. 'Program "'ilil' 11 1111 ltelljl 1.

Water Chemistry lll.A5-13 3.5.1-46 A Program (T-14) ASME Section lll.B1.2-10 XI, Subsection (T-24) 3.5.1-53 A IWF Program Boric Acid lll.B1 .2-11 Corrosion (TP-25) 3.5.1-55 A Program Baral Monitoring Vll.A2-5 3.3.1-13 A Program (A-88) Structures Monitoring Program, Alkali-lll.B4-1 Silica Reaction (T-29) 3.5.1-40 A, E, 517 (ASR) Monitoring Program Structures lll.B4-2 Monitoring (TP-1) 3.5.1-52 A Program SBK-L-17155 I Enclosure 2/ Page 201 U.S. Nuclear Regulatory Commission ., ,: '.I Intended *'component Type Function Emergency Diesel Generator (EOG) Support -Carbon Steel -Structural Exposed to Air Indoor Support Uncontrolled HVAC System Components -Structural Exposed to Air Outdoor Support HVAC System Components -Structural Exposed to Air Outdoor Support HVAC System Components -Structural Exposed to Air Outdoor Support l*I Material Steel Concrete Concrete Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation ' :, ',iJ 1'1 t*' :1:1'! I 1111:11,1 'ij., *

11 :1'111111" :I Management 1:! ,,, . , ' *'j'I ' l::l:l'l:l"i:i:* i'l'!:HJ: 'li1 :1:111: Air Indoor Uncontrolled Loss of Material (External) Air Outdoor Reduction in Concrete Anchor (External) Capacity Air Outdoor Expansion and cracking (External) Air Outdoor Deformation/reduction in (External) structural capacity :1 Aging NU REG Table Management 1801,Vol.2 1*:J.X.1Vci/. 1:1 Note '*** Prog,ram ;;,, 1:. j;1:': I ' ,' : T :.. . ,1 111 : Structures Monitoring 111.84-10 3.5.1-39 A Program (T-30) Structures Monitoring Program, Alkali-111.84-1 Silica Reaction 3.5.1-40 A, E, 517 (ASR) (T-29) Monitoring Program Structures Monitoring Program, Alkali Silica Reaction (ASR) 111.84-1 A,E, Monitoring 3.5.1-27 Program & (T-29) 517, 519 Building Deformation Monitoring Program Building Deformation lll.B4-1 3.5.1-61 A, E, 520 Monitoring (T-29) Program SBK-L-17155 I Enclosure 2/ Page 202 U.S. Nuclear Regulatory Commission 'Intended Component Type Function 1:i HVAC System Components -Structural Exposed to Air Indoor Support New Fuel Storage Racks Support -Carbon Steel -Structural Exposed to Air Indoor Support Uncontrolled New Fuel Storage Racks Structural Support -Carbon Steel -in Air Support with Borated Water Leakage Non-ASME -Constant and Variable Load Spring Hangers -Structural Exposed to Air Indoor Support Uncontrolled Non-ASME -Constant and Variable Load Spring Hangers -Structural in Air with Borated Water Support Leakage . ' Material w1: **. Steel Steel Steel Steel Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation ,'.!.' Aging Effect Requiring " Environment Management Air Indoor Deformation/reduction in (External) structural integrity Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Mechanical Function (External) Air w/Borated Water Leakage Loss of Material (External) ';!Aging 1:1 :1: *1 '1 111 111.1J*1,,:111: Table .:rl:r 1 Management . 1801 Vol. 2 3.X.1 Program Item Item Note, j;i Building Deformation /11.84-1 3.5.1-61 A, E, 519 Monitoring (T-29) Program Structures Monitoring Vll.A1-1 3.3.1-86 A Program (A-94) Boric Acid lll.B5-8 Corrosion (T-25) 3.5.1-55 A Program Structures Monitoring lll.B1.2-2 3.5.1-54 H, 514 Program (T-28) Boric Acid Corrosion lll.B1 .2-11 3.5.1-55 A Program (T-25)

SBK-L-17155 I Enclosure 2/ Page 203 U.S. Nuclear Regulatory Commission *1. Intended Component Type Function. Non-ASME Piping & Components -Concrete -Structural Exposed to Air Indoor Support Uncontrolled Non-ASME Piping & Structural Components -Concrete -Support Exposed to Air Outdoor Non-ASME Piping & Components -Lubrite -Structural Exposed to Air Indoor Support Uncontrolled Non-ASME -Stainless Steel -Structural Exposed to Air Indoor Support Uncontrolled Material Concrete Concrete Lubrite Stainless Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation * '1'1 :i:' I I Aging ,Effect Requiring Environment ' 1111 . I :J: .1 *1 +111.:IJ .. '1' Air Indoor Reduction in Concrete Anchor Uncontrolled Capacity (External) Air Outdoor Reduction in Concrete Anchor (External) Capacity Air Indoor Uncontrolled Loss of Mechanical Function (External) Nooe Air Indoor Deformation/reduction in Uncontrolled structural integrity (External) Aging NU REG 'Table 11so1 vo1. 2 * . .

Management 3.X;1 Note 1,f 1_1,1w Program*, ,i1' Ii :1* Structures Monitoring Program, Alkali-111.82-1 Silica Reaction (T-29) 3.5.1-40 A, E, 517 (ASR) Monitoring Program Structures Monitoring Program, Alkali-111.82-1 Silica Reaction (T-29) 3.5.1-40 A,E,517 (ASR) Monitoring Program Structures Monitoring 111.82-2 3.5.1-52 A (TP-1) Program Nooe Structures Monitoring Program, & 111.81 .2-8 Building (TP-4) 3.5.1-59 A, E, 520 Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 204 U.S. Nuclear Regulatory Commission " *' Componenf Type Intended 'Function Non-ASME Support -Carbon Structural Steel -Exposed to Air Indoor Support Uncontrolled Non-ASME Support -Carbon Structural Steel -Exposed to Air Outdoor Support Non-ASME Support -Carbon Structural Steel -in Air with Borated Support Water Leakage Panels -Aluminum -Exposed Structural to Air Indoor Uncontrolled Support Panels -Aluminum -in Air with Structural Borated Water Leakage Support Panels -Carbon Steel -Structural Exposed to Air Indoor Support Uncontrolled *I Material '1!11 ;!'I Steel Steel Steel Aluminum Aluminum Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation 1Eriv,ironment Aging Effect Requiring r'. ,, Management 1* 1. 1111 Air Indoor Uncontrolled Loss of Material (External) Air Outdoor Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Noo* Uncontrolled Deformation/reduction in (External) structural capacity Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Aging ,\'1l':1:ri NU REG Table Management 1801Vol.2 3.X.1 Note"':,. Program Item Item Structures lll.B2-10 Monitoring (T-30) 3.5.1-39 A Program Structures lll.B2-10 Monitoring 3.5.1-39 A Program (T-30) Boric Acid lll.B2-11 Corrosion (T-25) 3.5.1-55 A Program Noo* Structures Monitoring Program & lll.B3-2 3.5.1-58 A, E, 520 Building (TP-8) Deformation Monitoring Program Boric Acid lll.B3-4 Corrosion (T-3) 3.5.1-55 A Program Structures lll.B3-7 Monitoring (T-30) 3.5.1-39 A Program SBK-L-17155 I Enclosure 2/ Page 205 U.S. Nuclear Regulatory Commission Intended Component Type, ,1, Function ' I Panels -Carbon Steel -Exposed Structural to Air Outdoor Support Panels -Carbon Steel -in Air Structural with Borated Water Leakage Support Panels -Concrete -Exposed to Structural Air Indoor Uncontrolled Support Panels -Concrete -Exposed to Structural Air Outdoor Support Material ':1: .:1* '.1:. Steel Steel Concrete Concrete Table 3.5.2-6 Supports Summary of Aging Management Evaluation !'],* .:11'1'11.,:I' ' 11Vl ,11'11i.1'Jt' Aging Effect Environment Management ' ' Air Outdoor Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Reduction in Concrete Anchor Uncontrolled Capacity (External) Air Outdoor Reduction in Concrete Anchor (External) Capacity ,'1'1*1 111' ' ' i!]:irNGREGill11: 'l' "* 'If ": 1!1, I *I* I 11 I I :,j;Tabl'e* : 1 111 Ii: Management 1:. 1801 Yol. 21* I 3.X.111IJI Ii; '] ll'i1:1 :I

Ji: Pr()g.ram1'it!I

11i']i'1 .'*' i:I ,,.,,*, .. Item 1. . .,.,,,,, Structures lll.B3-7 Monitoring 3.5.1-39 A Program (T-30) Boric Acid lll.B3-8 Corrosion (T-25) 3.5. 1-55 A Program Structures Monitoring Program, Alkali-lll.B3-1 Silica Reaction (T-29) 3.5. 1-40 A, E, 517 (ASR) Monitoring Program Structures Monitoring Program, Alkali-lll.B3-1 Silica Reaction (T-29) 3.5. 1-40 A, E, 517 (ASR) Monitoring Program SBK-L-17155 I Enclosure 2/ Page 206 U.S. Nuclear Regulatory Commission Intended Component Type Function Platform -Concrete -Exposed Structural to Air Indoor Uncontrolled Support Platform -Concrete -Exposed Structural to Air Outdoor Support Platform Supports -Carbon Structural Steel -Exposed to Air Indoor Support Uncontrolled Platform Supports -Carbon Structural Steel -Exposed to Air Outdoor Support Platform Supports -Carbon Structural Steel -Exposed to Air Indoor Support Uncontrolled Material Concrete Concrete Steel Steel Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation ; ;-;I j'l:I: Jl:i 1;i.1; 111' _:j:i Aging Effect Requiring I Environment Management Air Indoor Reduction in Concrete Anchor Uncontrolled (External) Capacity Air Outdoor Reduction in Concrete Anchor (External) Capacity Air Indoor Uncontrolled Loss of Material (External) Air Outdoor Loss of Material (External) Air Indoor Deformation/reduction in Uncontrolled structural capacity (External) 1 .* Aging NUREGlii 11 **:*Table I:! I 1801 Vol. 2 ., ' Management 1* 3.X.1 Note Program Item *lte.m Structures Monitoring Program, Alkali-111.85-1 Silica Reaction 3.5.1-40 A,E,517 (ASR) (T-29) Monitoring Program Structures Monitoring Program, Alkali-111.85-1 Silica Reaction (T-29) 3.5.1-40 A,E,517 (ASR) Monitoring Program Structures 111.85-7 Monitoring (T-30) 3.5.1-39 A Program Structures 111.85-7 Monitoring 3.5.1-39 A, 503 Program (T-30) Structures 111.85-7 Monitoring (T-30) 3.5.1-59 E, 520 Program, BD SBK-L-17155 I Enclosure 2/ Page 207 U.S. Nuclear Regulatory Commission Intended Component Type Function Platform Supports -Carbon Structural Steel -Exposed to Air Support Outdoor Platform Supports -Carbon Structural Steel -in Air with Borated Support Water Leakage Spent Fuel Rack Support -Structural Stainless Steel -in Treated Water Support Thermal Insulation Aluminum Structural Jacketing -Exposed to Air Support Indoor Uncontrolled Thermal Insulation Stainless Structural Steel Jacketing -Exposed to Air Support Indoor Uncontrolled Material Steel Steel Stainless Steel Aluminum Stainless Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation "

Aging Effect Requ.iring Environment Management Air Outdoor Deformation/reduction in (External) structural capacity Air w/Borated Water Leakage Loss of Material (External) Treated Borated Cracking Water (External) Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Aging NU REG Table Management 1801 Yol. 2 3.X.1 Note Program Item Item Structures lll.B5-7 Monitoring (T-30) 3.5.1-61 E, 520 Program, BD Boric Acid lll.B5-8 Corrosion (T-25) 3.5.1-55 A Program Water Chemistry Vll.A2-7 3.3.1-90 A, 507 Program (A-97) Nooe Building lll.B2-4 Deformation (TP-8) 3.5.1-58 A, E, 520 Monitoring Program Nooe Building lll.B2-8 Deformation (TP-4) 3.5.1-59 A, E, 520 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 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-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 (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 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 Intended Component Type Function TUR -Aluminum -in Air Indoor Structural Uncontrolled Support TUR -Built-Up Roofing -Structural Exposed to Air Outdoor Support TUR -Carbon Steel -Exposed Structural to Air Outdoor Support TUR -Carbon Steel -in Air Structural Indoor Uncontrolled Support TUR -Concrete (Sump) -Structural Exposed to Raw Water Support Material Aluminum Roofing Steel Steel Concrete Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Indoor Uncontrolled None (External) Air Outdoor Separation, Environmental (External) Degradation, Water In-Leakage Air Outdoor Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Raw Water Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item None 111.83-2 3.5.1-58 A Structures Ill .A6-12 Monitoring 3.5.1-44 H, 505 Program, (TP-7) Structures Ill .A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures Ill .A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures Ill .A3-4 Monitoring 3.5.1-31 A, 509 Program (T-05)

SBK-L-17155 I Enclosure 2/ Page 211 U.S. Nuclear Regulatory Commission Intended Component Type Function TUR -Concrete (Sump) -Structural Exposed to Raw Water Support TUR -Concrete -Exposed to Air Structural Outdoor Support TUR -Concrete -Exposed to Air Structural Outdoor Support TUR -Concrete -Exposed to Air Structural Outdoor Support ,!j Material Concrete Concrete Concrete Concrete Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation I Aging Effect Requiring Environment Management Raw Water (External) Expansion and Cracking Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) *.Aging I. NUREG Table *:1:,:;:r: 3.x.1 ,:j' Managemen.t 1801 Vol. 2 :. Note* Program Item Item Structures Monitoring Program, Alkali-Ill .A3-2 Silica Reaction (T-03) 3.5.1-27 A, 517 (ASR) Monitoring Program Structures Ill .A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Ill .A3-2 3.5.1-27 A, 517 Silica Reaction (T-03) (ASR) Monitoring Structures Ill .A3-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 212 U.S. Nuclear Regulatory Commission Component Type Intended Function TUR -Concrete -Exposed to Air I Structural Outdoor Support TUR -Concrete -in Air Indoor Uncontrolled TUR -Concrete -in Air Indoor Uncontrolled TUR -Concrete -in Air Indoor Uncontrolled I Structural Support Structural Support I Structural Support TUR -Concrete Masonry Units -I Structural in Air Indoor Uncontrolled Support Material I Concrete I Concrete Concrete I Concrete I Concrete Block Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation Environment I Air Outdoor (External) Air Indoor I Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor I Uncontrolled (External) Air Indoor I Uncontrolled (External) * :i:1.I: : Aging Effect Requiring Management I Loss of Material, Cracking Aging Management Program 1 Structures Monitoring Program --Cracking, Loss of Bond, Loss of M .t . I . I Structures Material (Spalling, Scaling) Expansion and Cracking Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Cracking Structures Monitoring Program, AlkaliSilica Reaction (ASR) Monitoring Structures Monitoring Program Structures Monitoring Program NU REG 1801 Vol. 2 Item Ill .A3-6 (T-01) Ill .A3-9 (T-04) Ill .A3-2 (T-03) I Ill .A3-10 (T-06) I Ill .A3-11 (T-12) Table 3.X.1 Item 3.5.1-26 3.5.1-23 3.5.1-27 I 3.5.1-24 I 3.5.1-43 Note A A A, 517 IA IA SBK-L-17155 I Enclosure 2/ Page 213 U.S. Nuclear Regulatory Commission Component Type Intended Function TUR -Fire Penetration Seal -in Fire Barrier Air Indoor Uncontrolled TUR -Fire Penetration Seal -in Fire Barrier Air Indoor Uncontrolled TUR -Penetration Seal -Structural Exposed to Air Outdoor Support Material Elastomer Elastomer Elastomer Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation I' 1,i; .1,., '* ,I* Environment Aging Effect Requiring Management Air Indoor Increased Hardness, Shrinkage Uncontrolled (External) and Loss of Strength Air Indoor Increased Hardness, Shrinkage Uncontrolled (External) and Loss of Strength Air Outdoor Increased Hardness, Shrinkage (External) and Loss of Strength Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Fire Protection Vll.G-1 3.3.1-61 A Program (A-19) Structures Vll.G-1 Monitoring 3.3.1-61 E, 514 Program (A-19) Structures Vll.G-2 Monitoring 3.3.1-61 E, 515 Program (A-20)

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-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 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-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 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 2/ Page 215 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Built-Up Roofing -SERVICE WATER COOLING Shelter, TOWER Including Switchgear Protection Rooms in Air Outdoor WCS -Built-Up Roofing -SERVICE WATER Shelter, PUMPHOUSE in Air Outdoor Protection WCS -Carbon Steel Door -SERVICE WATER COOLING Shelter, TOWER Including Switchgear Protection Rooms in Air Outdoor WCS -Carbon Steel Door -SERVICE WATER COOLING Structural TWR Including Swgr Rms in Air Support Indoor Uncontrolled WCS -Carbon Steel Door -SERVICE WATER Structural PUMPHOUSE in Air Indoor Support Uncontrolled WCS -Carbon Steel Door -Shelter, SERVICE WATER Protection PUMPHOUSE in Air Outdoor Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Material Environment Management Separation, Environmental Air Outdoor Roofing (External) Degradation, Water In-Leakage Separation, Environmental Roofing Air Outdoor Degradation, Water In-(External) Leakage Steel Air Outdoor Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material *:11 Aging NUREG.11801 Tab Management Vol. 2 Item 3.X.1 Note Program Item I Structures Monitoring Program, Building lll.A6-12 H, 505, Deformation (TP-7) 3.5.1-44 E, 520 Monitoring Program Structures Monitoring Program, Building lll.A6-12 3.5.1-44 H, 505, Deformation (TP-7) E, 520 Monitoring Program Structures Monitoring lll.A3-12 3.5.1-25 A, 503 (T-11) Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program SBK-L-17155 I Enclosure 2/ Page 216 U.S. Nuclear Regulatory Commission Component Type Intended Function WCS -Carbon Steel Fire Door -SERVICE WATER COOLING Fire Barrier TWR Including Swgr Rms in Air Indoor Uncontrolled WCS -Carbon Steel Fire Door -SERVICE WATER Fire Barrier PUMPHOUSE in Air Indoor Uncontrolled WCS -Carbon Steel -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms in Support Air Outdoor WCS -Carbon Steel -SERVICE Structural WATER COOLING TOWER in Support Raw Water WCS -Carbon Steel -SERVICE Structural WATER COOLING TOWER in Support Raw Water WCS -Carbon Steel -SERVICE Structural WATER COOLING TOWER in Support Raw Water Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation 1:l I: '*' :, . Fl"I' Material Environment Aging Effect Requiring Management Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Steel Air Outdoor Loss of Material (External) Raw Water Steel (External) Loss of Material Raw Water Steel (External) Loss of Material Raw Water Steel (External) Loss of Material Aging n* .Jable Management NUREG 18P1 *:3.X.1 Note Program Vol. 2 Item ltein Fire Protection Vll.G-3 3.3. 1-63 A Program (A-21) Fire Protection Vll.G-3 3.3. 1-63 A Program (A-21) Structures Monitoring lll.A3-12 3.5. 1-25 A, 503 (T-11) Program Structures 111.A6-11 Monitoring (T-21) 3.5.1-47 E, 511 Program Structures lll.A6-11 Monitoring (T-21) 3.5.1-47 E, 511 Program Structures 111.A6-11 Monitoring (T-21) 3.5.1-47 H, 511 Program SBK-L-17155 I Enclosure 2/ Page 217 U.S. Nuclear Regulatory Commission Component Type WCS -Carbon Steel -SERVICE WATER COOLING TOWER in Raw Water WCS -Carbon Steel -SERVICE WATER COOLING TWR Including Swgr Rms in Air Indoor Uncontrolled WCS -Carbon Steel -SERVICE WATER PUMPHOUSE in Air Indoor Uncontrolled WCS -Carbon Steel -SERVICE WATER PUMPHOUSE in Raw Water WCS -Carbon Steel -SERVICE WATER PUMPHOUSE in Raw Water WCS -Carbon Steel -SERVICE WATER PUMPHOUSE in Raw Water Intended Function Structural Support Structural Support Structural Support Structural Support Structural Support Structural Support Material Steel Steel Steel Steel Steel Steel Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Raw Water (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Raw Water (External) Raw Water (External) Raw Water (External) . I -; ... , .Table .. , * . Agmg NUREG 180,111 1 :::,3* x*. I ' * * ' ' 'II I 1:11:1!11.,. *, *1* '.A. g __ in_ g

I . ' M_

anagemen_ t. *I.* "Vol_:_,z_ ltery:i_ wi" I . ,, Item* .. ; . *:1:1: Management "1**' 1*1, * *l:i1Program ,, *1:. , "I* l:i:."1 :1 *1* " '1* I .. J, *,*1*::1:i:1: *1;1 :1; . !* ' ' ' 1. iii I Ii. Note 1: Loss of Material Loss of Material Loss of Material Loss of Material Loss of Material Loss of Material Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program lll.A6-11 (T-21) lll.A3-12 (T-11) lll.A3-12 (T-11) lll.A6-11 (T-21) lll.A6-11 (T-21) lll.A6-11 (T-21) 3.5.1-47 I E, 511 3.5.1-25 I A 3.5.1-25 I A 3.5. 1-47 I E, 511 3.5. 1-47 I E, 511 3.5.1-47 I H, 511 SBK-L-17155 I Enclosure 2/ Page 218 U.S. Nuclear Regulatory Commission *1;. , Intended' Component Type Function ,' 1 ' ' WCS -Carbon Steel -SERVICE Structural WATER PUMPHOUSE in Raw Support Water WCS -Carbon Steel -SERVICE Shelter, WATER PUMPHOUSE Siding in Air Indoor Uncontrolled Protection WCS -Carbon Steel -SERVICE Shelter, WATER PUMPHOUSE Siding in Air Outdoor Protection WCS -Concrete -Structural CIRCULATING WATER PUMPHOUSE Below Grade Support WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE Below Grade Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation ,I ,I :j:'J',, ,' ,,, j.11, :t Aging Effect Requirir;ig ,, , Material Environment Management '1 '!:'" ii: ; ' Raw Water Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel Loss of Material (External) Ground Cracking, Loss of Bond, Loss Concrete Water/Soil (External) of Material (Spalling, Scaling) Ground Concrete Water/Soil Expansion and Cracking (External) ,;p,, IA. I :I l'l'I 'if:, 11 'I ilJ1:1j 11'*1T bl I:*, i 1:11:, ,,mog 'i: ,;lil:i :1:1 NUREG*l1 aotl ii ,1, ,., , a 1e,, lffl Note Management :::,, ::1ti:**l1*t.1 t'11l**1 'I ,: ' 113.X.11:1 i' Program. ,. ' 1 Nol;1 2 Item ,' 1!,,:'::111,i I, ., I* ltem1. :. 1:1, ' " Structures lll.A6-11 Monitoring (T-21) 3.5.1-47 E, 511 Program Structures lll.A3-12 Monitoring 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures 111.A3-4 Monitoring 3.5. 1-31 A Program (T-05) Structures Monitoring Program , Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5. 1-27 517, 519 Program & Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 219 U.S. Nuclear Regulatory Commission lntende'd tlii ' Component Type Function WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE Below Grade WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE Below Grade WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE Below Grade WCS -Concrete -CIRCULATING WATER Structural PUMPHOUSE in Air Indoor Support Uncontrolled WCS -Concrete -CIRCULATING WATER Structural PUMPHOUSE in Air Indoor Support Uncontrolled " 1:111 i:. 1Material 111 1*1 ' Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation '1'1Environment Aging Effect Requiring 11 ;(:1 :I::. Ah:', 1 I; Management ,1*1 .. 1!' ""' ,,, ,,. Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) (External) Air Indoor Uncontrolled Expansion and Cracking (External) .1 I J1 lJ I 1*1 :j ,.'"J:,'i l*lll,,1':1 "'1'1' tTablel".i:i:' ,;j: 111: il:I, . ' Aging:iJ , . NUREG 1801 'I' 'Ii .Iii Management1 3.X.1 1Notelil'I Vol. 2 Item Program Item , t1/m1****., :1 Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures Monitoring lll.A3-9 3.5.1-23 A (T-04) Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 220 U.S. Nuclear Regulatory Commission Intended Component Type Function *1:1 WCS -Concrete -CIRCULATING WATER Structural PUMPHOUSE in Air Indoor Support Uncontrolled WCS -Concrete -Shelter, CIRCULATING WATER PUMPHOUSE in Air Outdoor Protection WCS -Concrete -CIRCULATING WATER Shelter, Protection PUMPHOUSE in Air Outdoor WCS -Concrete -Shelter, CIRCULATING WATER Protection PUMPHOUSE in Air Outdoor WCS -Concrete -Shelter, CIRCULATING WATER PUMPHOUSE in Air Outdoor Protection Material 'I' Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation ii! I 11m '1:1:1,!i I I'll', ' ' A in 'I Effect Re uirin , Environment . I *,:l.g lgl, l'l.1.1." 1111*.q :* .. 1: *lgl*I: !*1'l1 1 Management1:1 *1 {

I J .I . Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) ;i.1 Aging Table 111:1 NUREG 180,1, .1: '3.:X.1 H1: Management V I I 111* Note H. :I. ' , .,: ' ' ilj I ii:? "/Tu:m !*,:," l1f ' 11:1 1:1!: },. 1.:1!ji1*.;1:-* ep11n1. i' Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01)

SBK-L-17155 I Enclosure 2/ Page 221 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE in Raw Water WCS -Concrete -CIRCULATING WATER Structural Support PUMPHOUSE in Raw Water WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE in Raw Water WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE in Raw Water WCS -Concrete -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms Support Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation I Aging Effect Requiring Environment Management Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water Expansion and Cracking (External) Raw Water Increase in Porosity and (External) Permeability, Loss of Strength Raw Water (Extern a!) Loss of Material Ground Water/Soil Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) *,Agiri'9'J, ilt, ,11!1,. *11i:l:1*1*1:t::l1* ,, + ii ,I .. NUREG 18011 Management Vol. 2 Item 3.X.1 Note .. Program Item Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A, 509 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A Program Structures lll.A6-7 Monitoring (T-20) 3.5.1-45 E, 511 Program Structures Monitoring lll.A3-4 3.5.1-31 A Program (T-05)

SBK-L-17155 I Enclosure 2/ Page 222 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Concrete -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms Support Below Grade WCS -Concrete -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms Support Below Grade WCS -Concrete -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms Support Below Grade WCS -Concrete -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms Support Below Grade WCS -Concrete -SERVICE WATER COOLING TOWER Missile Barrier Including Switchgear Rooms in Air Outdoor Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Effect Requiring' 'l Material Environment Management Ground Concrete Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Concrete Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Concrete Water/Soil Permeability, Loss of (External) Strength Ground Concrete Water/Soil Loss of Material, Cracking (External) Cracking, Loss of Bond, Loss Concrete Air Outdoor (External) of Material (Spalling, Scaling) *';1::1l'i1Agin'g II l:i: :li:ll'"' '1:l:::,,:al:111l:1:*1:1::1 l' ,11 1:1: .liable ;;* ' Management . NLJREG, 1801, '*3.X.1 " Note iJ Vol. 2 Item *Item Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) A, E, Monitoring lll.A3-2 3.5.1-27 Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program SBK-L-17155 I Enclosure 2/ Page 223 U.S. Nuclear Regulatory Commission r ' *I* !:I Component Type Intended Function WCS -Concrete -SERVICE WATER COOLING TOWER Shelter, Including Switchgear Rooms in Protection Air Outdoor WCS -Concrete -SERVICE WATER COOLING TOWER Missile Barrier Including Switchgear Rooms in Air Outdoor WCS -Concrete -SERVICE WATER COOLING TOWER Shelter, Including Switchgear Rooms in Protection Air Outdoor WCS -Concrete -SERVICE WATER COOLING TOWER Including Switchgear Rooms in Missile Barrier Air Outdoor ,, :i: Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation ;1: Aging Effect Requiring Environmer:it Management ii. Jfli] ' ljjlll ,. 'I' Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Air Outdoor (External) Expansion and Cracking Increase in Porosity and Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) 'Aging I* l'.I . ' '".*'*I* .,.1 . l'li'll11111li . NUREG 1801' Table* *'*1' Ji ,::,-:.:Ii :j:l'*11: Management 3.X.1 . "Ir Vol. 2 Item Notet'*i!ii:I Program Item :I:: :J:1 Structures Monitoring lll.A3-9 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Proaram Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 224 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Concrete -SERVICE WATER COOLING TOWER Shelter, Including Switchgear Rooms in Protection Air Outdoor WCS -Concrete -SERVICE WATER COOLING TOWER Missile Barrier Including Switchgear Rooms in Air Outdoor WCS -Concrete -SERVICE WATER COOLING TOWER Shelter, Including Switchgear Rooms in Protection Air Outdoor WCS -Concrete -SERVICE Structural WATER COOLING TOWER in Raw Water Support WCS -Concrete -SERVICE Ultimate Heat WATER COOLING TOWER in Sink Raw Water WCS -Concrete -SERVICE Structural WATER COOLING TOWER in Support Raw Water Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation iji ' *'*1: I 11

Aging Effect Requiring Material Environment Increase in Porosity and Concrete Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Concrete Air Outdoor Loss of Material, Cracking (External) Concrete Air Outdoor Loss of Material, Cracking (External) Cracking, Loss of Bond, Loss Raw Water Concrete (External) of Material (Spalling, Scaling) Cracking, Loss of Bond, Loss Raw Water Concrete (External) of Material (Spalling, Scaling) Raw Water Concrete (External) Expansion and Cracking Aging Table :1:, NUREG 1801 Management 3.X.1 Note Vol. 2 Item Program Item Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-6 Monitoring (T-01) 3.5. 1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5. 1-26 A Program Structures lll.A3-4 Monitoring 3.5. 1-31 A, 509 (T-05) Program Structures lll.A3-4 Monitoring 3.5.1-31 A, 509 (T-05) Program Structures Monitoring Program, Alkali-.Silica Reaction (ASR) lll.A3-2 3.5.1-27 A, E, Monitoring (T-03) 517, 519 Program & Building Deformation Monitorina SBK-L-17155 I Enclosure 2/ Page 225 U.S. Nuclear Regulatory Commission ll' Component Type Intended Function WCS -Concreti;! -SERVICE WATER COOLING TOWER in Ultimate Heat Raw Water Sink WCS -Concrete -SERVICE Structural WATER COOLING TOWER in Support Raw Water WCS -Concrete -SERVICE Ultimate Heat WATER COOLING TOWER in Sink Raw Water WCS -Concrete -SERVICE Structural WATER COOLING TOWER in Support Raw Water Material 1*: Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Effect Requiring 1 Environment Management ',,' '1'111111111 111 11*., ':j, " ::i Raw Water Expansion and Cracking (External) Raw Water Increase in Porosity and (External) Permeability, Loss of Strength Raw Water Increase in Porosity and (External) Permeability, Loss of Strength Raw Water (External) Loss of Material I ' Aging NUREG 1801 1, Tablerll Management Vol. 2 Item 3.X.1 Program Item Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A Program Structures lll.A6-7 Monitoring (T-20) 3.5.1-45 E, 511 Program SBK-L-17155 I Enclosure 2/ Page 226 U.S. Nuclear Regulatory Commission ,, I:' ' l: Intended I' Comppnent Type Function WCS -Concrete -SERVICE Ultimate Heat WATER COOLING TOWER in Sink Raw Water WCS -Concrete -SERVICE WATER COOLING TWR Fire Barrier Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Structural Including Swgr Rms in Air Support Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Fire Barrier Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Structural Including Swgr Rms in Air Support Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Fire Barrier Including Swgr Rms in Air Indoor Uncontrolled Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation .1: t 1:1, I *: Aging Effect Requiring Material, ill , Environment Management ii* Raw Water Concrete (External) Loss of Material Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) (External) Air Indoor Concrete Uncontrolled Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Indoor Concrete Uncontrolled Concrete Cracking and (External) Spalling I 1 11 :lb .:I: :i,(' Table' 11 \I 'I" 'II: :1,1' NUREG 1801 Management Vol. 2 Item, 3.X.1 I I: Note "lI Program Item '" ' j'I J!1:.ll: Structures lll.A6-7 Monitoring (T-20) 3.5.1-45 E, 511 Program Fire Protection Vll.G-29 3.3.1-67 A Program (A-91) Fire Protection Vll.G-29 3.3.1-67 A Program (A-91) Structures Monitoring lll.A3-9 3.5, 1-23 A (T-04) Program Structures Monitoring lll.A3-9 3.5.1-23 A Program (T-04) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90)

SBK-L-17155 I Enclosure 2/ Page 227 U.S. Nuclear Regulatory Commission *1:; Component Type r ,i;11 Intended .Function ***1 ' 1:1: ;,,, WCS -Concrete -SERVICE WATER COOLING TWR Structural Including Swgr Rms in Air Support Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Fire Barrier Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Structural Including Swgr Rms in Air Support Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Fire Barrier Including Swgr Rms in Air Indoor Uncontrolled 1;1; Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation 'ii ', I* .. *. 'Ji j:i'J:ii1 11 11 ::j:1:*1*1;, ' Effect 'Requiring Material Environment Management ' 1 Air Indoor Concrete Uncontrolled Concrete Cracking and (External) Spalling Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Air Indoor Concrete Uncontrolled Concrete Cracking and (External) Spalling T1*1:(H:*:1*1 ' I 1:1l: !;. I .,ii 1ii'fi!' llrli' 1'!1111 ji:llJ.i "*' i ,, *r:*. ":' !'1,*,,:i:1* ' , *. 1;111A9ingl,* Iii , ':rab!e 1,1, 11 ,, ' "' *I j:j1': 1: NUREG11801 ** , *Management H' 11 V ol.1 2 Item ., ':' .. l'I Note 11' Program Item 'jl! 'l'Jlli' f' 1: ' *::: 1::1: Fire Protection Vll.G-28 3.3. 1-65 A Program (A-90) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5. 1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5. 1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Fire Protection Vll.G-28 3.3. 1-65 A Program (A-90)

SBK-L-17155 I Enclosure 2/ Page 228 U.S. Nuclear Regulatory Commission Component Type WCS -Concrete -SERVICE WATER COOLING TWR Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER PUMPHOUSE Below Grade WCS -Concrete -SERVICE WATER PUMPHOUSE Below Grade Intended Function Structural Support Fire Barrier Structural Support Structural Support Structural Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Environment Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Ground Water/Soil (External) Ground Water/Soil (External) l;:l*i . Aging Effect Requiring 1.1 Management Concrete Cracking and Spalling Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) Expansion and Cracking Aging Management'" ',Program Fire Protection Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program, Silica Reaction (ASR) Monitoring Program & Building Deformation Monitoring Program NUREG 1801 Vol. 2 Item Vll.G-28 (A-90) lll.A3-10 (T-06) lll.A3-10 (T-06) lll.A3-4 (T-05) lll.A3-2 (T-03) Table 3.X.1 Item 3.3.1-65 3.5.1-24 3.5.1-24 3.5.1-31 3.5.1-27 N.ote A A A A A,E, 517, 519 SBK-L-17155 I Enclosure 2/ Page 229 U.S. Nuclear Regulatory Commission I ,*1 Component Type, ,Intended I ! fiuriction* WCS -Concrete -SERVICE Structural WATER PUMPHOUSE Below Support Grade WCS -Concrete -SERVICE Structural WATER PUMPHOUSE Below Support Grade WCS -Concrete -SERVICE Structural WATER PUMPHOUSE Below Support Grade WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Indoor Uncontrolled Support WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled !'Jlaterial *1+1 *ii' Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Effect II:' 1:['lilJli:i1ll'l1[ 1:!:1::'1i:lil11l:11111111:1:J;1W jll 111:1*1'11 ,,, , .. Environment '1il NUREG 1,11.BOt' 11 3:X.1 'Ii '!111!1iNote .1' M , t, ,. ,* :.: 'Management 1. : "1 p ' ,, Vol. 2 Item '*1 Item 1 ' 1*i.1t.':iV:1 . ,1 , . rogram * ' . l*I 'lfJl:i;1':::*,1:1* Ground Increase in Porosity and Structures 111.A3-5 Water/Soil Permeability, Cracking, Loss Monitoring (T-07) 3.5.1-31 A (External) of Material (Spalling, Scaling) Program Ground Increase in Porosity and Structures lll.A3-7 Water/Soil Permeability, Loss of Monitoring (T-02) 3.5.1-32 A, 509 (External) Strength Program Ground Structures lll.A3-6 Water/Soil Loss of Material, Cracking Monitoring (T-01) 3.5.1-26 A (External) Program Air Indoor Fire Protection Vll.G-29 Uncontrolled Loss of Material Program (A-91) 3.3.1-67 A (External) Air Indoor Fire Protection Vll.G-29 Uncontrolled Loss of Material 3.3.1-67 A (External) Program (A-91) Air Indoor Cracking, Loss of Bond, Loss Structures lll.A3-9 Uncontrolled Monitoring 3.5.1-23 A (External) of Material (Spalling, Scaling) Program (T-04)

SBK-L-17155 I Enclosure 2/ Page 230 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Indoor Uncontrolled Support WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Indoor Uncontrolled Support WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Support Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment I' 1F,:i:I Management I', , 1 ,I Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging NUREG 1801 Table Management 3.X.1 Note Program Vol. 2 Item Item Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Proqram Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 231 U.S. Nuclear Regulatory Commission ,., Intended Component Type Function WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Indoor Uncontrolled Support WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Support Indoor Uncontrolled WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Missile Barrier Outdoor . 'l Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Aging I* " '1; *'"'1',!I NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note Program Item Fire Protection Vll.G-28 3.3. 1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures lll.A3-10 Monitoring (T-06) 3.5. 1-24 A Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04)

SBK-L-171 SS I Enclosure 2/ Page 232 U.S. Nuclear Regulatory Commission *111:1. , "I Intended 1Type 1: Function WCS -Concrete -SERVICE Shelter, WATER PUMPHOUSE in Air Protection Outdoor WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Missile Barrier Outdoor WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Shelter, Outdoor Protection WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Missile Barrier Outdoor ii 11* Material ,1:1.1 *t *I Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation ,., Aging Effect Requiring *1Environment Management I :11 *:I* 'j,, Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) , 111'1:111:1T , , '1:1 11 t , 'I' t* ,,JF111 'I** Table ** 111 11 ' , ' .. Agmg I . , 1NUREG11ao1' ! I I ! 11 ' I Management* 3.X.1 Note 1,: Program Vol. 2 Item Item . I*, . :r i Structures 111.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 233 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Concrete -SERVICE Shelter, WATER PUMPHOUSE in Air Protection Outdoor WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Missile Barrier Outdoor WCS -Concrete -SERVICE Shelter, WATER PUMPHOUSE in Air Protection Outdoor WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Raw Water Support WCS -Concrete -SERVICE WATER PUMPHOUSE in Raw Structural Water Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation 1:i; .* !1, 1:1 '1 Environment

1,1,,.1 M ,,,,*1 ... "* .,,,,h t''"j"*' .1 ... 11i:1t1t1 , *

anagemen

1.i ,, :1r1 'I :I . y ':i'I fl:!:,. Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Air Outdoor (External) Loss of Material, Cracking Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water Expansion and Cracking (External) }','* "'*A: ... ,. .. 1.* ,J .. 1,:,", , .,.: ' Table. ' :::11:!' '"' gmg" 11!: l'E NUREGl1aofli, 'ii' ' ,,.,,*j1 'jiv. 11,211t 111:,J1, n11.1.3:x.1w* ,

Note .... ,: ... ,, 1°**."*I II j:il ,* 111111' :111Program +" 1 :1 ' ,. ' 'I: '*'l'l:',*:I* I** I 1*':'1** ,**,,1*!***11, .. ,i* Structures llLA3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-4 Monitoring 3.5.1-31 A, 509 Program (T-05) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 234 U.S. Nuclear Regulatory Commission Component Type WCS -Concrete -SERVICE WATER PUMPHOUSE in Raw Water WCS -Concrete -SERVICE WATER PUMPHOUSE in Raw Water WCS -Fire Penetration Seal -SERVICE WATER COOLING TWR including Swgr Rms in Air Indoor Uncontrolled WCS -Fire Seal -SERVICE WATER PUMPHOUSE in Air Indoor Uncontrolled WCS -Penetration Seal -SERVICE WATER COOLING TOWER Including Switchgear Rooms in Air Outdoor WCS -Penetration Seal -SERVICE WATER PUMPHOUSE in Air Outdoor Intended Function Structural Support Structural Support Fire Barrier Fire Barrier Shelter, Protection Shelter, Protection Material Concrete Concrete Elastomer Elastomer Elastomer Elastomer Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation 'l'I 1,1,,:1:1., \ ,, . . , 1

Aging . , * ',,,I ,Managem1ent}' Environment ,.,1:1:k!I: 1 :1' :I! 'j':',1 l!I* ,1, , P1rogram,'li'l,l;j!1, 1:i ;:. 1 ' ',J1' * ' Raw Water (External) Raw Water (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Outdoor (External) Air Outdoor (External) Increase in Porosity and Permeability, Loss of Strength Loss of Material Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Structures Monitoring Program Structures Monitoring Program Fire Protection Program Fire Protection Program Structures Monitoring Program Structures Monitoring Program *1' Table:' ... 801'1 'I '"' " '"'1 , . , Note .... '"'l'i' ,. :1,jiP!X*l: i!*l'11."*', *,1:1 , 11,vo1:1211tepi ,* *,1 H ltenili' q:, 'P:Hii l:'il' *1:1 ':!:1111 1 ' , I ',, 111.A3-7 (T-02) lll.A6-7 (T-20) Vll.G-1 (A-19) Vll.G-1 (A-19) Vll.G-2 (A-20) Vll.G-2 (A-20) 3,5.1-32 I A 3.5.1-45 I E, 511 3.3.1-61 I A 3.3.1-61 I A 3.3.1-61 I E, 515 3.3.1-61 I E, 515 SBK-L-17155 I Enclosure 2/ Page 235 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Penetration Sea/ -SERVICE WATER COOLING Shelter, TOWER Including Switchgear Protection Rooms in Air Outdoor WCS -Penetration Sea/ -SERVICE WATER Shelter, Protection PUMPHOUSE in Air Outdoor WCS -Fire Penetration Seal -SERVICE WATER COOLING Fire Barrier TWR including Swgr Rms in Air Indoor Uncontrolled WCS -Fire Seal -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled Material Elastomer Elastomer Elastomer Elastomer Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation . '" '. '"' ll' ,1,11 Aging Effect'Requiring Environment Management Air Outdoor Separation (External) Air Outdoor Separation (External} Air Indoor Uncontrolled Separation (External) Air Indoor Uncontrolled Separation (External) ., Aging :1:' 'I' 111Table J 1;1

NUREG 1801. I " Management Vol. 2 Item 3.X.1 Note Program Item Structures Monitoring Program, Building Vll.G-2 3.5.1-60 E,520 Deformation (A-20) Monitoring Program Structures Monitoring Program, Building Vll.G-2 3.5.1-60 E, Deformation (A-20) 520 Monitoring Program Structures Monitoring Program, Building Vll.G-1 3.5.1-60 E, 520 Deformation (A-19) Monitoring Program Structures Monitoring Program, Building Vll.G-1 3.5.1-60 E, 520 Deformation (A-19) Monitoring Program SBK-L-17155 I Enclosure 2/ Page 236 U.S. Nuclear Regulatory Commission Standard Notes Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation 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 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-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 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 (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 components by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Building Deformation Monitoring Program. to SBK-L-17155 Supplement 58 -NextEra Energy Seabrook's revised LRA Appendix A -Updated Final Safety Analysis Report Supplement Table A.3, License Renewal 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 LOCATION Provide confirmation and acceptability of the 1. PWR Vessel Internals implementation ofMRP-227-A by addressing the plant-A.2.1.7 specific Applicant/Licensee Action Items outlined in section 4.2 of the NRC SER. Enhance the program to include visual inspection for 2. Closed-Cycle Cooling Water cracking, loss of material and fouling when the in-scope A.2.1.12 systems are opened for maintenance. Inspection of Overhead Enhance the program to monitor general corrosion on the Heavy Load and Light Load crane and trolley structural components and the effects of A.2.1.13 3. (Related to Refueling) Handling Systems wear on the rails in the rail system. Inspection of Overhead 4. Heavy Load and Light Load Enhance the program to list additional cranes for A.2.1.13 (Related to Refueling) monitoring. Handling Systems Enhance the program to include an annual air quality test 5. Compressed Air Monitoring requirement for the Diesel Generator compressed air sub A.2.1.14 system. 6. Fire Protection Enhance the program to perform visual inspection of A.2.1.15 penetration seals by a fire protection qualified inspector. Enhance the program to add inspection requirements such 7. Fire Protection as spalling, and loss of material caused by freeze-thaw, A.2.1.15 chemical attack, and reaction with aggregates by qualified inspector. --------**---------SCHEDULE Complete Prior to the period of extended operation. Prior to the period of extended operation. Prior to the period of extended operation. Prior to the period of extended operation. Prior to the period of extended operation. Prior to the period of extended operation.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 3 8. Fire Protection 9. Fire Water System 10. Fire Water System 11. Fire Water System Enhance the program to include the performance of visual inspection of fire-rated doors by a fire protection qualified inspector. Enhance the program to include NFPA 25 (2011 Edition) guidance for "where sprinklers have been in place for 50 years, they shall be replaced or representative samples 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 periodic flow testing of the fire water system in accordance 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 examinations are performed. These inspections will be 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 Prior to the period of extended A.2.1.15 operation. Prior to the period of extended A.2.1.16 operation. Prior to the period of extended A.2.1.16 operation. Within ten years prior to the A.2.1.16 period of extended operation.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 4 12. Aboveground Steel Tanks 13. Fire Water System 14. Fuel Oil Chemistry 15. Fuel Oil Chemistry 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 managing the aging effects of loss of material and cracking, 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 internal bottom surface of the two Fire Protection Water 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 offloading to the Auxiliary Boiler fuel oil storage tank and 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 tank at least once per quarter and to remove water as necessary. A.2.1.17 Within 10 years prior to the period of extended operation. A.2.1.16 Within ten years prior to the period of extended operation. Prior to the period of extended A.2.1.18 operation. A.2.1.18 Prior to the period of extended operation.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 5 16. Fuel Oil Chemistry 17. Fuel Oil Chemistry 18. Reactor Vessel Surveillance 19. Reactor Vessel Surveillance 20. Reactor Vessel Surveillance 21. Reactor Vessel Surveillance Enhance the program to require draining, cleaning and inspection of the diesel fire pump fuel oil day tanks on a 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 fuel oil storage tanks, Diesel Generator fuel oil day tanks, diesel fire pump fuel oil day tanks and auxiliary boiler fuel oil storage tank. Enhance the program to specify that all pulled and tested capsules, unless discarded before August 31, 2000, are 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 cold leg temperature or higher fluence, the impact of plant 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 meets the schedule requirements of 10 CFR 50 Appendix 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 maintains it in a condition which would permit its future use, including during the period of extended operation. Prior to the period of extended A.2.1.18 operation. A.2.1.18 Prior to the period of extended operation. Prior to the period of extended A.2.1.19 operation. Prior to the period of extended A.2.1.19 operation. Prior to the period of extended A.2.1.19 operation. A.2.1.19 Prior to the period of extended operation.

U.S. Nuclear Regulatory Commission SBK-L-17 I 55 I Enclosure 3/ Page 6 22. One-Time Inspection 23. Selective Leaching of Materials 24. Buried Piping And Tanks Inspection One-Time Inspection of 25. ASME Code Class 1 Small Bore-Piping External Surfaces 26. Monitoring Inspection of Internal Surfaces in Miscellaneous 27. Piping and Ducting Components 28. Lubricating Oil Analysis 29. Lubricating Oil Analysis Implement the One Time Inspection Program. A.2.1.20 Within ten years prior to the period of extended operation. Implement the Selective Leaching of Materials Program. The program will include a one-time inspection of selected Within five years prior to the components where selective leaching has not been A.2.1.21 period of extended operation. identified and periodic inspections of selected components where selective leaching has been identified. Implement the Buried Piping And Tanks Inspection Within ten years prior to the Program. A.2.1.22 period of extended operation Implement the One-Time Inspection of ASME Code Class Within ten years prior to the A.2.1.23 1 Small Bore-Piping Program. period of extended operation. Enhance the program to specifically address the scope of the program, relevant degradation mechanisms and effects Prior to the period of extended of interest, the refueling outage inspection frequency, the A.2.1.24 operation. training requirements for inspectors and the required periodic reviews to determine program effectiveness. Implement the Inspection of Internal Surfaces in A.2.1.25 Prior to the period of extended Miscellaneous Piping and Ducting Components Program. operation. Enhance the program to add required equipment, lube oil Prior to the period of extended analysis required, sampling frequency, and periodic oil A.2.1.26 changes. operation. Enhance the program to sample the oil for the Reactor A.2.1.26 Prior to the period of extended Coolant pump oil collection tanks. operation.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 7 30. Lubricating Oil Analysis ASME Section XI, 31. Subsection IWL Structures Monitoring 32. Program Structures Monitoring 33. Program Electrical Cables and Connections Not Subject to 34. 10 CFR 50.49 Environmental Qualification Requirements Electrical Cables and Connections Not Subject to 10 CFR 50.49 35. Environmental Qualification Requirements Used in Instrumentation Circuits Inaccessible Power Cables Not Subject to 10 CFR 50.49 36. Environmental Qualification Requirements 37. Metal Enclosed Bus Enhance the program to require the performance of a one-time ultrasonic thickness measurement of the lower portion A.2.1.26 Prior to the period of extended of the Reactor Coolant pump oil collection tanks prior to operation. the period of extended operation. Enhance procedure to include the definition of A.2.1.28 Prior to the period of extended "Responsible Engineer". operation. Enhance procedure to add the aging effects, additional Prior to the period of extended locations, inspection frequency and ultrasonic test A.2.1.31 operation. requirements. Enhance procedure to include inspection of opportunity Prior to the period of extended when planning excavation work that would expose A.2.1.31 operation. inaccessible concrete. Implement the Electrical Cables and Connections Not Prior to the period of extended Subject to 10 CFR 50.49 Environmental Qualification A.2.1.32 operation. Requirements program. Implement the Electrical Cables and Connections Not Prior to the period of extended Subject to 10 CFR 50.49 Environmental Qualification A.2.1.33 operation. Requirements Used in Instrumentation Circuits program. Implement the Inaccessible Power Cables Not Subject to Prior to the period of extended 10 CFR 50.49 Environmental Qualification Requirements A.2.1.34 operation. program. Implement the Metal Enclosed Bus program. A.2.1.35 Prior to the period of extended operation.

U.S. Nuclear Regulatory Commission SBK-L-l 71SS I Enclosure 3/ Page 8 38. Fuse Holders Electrical Cable Connections Not Subject to 10 CFR S0.49 39. Environmental Qualification Requirements 40. 34S KV SF6 Bus Metal Fatigue of Reactor 41. Coolant Pressure Boundary Metal Fatigue of Reactor 42. Coolant Pressure Boundary Pressure -Temperature Limits, including Low 43. Temperature Overpressure Protection Limits Implement the Fuse Holders program. A.2.1.36 Prior to the period of extended operation. Implement the Electrical Cable Connections Not Subject to Prior to the period of extended 10 CFR S0.49 Environmental Qualification Requirements A.2.1.37 operation. program. Implement the 34S KV SF6 Bus program. A.2.2.1 Prior to the period of extended operation. Enhance the program to include additional transients Prior to the period of extended beyond those defined in the Technical Specifications and A.2.3. l operation. UFSAR. Enhance the program to implement a software program, to Prior to the period of extended count transients to monitor cumulative usage on selected A.2.3.1 operation. components. The updated analyses will be Seabrook Station will submit updates to the P-T curves and submitted at the appropriate time L TOP limits to the NRC at the appropriate time to comply A.2.4.1.4 to comply with l 0 CFR SO with 10 CFR SO Appendix G. Appendix G, Fracture Toughness Requirements.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 9 44. Environmentally-Assisted Fatigue Analyses (TLAA) 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 At least two years prior to the Fen factors to valid CUFs determined from an existing A.2.4.2.3 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 Alkali-Silica Reaction 45. (ASR) Monitoring Program 46. Protective Coating Monitoring and Maintenance 47. Protective Coating Monitoring and Maintenance 48. Protective Coating Monitoring and Maintenance 49. Protective Coating Monitoring and Maintenance ASME Section XI, 50. Subsection IWE 51. Number Not Used 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 the change in through-thickness expansion since period of extended operation installation of the extensometers and compare it to change (initial study) and 10 years determined from extensometer readings. Consistency thereafter (follow-up study). between these results will provide additional corroboration of the methodology in MPR-4153. Enhance the program by designating and qualifying an A.2.1.38 Prior to the period of extended Inspector Coordinator and an Inspection Results Evaluator. operation. Enhance the program by including, "Instruments and Equipment needed for inspection may include, but not be limited to, flashlight, spotlights, marker pen, mirror, A.2.1.38 Prior to the period of extended measuring tape, magnifier, binoculars, camera with or operation. without wide angle lens, and self sealing polyethylene sample bags." Enhance the program to include a review of the previous A.2.1.38 Prior to the period of extended two monitoring reports. operation. Enhance the program to require that the inspection report is to be evaluated by the responsible evaluation personnel, A.2.1.38 Prior to the period of extended who is to prepare a summary of findings and operation. recommendations for future surveillance or repair. Baseline inspections were Perform UT of the accessible areas of the containment completed during OR16. Repeat liner plate in the vicinity of the moisture barrier for loss of A.2.1.27 containment liner UT thickness examinations at intervals of no material. Perform opportunistic UT of inaccessible areas. more than five (5) refueling outages.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 11 ASME Section XI, 52. Subsection IWL 53. Reactor Head Closure Studs Implement measures to maintain the exterior surface of the Contairunent Structure, from elevation -30 feet to +20 feet, A.2.1.28 Complete in a dewatered state. Replace the spare reactor head closure stud(s) Prior to the period of extended manufactured from the bar that has a yield strength> 150 A.2.1.3 ksi with ones that do not exceed 150 ksi. operation.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 12 Steam Generator Tube 54. Integrity 55. Number Not Used Closed-Cycle Cooling Water 56. System 57. Closed-Cycle Cooling Water System 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 weld inspections for the remaining life of the steam A.2.1.10 Complete 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. Revise the station program documents to reflect the EPRI Prior to the period of extended Guideline operating ranges and Action Level values for A.2.1.12 hydrazine and sulfates. operation. Revise the station program documents to reflect the EPRI Prior to the period of extended Guideline operating ranges and Action Level values for A.2.1.12 operation. Diesel Generator Cooling Water Jacket pH.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 13 58. Fuel Oil Chemistry Nickel Alloy Nozzles and 59. Penetrations Buried Piping and Tanks 60. Inspection Compressed Air Monitoring 61. Program 62. Water Chemistry 63. Flow Induced Erosion 64. Buried Piping and Tanks Inspection Update Technical Requirement Program 5 .1, (Diesel Fuel Oil Testing Program) ASTM standards to ASTM D2709-A.2.1.18 Prior to the period of extended 96 and ASTM D4057-95 required by the GALL XI.M30 operation. Rev 1 The Nickel Alloy Aging Nozzles and Penetrations program Prior to the period of extended will implement applicable Bulletins, Generic Letters, and A.2.2.3 operation. staff accepted industry guidelines. Implement the design change replacing the buried Prior to the period of extended Auxiliary Boiler supply piping with a pipe-within-pipe A.2.1.22 operation. configuration with leak detection capability. Replace the flexible hoses associated with the Diesel Within ten years prior to the Generator air compressors on a frequency of every 10 A.2.1.14 period of extended operation. years. Enhance the program to include a statement that sampling Prior to the period of extended frequencies are increased when chemistry action levels are A.2.1.2 exceeded. operation. 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 A.2.1.2 Prior to the period of extended 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 A.2.1.22 Within ten years prior to the steel pipe within the scope of this program. If the initial period of extended operation. 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 65. Flux Thimble Tube Alkali-Silica Reaction 66. (ASR) Monitoring Program 67. Structures Monitoring Program Implement measures to ensure that the movable incore Prior to the period of extended detectors are not returned to service during the period of extended operation. NIA operation. -In Progress 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 thickness expansion of all monitored points by A.2.1.31.A of extended operation and every 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 degradation such as loss of material. The removed core A.2.1.31 Complete 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 68. Program Open-Cycle Cooling Water 69. System 70. Closed-Cycle Cooling Water System Alkali-Silica Reaction (ASR) Monitoring Program I 71. Building Deformation Monitoring Program 72. Flow-Accelerated Corrosion Inspection of Internal Surfaces in Miscellaneous 73. Piping and Ducting Components Perform sampling at the leak off collection points for A.2.1.31 Complete chlorides, sulfates, pH and iron once every three months. Replace the Diesel Generator Heat Exchanger Plastisol PVC lined Service Water piping with piping fabricated A.2.1.11 Complete from AL6XN material. Inspect the piping downstream of CC-V-444 and CC-V-446 to determine whether the loss of material due to Within ten years prior to the cavitation induced erosion has been eliminated or whether A.2.1.12 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 acceptance criteria used are appropriate to manage the effects of ASR. A.2.1.3 lA Prior to the period of extended NextEra !implement the Alkali-Silica Reaction (ASR) A.2.l.31B operation. 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 A.2.1.8 Prior to the period of extended thinning caused by mechanisms other than FAC. operation. Enhance the program to include performance of focused examinations to provide a representative sample of20%, or a maximum of25, of each identified material, A.2.1.25 Prior to the period of extended environment, and aging effect combinations during each operation. 10 year period in the period of extended operation.

U.S. Nuclear Regulatory Commission SBK-L-17155 /Enclosure 3/Page 16 74. Fire Water System 75. Fire Water System 76. Fire Water System 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 and installed in the proper orientation (e.g., upright, 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 pipe or sprinklers is detected during pipe inspections, the 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).

main drain tests

deluge valve trip tests

fire water storage tank exterior surface inspections Prior to the period of extended A.2.1.16 operation. Prior to the period of extended A.2.1.16 operation. A.2.1.16 Prior to the period of extended operation.

U.S. Nuclear Regulatory Commission SBK-L-17 I 55 I Enclosure 3/ Page 17 77. Fire Water System 78. External Surfaces Monitoring Open-Cycle Cooling Water 79. System 80. Fire Water System 81. Fuel Oil Chemistry 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 A.2.1.16 Prior to the period of extended 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 are insulated and a sample of indoor insulated components A.2.1.24 Prior to the period of extended 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 Within 10 years prior to the internal coatings/linings for loss of coating integrity. A.2.1.11 period of extended operation. Enhance the program to include visual inspection of Within 10 years prior to the internal coatings/linings for loss of coating integrity. A.2.1.16 period of extended operation. Enhance the program to include visual inspection of Within 10 years prior to the internal coatings/linings for loss of coating integrity. A.2.1.18 period of extended operation.

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 18 Inspection of Internal 82. Surfaces in Miscellaneous Piping and Ducting Components 83. Alkali-Silica Reaction Monitoring ASME Section XI, 84. Subsection IWL 85. Fire Water System 86. Fire Water System 87. Fire Water System Enhance the program to include visual inspection of internal coatings/linings for loss of coating integrity. A.2.1.25 Within 10 years prior to the period of extended operation. 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-of-plane direction. A.2.1.31A Complete 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 Prior to the period of extended structures within the scope of ASME Section XI, A.2.1.28 operation. Subsection IWL Program. Enhance the program to perform additional tests and inspections on the Fire Water Storage Tanks as specified in Section 9.2.7 ofNFPA 25 (2011 Edition) in the event that A.2.1.16 Prior to the period of extended 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." Enhance the program to include disassembly, inspection, A.2.1.16 Prior to the period of extended and cleaning of the mainline strainers every 5 years. operation. Increase the frequency of the Open Head Spray Nozzle Air Flow Test from every 3 years to every refueling outage to

A.2.1.16 Prior to the period of extended 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 88. Fire Water System Inspection of Internal Surfaces in Miscellaneous 89. Piping and Ducting Components PWR Vessel Internals 90. 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 Within five years prior to the piping are configured to completely drain the piping, and A.2.1.16 c) normally-dry piping that could have been wetted by period of extended operation. 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 RCP Motor Refurbishment Specification for the internal painting of the motor upper bearing coolers and motor air A.2.1.25 Prior to the period of extended coolers. All four RCP motors will be refurbished and operation. 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 227-A (Pressurized Water Reactor Internals Inspection and A.2.1.7 Evaluation Guidelines) and NEI 03-08 (Guideline for the operation Management of Materials Issues).

U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 20 Building Deformation 91 Monitoring 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 additional parameters to be monitored based on the results A.2.l.31B March 15, 2020 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. to SBK-L-17155 NextEra Energy Seabrook, Application for Withholding Proprietary Information from Public Disclosure and Affidavit U.S. Nuclear Regulatory Commission SBK-L-17155 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. Nuclear Regulatory Commission 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. Subscribed and sworn to before me this 12 O day of October, 2017. Notary Public My commission expires 3/rt;/1,.,7__ Regional Vice President -Northern Region NextEra Energy Seabrook, LLC 626 Lafayette Road Seabrook, New Hampshire 03874

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+{{#Wiki_filter:Enclosure 1 to this Letter Contains Proprietary Information Withhold Enclosure 1 from Public Disclosure in Accordance with 10 CFR 2.390 October 03, 2017 10 CFR 54 Docket No. 50-443 SBK-L-17155 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station NFXTera SEABROOK 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:==
+. NextEra Energy Seabrook LLC, letter SBK-L-10077, "Seabrook Station Application for Renewed Operating License," May 25, 2010 (Accession Number ML 101590099). 2. NRC, "Request for Additional Information for the Review of the Seabrook Station License Renewal Application (CAC NO. ME4028)," March 29, 2017 (Accession Number ML 17088A614). In Reference 1, NextEra Energy Seabrook, LLC (NextEra Energy Seabrook) submitted an application 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 application related to Alkali-Silica Reaction (ASR) and Building Deformation Monitoring Programs. Enclosure 1 provides NextEra Energy Seabrook's response to the NRC's Request for Additional Information (RAI) concerning the Alkali-Silica Reaction and Building 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-17155/ Page 2 Enclosure 2 provides the revised License Renewal Application, Section 3.5, as referenced in the response to RAI 3.5-A1-1: AMR within Enclosure 1. 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 Commission and addressing the considerations 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 version of this letter and revised Alkali-Silica Reaction Monitoring Program Aging Management Plan A.2.1.31.A will be submitted under separate cover by November 3, 2017. This letter contains two revised Commitments (45 and 66). Enclosure 3 provides the revised LRA Appendix A -Updated Final Safety Analysis Report Supplement Table A.3, License Renewal Commitment List. If there are any questions or additional information is needed, please contact Mr. Edward J. Carley, Engineering Supervisor -License Renewal, at (603) 773-7957. If you have any questions regarding 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 , 2017. Sincerely, NextEra Energy Seabrook, LLC hem Region U.S. Nuclear Regulatory Commission SBK-L-17155/ Page 3
+==Enclosures:==
+Enclosure 1 -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 (Proprietary) Enclosure 2 -Seabrook Station License Renewal Application, Section 3.5 Enclosure 3 -LRA Appendix A -Final Safety Report Supplement Table A.3, License Renewal Commitment List Updated to Reflect Changes to Date Enclosure 4 -NextEra Energy Seabrook, Application for Withholding Proprietary Information from Public Disclosure and Affidavit cc: D. H. Dorman J.C. Poole P. C. Cataldo L. M. James Mr. Perry Plummer NRC Region I Administrator NRC Project Manager NRC Senior Resident Inspector NRC Project Manager, License Renewal 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    to SBK-L-17155 Seabrook Station License Renewal Application, Section 3.5 U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 2/ Page 2 Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components Item Component Aging Management Number Aging Effect I Mechanism Further Evaluation Program Recommended PWR 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 walls, dome, basemat, inaccessible concrete areas examination of representative samples of environment is aggressive ring girder, buttresses. due to aggressive chemical below-grade concrete and periodic monitoring containment (as attack, and corrosion of of groundwater if environment is non-applicable) embedded steel aggressive. A plant-specific program is to be evaluated if environment is aggressive. Discussion :* Seabrook manages accessible and inaccessible concrete components due to corrosion of embedded steel with the ASME Section XI, Subsection IWL Program, and B.2.1.28. Aggressive chemical attack is an applicable aging effect requiring management for Seabrook. Further evaluation is provided in LRA Subsection 3.5.2.2.1.1. The Structures Monitoring Program. B.2.1.31, will perform concrete testing and rebar inspection to determine the effects of the ag.gressive groundwater on the concrete. The concrete 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 . IFi!I ' ,,:11 :1:111: I' ' Item ,, ,Agipg Managerre!lt Further Evaluation Component Aging Effect I Mechanism !: 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 increased stress levels from watering system is relied upon for control of scope of the applicant's settlement settlement, then the licensee is to ensure structures monitoring proper functioning of the de-watering system program or a de-watering through the period of extended operation. system is relied upon 3.5.1-3 Concrete elements: Reduction in foundation Structures Monitoring Program. If a de-Yes, if not within the foundation, strength, cracking, differential watering system is relied upon to control scope of the applicant's subfoundation settlement due to erosion of erosion of cement from porous concrete structures monitoring porous concrete subfoundations, then the licensee is to ensure program or a de-watering subfoundation proper functioning of the de-watering system system is relied upon through the period of extended operation Discussion Seabrook does not rely on a dewatering system for control of settlement. Cracking and distortion due to increased stress levels from settlement is not an aging effect requiring 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. Reduction in foundation strength, cracking, and differential settlement due to erosion of porous concrete subfoundations is not an aging effect requiring management for the Seabrook Containment Structure. Further evaluation is provided in LRA Subsection 3.5.2.2.1.2.
+SBK-L-17155 I Enclosure 2/ Page 4 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components t*; ,.f,1, :1: 'I' :I!* 1* "' Item Component Aging Effect I Mechanism Aging '!!I' Further Evaluation Number Program ,ii* *i'l 1+ . ' , 3.5. 1-4 Concrete elements: Reduction of strength and Plant-specific Yes, plant-specific if dome, wall, basemat, modulus due to elevated temperature limits are ring girder, buttresses, temperature exceeded containment, concrete fill-in annulus (as applicable) 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 liner, liner anchors, general, pitting, and crevice significant for inaccessible integral attachments corrosion areas 3.5.1-7 Prestressed Loss of prestress due to TLAA evaluated in accordance with 10 CFR Yes, TLAA containment tendons relaxation, shrinkage, creep, 54.21 (c) and elevated temperature l*l'.1*1 !Ii Discussion ' This item is not applicable to Seabrook. No containment components exceed the specified temperature thresholds. Further evaluation is provided in LRA Subsection 3.5.2.2.1.3. Consistent with NUREG-1801. 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. This item is not applicable to Seabrook. 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 '''" 1:1 ,, .,, I ' t Item l*I ,,, Aging Management Further Evaluation Number '*1Component Aging Effect I Mechanism Program Recommended 1;1 I '*I' I.I Iii 3.5.1-8 BWRonly. 3.5.1-9 Steel, stainless steel Cumulative fatigue damage TLAA evaluated in accordance with 1 O CFR Yes, TLAA elements, dissimilar (CLB fatigue analysis exists) 54.21 (c) metal welds: penetration sleeves, penetration bellows; suppression pool shell, unbraced down comers 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 penetration sleeves, corrosion cracking additional appropriate examinations I to be evaluated penetration bellows, evaluations for bellows assemblies and dissimilar metal welds dissimilar metal welds 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 elements, dissimilar loading supplemented to detect fine cracks to be evaluated metal welds: penetration sleeves, penetration bellows; suppression pool shell, unbraced downcomers 3.5.1-13 BWRonly. , H . ,,, ,+,:i:ii'JI; Discussion .l*I Consistent with NUREG-1801 for Seabrook containment penetrations that experience significant cyclic loading. Further evaluation is provided in LRA Subsection 3.5.2.2.1.6. Cracking due to stress corrosion cracking is not an aging effect requiring management for these stainless steel components. Further evaluation is provided in LRA Subsection 3.5.2.2.1.7. This item is not applicable to Seabrook. Cracking due to cyclic loading is not an aging effect requiring management for the Seabrook penetration elements. Further evaluation is provided in LRA Subsection 3.5.2.2.1.8.
+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 ., f. I '1 .,. Item *I Aging Management Further Evaluation Number Component Aging Effect I P.rogram Recommended ' 3.5.1-14 Concrete elements: Loss of material (scaling, ISi (IWL) Evaluation is needed for plants that Yes, for inaccessible dome, wall, basemat, cracking, and spalling) due to are located in moderate to severe weathering areas of plants located in ring girder, buttresses, freeze -thaw conditions (weathering index >100 day -moderate to severe containment (as inch/yr) (NUREG-1557) weathering conditions applicable) 'I Discussion I , 1J1;11!i1'1ili Loss of material due to freeze-thaw effects is not an aging effect requiring management for Seabrook. 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 :1; ii" ' I '1111 ,., :i ' '"!"'"'II II ,,, Item Component Aging Effect I Mechanism Aging Management Further Evaluation Number Program Recommended 3.5.1-15 Concrete elements: Increase in porosity ISi (IWL) for accessible areas. None for Yes, if concrete was not walls, dome, basemat, permeability due to leaching inaccessible areas if concrete was constructed constructed as stated for ring girder, buttresses, of calcium hydroxide; in accordance with the recommendations of inaccessible areas. containment, concrete cracking due to expansion ACI 201.2R fill-in annulus (as and reaction with aggregate applicable) ,,,,., .,,., . 'i! ,:1:111111*1:1 Discussion +tie AMR Fes<ilts eeAel<iele ttiat eltie le eiq:iaAsieA aAel FeaetieA wi!R a&sect;&sect;Fe&sect;ale is Rel aA a&sect;iA&sect; Ffl66RaAiSFfl F6f:1tliFiA&sect; FAaAa&sect;eFAeAI feF !Re eeA!aiAFA6AI S!Ftie!tire at Seal:JFeelc Concrete was constructed equivalent to recommendations in ACI 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 1:1'1111 11'11:111', 11111:1! ll'll11111llt11:1il:i!l'lilil:I !li:I , ''JI :1:1,11,:j:: Fl Fl ,,.,,. 1:1 *' ii! il'J.111 Item Component Aging Effect I Mechanism Aging Management, ,
+* Further Evaluation ",. Number Program Recommended 3.5.1-16 Seals, gaskets, and Loss of sealing and leakage ISi (IWE) and 10 CFR Part 50, Appendix J No moisture barriers through containment due to deterioration of joint seals, gaskets, and moisture barriers (caulking, flashing, and other sealants) :11*::11111:1 ,,:J'li1'' i'il:''1:r1,111r111,1, .1: y1.111, Discussion 1*; 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 evaluation is provided in LRA Subsection 3.5.2.2. 1. 10. Consistent with NUREG-1801. Seabrook manages loss of sealing with the ASME 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 therefore Seabrook manages loss of sealing due to ASR with the Building Deformation Monitoring Program, B.2.1.31B.
+SBK-L-17155 I Enclosure 2/ Page 9 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components :" !;, I :j:i:JJ '.!: :1:1 :i: Item Component Aging Effect I Mechanism Agi.ng Management Further Evaluation Number Program Recommended 3.5.1-17 Personnel airlock, Loss of leak tightness in 1 O CFR Part 50, Appendix J and plant No equipment hatch and closed position due to Technical Specifications CRD hatch locks, mechanical wear of locks, hinges, and closure hinges, and closure mechanisms mechanisms 3.5.1-18 Steel penetration Loss of material due to ISi (JWE) and 10 CFR Part 50 Appendix J No sleeves and dissimilar general, pitting, and crevice metal welds; personnel corrosion airlock, equipment hatch, and CRD hatch 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 containment: tendons corrosion and anchorage components Safety Related and Other Structures; and Component Supports I *1;1 :Li. I 1:1 1'.l:.l.11:1; Discussion Consistent with NUREG-1801. The 10 CFR 50 Appendix J Program, B.2.1.30, is used to manage loss of leak tightness. Consistent with NUREG-1801. The ASME Section XI, Subsection IWE, B.2.1.27 manages loss of material due to corrosion, 1 O CFR 50 Appendix J Program, B.2.1.30, manages loss of leak tightness. Not Applicable. Seabrook Station does not have prestressed tendons.
+SBK-L-17155 I Enclosure 2/ Page 10 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components ,,,,, .. II ..* ,,:, !! w111 1,n!' 11: , 'il'i m111w111:11:1:111:1i1 i'1111i:111'11 n1 1111w11w1 Item 1;, Component Aging Effect I Mechanism Aging Management Further Evaluation *,, Number Program Recommended 3.5.1-23 All Groups except Cracking, loss of bond, and Structures Monitoring Program Yes, if not within the Group 6: interior and loss of material (spalling, scope of the applicant's above grade exterior scaling) due to corrosion of Structures Monitoring concrete embedded steel Program 3.5.1-24 All Groups except Increase in porosity and Structures Monitoring Program Yes, if not within the Group 6: interior and permeability, cracking, loss of scope of the applicant's above grade exterior material (spalling, scaling) Structures Monitoring concrete due to aggressive chemical Program attack 3.5.1-25 All Groups except Loss of material due to Structures Monitoring Program If protective Yes, if not within the Group 6: steel corrosion coatings are relied upon to manage the effects scope of the applicant's components: all of aging, the structures monitoring program is Structures Monitoring structural steel to include provisions to address protective Program coating monitoring and maintenance i:!!l:i'';1:l'!*1,i1:J11:,11 ,, '11' .11111: 'IJ' ii'iii!''' :11 Discussion , Consistent with NUREG-1801. 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. The Seabrook AMR results conclude that the groundwater is aggressive and chemical attack is 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. Consistent with NUREG-1801. Seabrook manages 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' 11:111 l'I li:h i!iii*I* 1'1.l:'' 1111 j:I :f'I "", lil'.lh1 j:I Item Component Aging Effect I Mechanism Aging Management Further Evaluation Number Program Recommended 3.5.1-26 All Groups except Loss of material (spalling, Structures Monitoring Program Evaluation is Yes, if not within the Group 6: accessible and scaling) and cracking due to needed for plants that are located in moderate scope of the applicant's inaccessible concrete: freeze-thaw to severe weathering conditions (weathering Structures Monitoring foundation index >100 day-inch/yr) (NUREG-1557) Program or for inaccessible areas of plants located in moderate to severe weathering conditions *ijlj 1;1!1111111: ;1.111; :1 *M1,: Discussion Consistent with NUREG-1801. Seabrook manages Loss of material (spalling, scaling) and cracking due to freeze-thaw with the Structures Monitoring Program, B.2.1.31. Further evaluation is provided in LRA Subsection 3.5.2.2.2.1, Item 4.
+SBK-L-17155 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 Evaluation Number Component Aging Effect I Mechanism ' 1 , 1*1 Recommended ' 3.5.1-27 All Groups except Cracking due to expansion Structures Monitoring Program. None for Yes, if not within the Group 6: accessible and due to reaction with inaccessible areas if concrete was constructed scope of the applicant's inaccessible interior I aggregates in accordance with the recommendations in Structures Monitoring exterior concrete AC! 201.2R-77 Program or concrete was not constructed as stated for inaccessible areas ,, Discussiop +Ris iteFA is Aet a1313lieasle te Seasreelc +Re Seasreel' .O.MR Fes\ollts eeAel\o!Ele !Rat FeaetieA wi!R a&sect;&sect;Fe&sect;ates is Ae! si&sect;AifieaA! aAEl !Re eeAoFe!e was oeAstrneteEl oeAsis!eA! wi!R I The recommendations of AC! 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). NeAe!Reless, all Seasreel' Stf1:16l1:1Fal 69FAJ39AeA!S a1313lioasle te !Ris iteFA will se FAeAiteFeEl sy !Re S!F1:10!1:1Fes MeAiteFiA&sect; Pre&sect;FaFA, Cracking due to expansion and reaction with aggregates is monitored by the Structures Monitoring Program, B.2.1.31, the Alkali-Silica Reaction (ASR) Monitoring 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.: ,, !111111-i'l Iii' '*'"* .,,.1H. ,/11*' Item Component ., Aging Effect I Mechanism Aging Management I*'* Further Evaluation l'I 11'1 Number Program Recommended 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 increased stress levels from watering system is relied upon for control of scope of the applicant's settlement settlement, then the licensee is to ensure Structures Monitoring proper functioning of the de-watering system Program or a de-watering through the period of extended operation system is relied upon 3.5.1-29 Groups 1-3, 5-9: Reduction in foundation Structures Monitoring Program If a de-Yes, if not within the foundation strength, cracking, differential watering system is relied upon for control of scope of the applicant's 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 subfoundation through the period of extended operation system is relied upon Discussion Monitoring Program, B.2.1.318. Further evaluation is provided in LRA Subsection 3.5.2.2.2.1, Item 5. This item is not applicable to Seabrook. The Seabrook AMR results 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 Subsection 3.5.2.2.2.1, Item 6. This item is not applicable to Seabrook. The Seabrook AMR results 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 Subsection 3.5.2.2.2.1, Item 7.
+SBK-L-17155 I Enclosure 2/ Page 14 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components 1: ,, i'I Item Component Aging Effect I Mechanism Aging Management Further Evaluation Number Recommended 1:1 Iii 11111:1 1'1 ii, l'I ,, 3.5.1-30 Group 4: Radial beam Lock-up due to wear ISi (IWF) or Structures Monitoring Program Yes, if not within the seats in BWR drywell; scope of ISi of Structures RPV support shoes for Monitoring Program PWR with nozzle support; Steam generator supports 3.5.1-31 Groups 1-3, 5, 7-9: Increase in porosity and Structures Monitoring Program Examination of Yes, plant-specific if below grade concrete permeability, cracking, loss of representative samples of below grade environment is aggressive components, such as material (spalling, scaling) I concrete, and periodic monitoring of 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 loss of material (spalling, evaluated if the environment is aggressive scaling)/ corrosion of embedded steel '' Discussion ' 11*1 Lubrite materials for nuclear applications are designed to resist deformation, have a low coefficient of friction, resist 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. The Seabrook AMR results conclude that the groundwater is aggressive. The Structures Monitoring Program, B.2.1.31, will manage degradation of 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-17155/Enclosure2/Page15 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components 1; Item Component Aging Effect I Mechanism Aging Management Further Evaluation Number ' Program Recommended 111 111. :I I !I!!' :1: :Ii I :1:* :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 exterior above and permeability, loss of strength areas. None for inaccessible areas if concrete constructed as stated for below grade reinforced due to leaching of calcium was constructed in accordance with the inaccessible areas concrete foundations hydroxide recommendations in ACI 201.2R-77 3.5.1-33 Group 1-5: concrete Reduction in strength and Plant-specific Yes, plant specific if modulus due to elevated temperature limits are temperature exceeded ' Discussion :111:1 Loss of material due to leaching of calcium hydroxide is considered to be an aging effect requiring management for Seabrook. There have been indications of leaching in below grade concrete in Seabrook structures. Further evaluation is provided in LRA Subsection 3.5.2.2.2.2, Item 5. This item is not applicable to Seabrook concrete components do not exceed the temperature limits specified in NUREG-1800. Further evaluation is provided in LRA Subsection 3.5.2.2.2.3.
+SBK-L-17155 I Enclosure 2/ Page 16 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components ,,, *I Item Component Aging Effect I Mechanism Aging Management Further Evaluation 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 of material due to corrosion Associated with Nuclear Power Plants and for environment is aggressive of embedded steel, increase inaccessible concrete, examination of in porosity and permeability, representative samples of below grade cracking, loss of material due concrete, and periodic monitoring of to aggressive chemical attack groundwater, if environment is non-aggressive. Plant-specific if environment is aggressive 3.5.1-35 Group 6: exterior above Loss of material (spalling, Inspection of Water Control Structures Yes, for inaccessible and below grade scaling) and cracking due to Associated with Nuclear Power Plants is areas of plants located in concrete foundation freeze-thaw needed for plants that are located in moderate moderate to severe to severe weathering conditions (weathering weathering conditions index >100 day-inch/yr) (NUEG 1557) 'l'l.11ll1:Ej: Discussion Concrete in inaccessible areas is evaluated for increase in Porosity and Permeability, and Loss of Material (Spalling, Scaling), Chemical Attack; Cracking, 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. Consistent with NUREG-1801. Seabrook manages Loss of material (spalling, scaling) and cracking due to freeze-thaw with the Structures Monitoring Program, B.2.1.31. Further evaluation is provided in LRA Subsection 3.5.2.2.2.4, Item 2.
+SBK-L-17155 I Enclosure 2/ Page 17 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components 1:1 ,,, ' I: Item Aging Management, Further Evaluation Number Component Aging Effect I Mechanism 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 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 recommendations in ACI 201.2R77 :1; Discussion GeAsisleAI wi!R The concrete was constructed consistent with the recommendations of ACI 201.2R. Seabrook Station Operating Experience has indicated that Alkali-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 for 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,' ,,,,,,,,,: Item Component Aging Effect I Mechanism Aging Management Further Evaluation 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 and below grade permeability, Joss of strength Control Structures Associated with Nuclear constructed as stated for 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 recommendations in ACI 201.2R77 3.5.1-38 Group 7, 8: Tank liners Cracking due to stress Plant-specific Yes, plant-specific corrosion cracking; Joss of material due to pitting and crevice corrosion 3.5.1-39 Support members; Loss of material due to Structures Monitoring Program Yes, if not within the welds; bolted general and pitting corrosion scope of the applicant's connections; support Structures Monitoring anchorage to building Program structure ' 'l",;I Discussion ,"' Consistent with NUREG-1801. The Structures Monitoring 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. There are no components at Seabrook that are subject to this aging effect. Further evaluation is provided in LRA Subsection 3.5.2.2.2.5. Consistent with NUREG-1801. The Structures Monitoring Program, B.2.1.31, will 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 Component ,, Aging Effect I Aging Management Further Evaluation Number
+* Prog'ram' ''i'' ,, Recommended "' 3.5. 1-40 Building concrete at Reduction in concrete anchor Structures Monitoring Program Yes, if not within the locations of expansion capacity due to local scope of the applicant's and grouted anchors; concrete degradation I Structures Monitoring grout pads for support service-induced cracking or Program base plates other concrete aging mechanisms 3.5.1-41 Vibration isolation Reduction or loss of isolation Structures Monitoring Program Yes, if not within the elements function I radiation scope of the applicant's hardening, temperature, Structures Monitoring humidity, sustained vibratory Program loading 3.5. 1-42 Groups 81. 1, 81 .2, and Cumulative fatigue damage TLAA evaluated in accordance with 10 CFR Yes, TLAA 81 .3: support members: (CLB fatigue analysis exists) 54.21(c) anchor bolts, welds '" ,,,,, ,,.,, '!'Discussion l'I 1*1' *" Consistent with NU REG-1801. The Structures Monitoring Program, B.2.1.31, and 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. This item is not applicable to Seabrook. Seabrook does not have any supports with vibration isolation elements which require AMR Further evaluation is provided in LRA Subsection 3.5.2.2.2.6, Item 3. This item is not applicable to Seabrook. 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 Aging Management Evaluations for Structures and Structural Components I 11:+1. I] IJ Item Component Aging Effeet I Mechanism Aging Management Further Evaluation Number Program Recommended 3.5.1-43 Group 1-3, 5, 6: all Cracking due to restraint Masonry Wall Program No masonry block walls shrinkage, creep, and aggressive environment 3.5.1-44 Group 6 elastomer Loss of sealing due to Structures Monitoring Program No seals, gaskets, and deterioration of seals, moisture barriers gaskets, and moisture barriers (caulking, flashing, and other sealants) 3.5.1-45 Group 6: exterior above Loss of material due to Inspection of Water Control Structures No and below ground abrasion, cavitation Associated with Nuclear Power Plants concrete foundation; interior slab 3.5.1-46 Group 5: fuel pool liners Cracking due to stress Water Chemistry and Monitoring of spent fuel No corrosion cracking; loss of pool water level and level of fluid in the leak material due to pitting and chase channel crevice corrosion Discussion Seabrook manages cracking of masonry block walls and 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. Consistent with NUREG-1801. The Structures Monitoring Program, B.2.1.31., and Building Deformation Monitoring Program, B.2.1.318. Consistent with NU REG-1801. The Structures Monitoring Program, B.2.1.31, will confirm the absence of aging effects requiring management. The spent fuel pool is normally maintained less than 140&deg;F, therefore Stress Corrosion Cracking is not an aging effect that requires 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 ll1 :'i: 11!: 11' l:l'ili! "It* ' 1*:: 1*1:ll*l']::*''!'I Item Component Aging Effect I Mechanism Aging* Management Further Evaluation Number Program Recommended 3.5.1-47 Group 6: all metal Loss of material due to Inspection of Water Control Structures No structural members general (steel only), pitting, Associated with Nuclear Power Plants. If and crevice corrosion protective coatings are relied upon to manage aging, protective coating monitoring and maintenance provisions should be included 3.5. 1-48 Group 6: earthen water Loss of material, loss of form Inspection of Water Control Structures No control structures -due to erosion, settlement, Associated with Nuclear Power Plants dams, embankments, sedimentation, frost action, reservoirs, channels, waves, currents, surface canals, and ponds runoff, seepage 3.5.1-49 BWRonly. 3.5.1-50 Groups B2 and 84: Loss of material due to pitting Structures Monitoring Program No galvanized steel, and crevice corrosion aluminum, stainless steel support members; welds; bolted connections; support anchorage to building structure 3.5.1-51 Group B1.1: high Cracking due to stress Bolting Integrity No strength low-alloy bolts corrosion cracking; loss of material due to general corrosion :I: ''''l:i: !*I'' .,:1:1> '']: 1F* Discussion Consistent with NU REG-1801. The Structures Monitoring Program, B.2. 1.31, will confirm the absence of aging effects requiring management. Consistent with NUREG-1801. The Structures Monitoring Program, B.2. 1.31 will confirm the absence of aging effects requiring management. Consistent with NUREG-1801. The Structures Monitoring Program, B.2.1.31, will confirm the absence of aging effects requiring management. There are no high strength bolts at Seabrook that are subject to this aging effect.
+SBK-L-17155 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 Component Aging Effect I Mechanism Aging Management Further Evaluation Number Fl .,. Ii!, 11111 Pl 'il:I Recommended . *l:i 'Fl
+* 1*1 'i:r* '"' 'i"H"1111r1*1 . 3.5.1-52 Groups 82 and 84: Loss of mechanical function Structures Monitoring Program No sliding support bearings due to corrosion, distortion, and sliding support dirt, overload, fatigue due to surfaces vibratory and cyclic thermal loads 3.5.1-53 Groups 81.1, 81 .2, and Loss of material due to ISl(IWF) No 81 .3: support members: general and pitting corrosion welds; bolted connections; support anchorage to building structure 3.5.1-54 Group 81.1, 81 .2, and Loss of mechanical function ISl(IWF) No 81 .3: Constant and due to corrosion, distortion, variable load spring dirt, overload fatigue due to hangers; guides; stops vibratory and cyclic thermal loads Discussion l'I Jti 1:1 There are no sliding support bearings of surfaces at Seabrook that are subject to this aging effect. Consistent with NUREG-1801. Seabrook manages the aging effect with the ASME Section XI, Subsection IWF Program, 8.2.1.29. Consistent with NUREG-1801. Seabrook manages the aging effect with the ASME Section XI, Subsection IWF Program, 8.2.1.29.
+SBK-L-17155 I Enclosure 2/ Page 23 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components ! .. , Im i 1:n' ,_ l!l 1f!i. I , ::1, ,,i1::: 1:11111 .. I,. .. 111 II )ll1!1 Item Aging Management ,J, ' * "Further Evaluation *i;* Number Component Aging Effect I Mechanism Program 1.1:1' Recommended 3.5.1-55 Steel, galvanized steel, Loss of material due to boric Boric Acid Corrosion No and aluminum support acid corrosion members; welds; bolted connections; support anchorage to building structure 3.5.1-56 Groups B1.1, B1 .2, and Loss of material function due ISl(IWF) No B1 .3: Sliding surfaces to corrosion, distortion, dirt, overload, fatigue due to vibratory and cyclic thermal loads 3.5.1-57 Groups B1.1, B1 .2, and Reduction or loss of isolation ISl(IWF) No B1 .3: Vibration isolation function/radiation hardening, elements temperature, humidity, sustained vibratory loading t1*I IF ii ' ' Discussion Consistent with NUREG-1801. Seabrook manages the aging effect of loss of material due to boric acid corrosion in steel, galvanized steel, and aluminum for all types of support members (including safety and non-safety), welds, bolted connections and support anchorage to building structure with the Boric Acid Corrosion Program, B.2.1.4. There are no sliding support bearings of surfaces at Seabrook that are subject to this aging effect. This item is not applicable to Seabrook. The Seabrook AMR results do not include any supports with vibration 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 Item Number 3.5.1-58 3.5.1-59 3.5.1-60 Component Galvanized steel and aluminum support members; welds; bolted connections; support anchorage to building structure exposed to air -indoor uncontrolled Stainless steel support members; welds; bolted connections; support anchorage to building structure Group 6 elastomer seals, gaskets, and moisture barriers Aging Effect I Mechanism Nooe Nooe l\11:.i ,*I ;l:I ,. 'I' 'i:i Aging Management Program Reduction in structural Structures Monitoring Program capacity directly/ indirectly due to the expansion of concrete Nooe I Nooe Reduction in structural Structures Monitoring Program capacity directly/ indirectly due to the expansion of concrete Loss of bound, I Structures Monitoring Program misalignment, distortion, and/or reduction in structural capacity due to expansion of concrete 1iH *i: I Further Evaluation Recommended 11 N/\ Re agiAg effect maAagemeAt or agiAg maAagemeAt 13rogram Yes, if not within the scope of the applicant's Structures Monitoring Program W\ no agiAg effect maAagemeAt er agiAg maAagemeAt 13rogram Yes, if not within the scope of the applicant's Structures Monitoring Program Yes, if not within the scope of the applicant's Structures Monitoring Program 'I' Discussion Consistent with NUREG-1801. The Structures Monitoring Program, B.2.1.31, and Building Deformation Monitoring Program, B.2.1.31B will manage degradation for the aging effects. GoAsistent with NURE;G Plant Specific. The Structures Monitoring Program, B.2.1.31, and Building Deformation Monitoring Program, B.2.1.31B will manage degradation for the aging effects. Plant Specific The Structures Monitoring Program, B.2.1.31, and Building Deformation Monitoring Program, B.2.1.31B will manage degradation for the aging effects.
+SBK-L-17155 I Enclosure 2/ Page 25 U.S. Nuclear Regulatory Commission Table 3.5.1 Summary Of Aging Management Evaluations for Structures and Structural Components ''I 1:I, I 1:; '*lli1:1:1:1:1:11 ,11li Ii ,1'' t1111M1 l,1:11l!:i1 1il1/'jl11i'1illl' l!j, :1:i:1:1'1::1 Item Component Aging Effect I Mechanism Aging Management *
+* 1* ** ' ' Further.Evaluation' Number Program Recommended 3.5.1-61 Steel, galvanized steel, Reduction/loss in Structures Monitoring Program Yes, if not within the and aluminum support structural capacity due to scope of the members; welds; expansion of concrete applicant's Structures bolted connections; Monitoring Program support anchorage to building structure li1i:lily1n I'! .. 'l'I' , Discussion Plant Specific The Structures Monitoring Program, B.2.1.31, and Building Deformation Monitoring Program, B.2.1.318 will manage degradation for the aging effects.
+SBK-L-17155 I Enclosure 2/ Page 26 U.S. Nuclear Regulatory Commission i: ,: Component Type BSAS Carbon Steel FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Carbon Steel FIRE PUMPHOUSE Exposed to Air Outdoor BSAS Carbon Steel NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Carbon Steel NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor BSAS Carbon Steel REVETMENT Exposed to Air Outdoor BSAS Carbon Steel REVETMENT Exposed to Air Outdoor ,,, Intended Function Structural Support Structural Support Structural Support Structural Support Flood Barrier Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Air Indoor Uncontrolled Steel (External) Loss of Material Steel Air Outdoor (External) Loss of Material Air Indoor Uncontrolled Steel (External) Loss of Material Steel Air Outdoor (External) Loss of Material Steel Air Outdoor (External) Loss of Material Steel Air Outdoor (External) Loss of Material Aging NU REG-Table "'''+' ' Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A Program Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A, 503 Program Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A Program Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A, 503 Program Structures lll.A6-11 3.5.1-E, 503, Monitoring Program (T-21) 47 511 Structures lll.A6-11 3.5.1-E, 503, Monitoring Program (T-21) 47 511 SBK-L-17155 I Enclosure 2/ Page 27 U.S. Nuclear Regulatory Commission Component Type BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water Intended Function Flood Barrier Support Flood Barrier Support Flood Barrier Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item IV Item Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A6-11 3.5.1-Monitoring (T-21) 47 H, 514 Program Structures 111.A6-11 3.5.1-Monitoring (T-21) 47 H, 514 Program SBK-L-17155 I Enclosure 2/ Page 28 U.S. Nuclear Regulatory Commission Component Type BSAS Carbon Steel REVETMENT Exposed to Raw Water BSAS Carbon Steel REVETMENT Exposed to Raw Water SSAS Carbon Steel STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Indoor Uncontrolled SSAS Carbon Steel STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor SSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor SSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor Intended Function Flood Barrier Support Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material I Environment Requiring 1,li!'I II Managemeni Steel Raw Water (External) Loss of Material Steel Raw Water (External) Loss of Material Air Indoor Uncontrolled Steel Loss of Material (External) Steel Air Outdoor (External) Loss of Material Cracking, Loss of Bond, Loss of Concrete Air Outdoor (External) Material (Spalling, Scaling) Expansion and Concrete Air Outdoor (External) Cracking cc Aging NU REG-Table , Management ,1so1 vor.; 3.X-1 Note 121tem1 * ' :, Program ' Item Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A6-11 3.5.1-E, 509, Monitoring (T-21) 47 511 Program Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A Program Structures lll.A3-12 3.5.1-Monitoring (T-11) 25 A, 503 Program Structures Monitoring lll.A3-9 3.5.1-A (T-04) 23 Program Structures Monitoring Program, lll.A3-2 3.5.1-A, E, Alkali-Silica (T-03) 27 517 Reaction (ASR) Monitoring Proa ram SBK-L-17155 I Enclosure 2/ Page 29 U.S. Nuclear Regulatory Commission Component Type SSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor SSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor SSAS Concrete (Sump) FIRE PUMPHOUSE Exposed to Raw Water BSAS Concrete (Sump) FIRE PUMPHOUSE Exposed to Raw Water SSAS Concrete (Sump) STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Raw Water Intended Function Structural Support Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Concrete Air Outdoor (External) Loss of Material Cracking, Loss of Concrete Raw Water (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Raw Water (External) Cracking Cracking, Loss of Concrete Raw Water (External) Bond, Loss of Material (Spalling, Scaling) Aging NU REG-Table Management 1801 Vol. Note Program 2 Item Item Structures Monitoring 111.A3-10 3.5.1-A (T-06) 24 Program Structures lll.A3-6 3.5.1-Monitoring (T-01) 26 A Program Structures Monitoring lll.A3-4 3.5.1-A Program (T-05) 31 Structures Monitoring Program , Alkali-lll.A3-2 3.5.1-A, E, Silica Reaction (ASR) (T-03) 27 517 Monitoring Program Structures Monitoring lll.A3-4 3.5.1-A (T-05) 31 Program SBK-L-17155 I Enclosure 2/ Page 30 U.S. Nuclear Regulatory Commission Component Type SSAS Concrete (Sump) STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Raw Water SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled Intended Function Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Expansion and Concrete Raw Water (External) Cracking Cracking, Loss of Air Indoor Uncontrolled Bond, Loss of Concrete (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Concrete (External) Cracking Increase In Porosity and Air Indoor Uncontrolled Permeability, Concrete (External) Cracking, Loss of Material (Spalling, Scaling) Aging NU REG-Table Management 1801 Vol. 3.X-1 Nqte Program 2 Item Item Structures Monitoring Program, Alkali-lll.A3-2 3.5.1-A, E, Silica Reaction (T-03) 27 517 (ASR) Monitoring Program Structures 3.5.1-Monitoring lll.A6-1 E, 511 (T-18) 34 Program Structures Monitoring Program, Alkali-lll.A6-2 3.5.1-E, 511, Silica Reaction (T-17) 36 517 (ASR) Monitoring Program Structures lll.A3-10 3.5.1-Monitoring A (T-06) 24 Program SBK-L-17155 I Enclosure 2/ Page 31 U.S. Nuclear Regulatory Commission Component Type SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor Intended Function Missile Barrier Structural Support Missile Barrier Structural Support Missile Barrier Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Air Outdoor (External) Cracking Expansion and Concrete Air Outdoor (External) Cracking Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Aging NU REG-Table '*it' Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-A Program (T-06) 24 SBK-L-17155 I Enclosure 2/ Page 32 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Raw Water BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Raw Water Intended Function Structural Support Missile Barrier Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Managernent Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Loss of Material, Concrete Air Outdoor (External) Cracking Loss of Material, Concrete Air Outdoor (External) Cracking Cracking, Loss of Concrete Raw Water (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Raw Water (External) Cracking Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring 111.A3-10 3.5.1-A (T-06) 24 Program Structures lll.A6-5 3.5.1-Monitoring (T-15) 35 E, 511 Program Structures lll.A6-5 3.5.1-Monitoring (T-15) 35 E, 511 Program Structures Monitoring lll.A3-4 3.5.1-A (T-05) 31 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 33 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete DISCHARGE TRANSITION STRUCTURE Exposed to Raw Water BSAS Concrete FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Concrete FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Concrete FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Concrete FIRE PUMPHOUSE Exposed to Air Outdoor Intended Function Structural Support Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation ,., .. , Aging Effect Material Environment Requiring Management Increase In Concrete Raw Water (External) Porosity and Permeability, Loss of Strength Cracking, Loss of Concrete Air Indoor Uncontrolled Bond, Loss of (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Concrete (External) Cracking Increase In Porosity and Concrete Air Indoor Uncontrolled Permeability, (External) Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) 'Aging ' NUREG-1 1 Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring lll.A6-6 3.5. 1-E, 511 (T-16) 37 Program Structures Monitoring lll.A3-9 3.5.1-A (T-04) 23 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 3.5.1-A, Monitoring (T-03) 27 517,E, Program & 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-A Program (T-06) 24 Structures Monitoring 111.A3-9 3.5.1-A (T-04) 23 Program SBK-L-17155 I Enclosure 2/ Page 34 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete FIRE PUMPHOUSE Exposed to Air Outdoor BSAS Concrete FIRE PUMPHOUSE Exposed to Air Outdoor BSAS Concrete FIRE PUMPHOUSE Exposed to Air Outdoor BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled Intended Function Structural Support Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Expansion and Concrete Air Outdoor (External) Cracking Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Loss of Material, Concrete Air Outdoor (External) Cracking Cracking, Loss of Concrete Air Indoor Uncontrolled Bond, Loss of (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Concrete (External) Cracking ---------------------Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) 111.A3-2 3.5.1-A, Monitoring (T-03) 27 517,E, Program & 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-A Program (T-06) 24 Structures lll.A3-6 3.5.1-Monitoring (T-01) 26 A Program Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 35 U.S. Nuclear Regulatory Commission Component Type SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Indoor Uncontrolled SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor Intended Function Structural Support Missile Barrier Structural Support Missile Barrier Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Increase In Porosity and Concrete Air Indoor Uncontrolled Permeability, (External) Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Air Outdoor (External) Cracking Expansion and Concrete Air Outdoor (External) Cracking Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Prqgram 2 Item Item Structures Monitoring lll.A3-10 3.5.1-A Program (T-06) 24 Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A6-2 3.5.1-E, 511, Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 36 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Air Outdoor BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Raw Water BSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Raw Water '1" Intended Function Missile Barrier Structural Support Missile Barrier Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation 1: Aging Effect Material Environment Requiring Management Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Loss of Material, Concrete Air Outdoor (External) Cracking Loss of Material, Concrete Air Outdoor (External) Cracking Cracking, Loss of Concrete Raw Water (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Raw Water (External) Cracking ' *.1 Nl'.IREG-Aging Table. " Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring lll.A3-10 3.5.1-A (T-06) 24 Program Structures Monitoring 111.A3-10 3.5.1-A Program (T-06) 24 Structures lll.A6-5 3.5.1-Monitoring A Program (T-15) 35 Structures lll.A6-5 3.5.1-Monitoring (T-15) 35 A Program Structures Monitoring lll.A3-4 3.5.1-A, 509 (T-05) 31 Program Structures Monitoring Program, Alkali-Silica Reaction E, 511, (ASR) 111.A6-2 3.5.1-Monitoring (T-17) 36 517, Program & 519 Building Deformation Monitorina SBK-L-17155 I Enclosure 2/ Page 37 U.S. Nuclear Regulatory Commission ., Component Type SSAS Concrete INTAKE TRANSITION STRUCTURE Exposed to Raw Water BSAS Concrete Masonry Units FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Concrete Masonry Units FIRE PUMPHOUSE Exposed to Air Indoor Uncontrolled BSAS Concrete Masonry Units NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete Masonry Units NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor Intended Function Structural Support Fire Barrier Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Increase In Concrete Raw Water (External) Porosity and Permeability, Loss of Strength Concrete Air Indoor Uncontrolled Block (External) Cracking Concrete Air Indoor Uncontrolled Block (External) Cracking Concrete Air Indoor Uncontrolled Cracking Block (External) Concrete Block Air Outdoor (External) Cracking Aging NU REG-Table I Management 1801 Vol. 3.X-1 Note Program 2 Item Item Program Structures Monitoring lll.A6-6 3.5.1-E, 511 Program (T-16) 37 Fire Protection lll.A3-11 3.5.1-Program (T-12) 43 E, 513 Structures lll.A3-11 3.5.1-Monitoring (T-12) 43 E, 511 Program Structures Monitoring lll.A3-11 3.5.1-E, 511 (T-12) 43 Program Structures lll.A3-11 3.5.1-Monitoring (T-12) 43 E, 511 Program SBK-L-17155 I Enclosure 2/ Page 38 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade Intended Function Structural Support Structural Support Structural Support Flood Barrier Support Flood Barrier Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Agin'g Effect Material Environment Requiring Management Cracking, Loss of Concrete Air Indoor Uncontrolled Bond, Loss of (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Concrete (External) Cracking Increase In Porosity and Concrete Air Indoor Uncontrolled Permeability, (External) Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Soil (External) Bond, Loss of Material (Spalling, Scaling) Cracking, Loss of Concrete Soil (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Soil (External) Cracking ''I' '" 1'11. ., '. Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Structures Monitoring lll.A3-9 3.5.1-A (T-04) 23 Program Structures Monitoring Program, Alkali-lll.A3-2 3.5.1-A, E, Silica Reaction (T-03) 27 517 (ASR) Monitoring Program Structures Monitoring lll.A3-10 3.5.1-A (T-06) 24 Program Structures Monitoring lll.A3-4 3.5.1-A, 509 (T-05) 31 Program Structures Monitoring lll.A3-4 3.5.1-A, 509 (T-05) 31 Program Structures Monitoring Program, Alkali-lll.A6-2 3.5.1-E, 511, Silica Reaction (T-17) 36 517 (ASR) Monitoring Proo ram SBK-L-17155 I Enclosure 2/ Page 39 U.S. Nuclear Regulatory Commission Component Type I BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Below Grade BSAS Concrete REVETMENT Exposed to Air Outdoor Intended Function Support Flood Barrier Support Flood Barrier Support Flood Barrier Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Expansion and Concrete Soil (External) Cracking Increase In Porosity and Concrete Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase In Porosity and Concrete Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase In Concrete Soil (External) Porosity and Permeability, Loss of Strength Increase In Concrete Soil (External) Porosity and Permeability, Loss of Strength Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item I" 1:,1 Structures Monitoring Program, Alkali-lll.A6-2 3.5.1-E, 511, Silica Reaction (T-17) 36 517 (ASR) Monitoring Proqram Structures Monitoring lll.A6-3 3.5.1-E, 511 Program (T-19) 34 Structures Monitoring lll.A6-3 3.5.1-E, 511 Program (T-19) 34 Structures Monitoring lll.A6-6 3.5.1-E, 509, Program (T-16) 37 511 Structures Monitoring lll.A6-6 3.5.1-E, 509, (T-16) 37 511 Program Structures Monitoring lll.A6-1 3.5.1-E, 511 (T-18) 34 Program SBK-L-17155 I Enclosure 2/ Page 40 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete REVETMENT Exposed to Air Outdoor BSAS Concrete REVETMENT Exposed to Air Outdoor SSAS Concrete REVETMENT Exposed to Air Outdoor SSAS Concrete REVETMENT Exposed to Air Outdoor SSAS Concrete REVETMENT Exposed to Air Outdoor SSAS Concrete REVETMENT Exposed to Air Outdoor Intended Function Support Flood Barrier Support Flood Barrier Support Flood Barrier Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring I Management Cracking, Loss of Concrete Air Outdoor (External) Bond, Loss of Material (Spalling, Scaling) Expansion and Concrete Air Outdoor (External) Cracking Expansion and Concrete Air Outdoor (External) Cracking Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Loss of Material, Concrete Air Outdoor (External) Cracking Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures Monitoring lll.A6-1 3.5.1-E, 511 Program (T-18) 34 Structures Monitoring Program, Alkali-lll.A6-2 3.5.1-E, 511, Silica Reaction (T-17) 36 517 (ASR) Monitoring Proqram Structures Monitoring Program, Alkali-lll.A6-2 3.5.1-E, 511, Silica Reaction (T-17) 36 517 (ASR) Monitoring Proqram Structures Monitoring 111.A3-10 3.5.1-A Program (T-06) 24 Structures Monitoring lll.A3-10 3.5.1-A (T-06) 24 Program Structures lll.A6-5 3.5.1-Monitoring (T-15) 35 E, 511 Program SBK-L-17155 I Enclosure 2/ Page 41 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete REVETMENT Exposed to Air Outdoor BSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Indoor Uncontrolled SSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Indoor Uncontrolled BSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor BSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor Intended Function Support Structural Support Structural Support Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring Management Loss of Material, Concrete Air Outdoor (External) Cracking Cracking, Loss of Air Indoor Uncontrolled Bond, Loss of Concrete (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Concrete (External) Cracking Increase In Porosity and Air Indoor Uncontrolled Permeability, Concrete (External) Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Concrete Air Outdoor (External) Material (Spalling, Scaling) Expansion and Concrete Air Outdoor (External) Cracking 'I Aging NU REG-Table Management 1801 Vol. 3.X-1 Note Program 2 Item Item Structures lll.A6-5 3.5.1-Monitoring (T-15) 35 E, 511 Program Structures Monitoring 111.A3-9 3.5.1-A (T-04) 23 Program Structures Monitoring Program, Alkali-lll.A3-2 3.5.1-A, E, Silica Reaction (T-03) 27 517 (ASR) Monitoring Proa ram Structures Monitoring lll.A3-10 3.5.1-A (T-06) 24 Program Structures lll.A3-9 3.5.1-Monitoring (T-04) 23 A Program Structures Monitoring Program, Alkali-lll.A3-2 3.5.1-A, E, Silica Reaction (T-03) 27 517 (ASR) Monitoring Proa ram SBK-L-17155 I Enclosure 2/ Page 42 U.S. Nuclear Regulatory Commission Component Type BSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor SSAS Concrete STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor SSAS Rock (Riprap) REVETMENT Exposed to Air Outdoor SSAS Rock (Riprap) REVETMENT Exposed to Air Outdoor SSAS Roofing For FIRE PUMPHOUSE Exposed to Air Outdoor SSAS Roofing For NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Outdoor Intended Function Structural Support Structural Support Flood Barrier Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material II 1, . 11 II Management'' Increase In Porosity and Concrete Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Loss of Material, Concrete Air Outdoor (External) Cracking Loss of Material, Rock Air Outdoor (External) Loss of Form Loss of Material, Rock Air Outdoor (External) Loss of Form Separation, Roofing Air Outdoor (External) Environmental Degradation, Water In-Leakage Separation, Environmental Roofing Air Outdoor (External) Degradation, Water In-Leakage Aging NU REG-Table Management . 1801 Vol. '* 3.X-1 Note ., .. ,,,.HProgram 1tl '* lli'li2'1tem'1'11*1'
+* ltEim 1:1 H Structures Monitoring lll.A3-10 3.5.1-A (T-06) 24 Program Structures lll.A3-6 3.5.1-Monitoring (T-01) 26 A Program Structures lll.A6-9 3.5.1-Monitoring E, 511 Program (T-22) 48 Structures lll.A6-9 3.5.1-Monitoring E, 511 Program (T-22) 48 Structures Monitoring lll.A6-12 3.5.1-H,505 Program (TP-7) 44 Structures 111.A6-12 3.5.1-Monitoring (TP-7) 44 H,505 Program SBK-L-17155 I Enclosure 2/ Page 43 U.S. Nuclear Regulatory Commission Component Type ' BSAS Roofing For STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Outdoor BSAS Slide Bearing (Fluorogold) NONESSENTIAL SWITCHGEAR BUILDING Exposed to Air Indoor Uncontrolled BSAS Stainless Steel STEAM GENERATOR SLOWDOWN RECOVERY BUILDING Exposed to Air Indoor Uncontrolled Intended Function Structural Support Structural Support Structural Support Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation Aging Effect Material Environment Requiring *I Management Separation, Roofing Air Outdoor (External) Environmental Degradation, Water In-Leakage Fluorogold Air Indoor Uncontrolled Fretting Or (External) Lockup Stainless Air Indoor Uncontrolled None Steel (External) Aging I NU REG-Table Management 1801 Vol. 3.X-1 Note ,Program!!' 1.1 2 ltem:if' ;.1 1; Item* *.. *i Structures Monitoring lll.A6-12 3.5.1-H, 505 (TP-7) 44 Program Structures Monitoring 111.84-2 3.5.1-c Program (TP-1) 52 No Aging Management 111.85-5 3.5.1-A Program (TP-5) 59 Required SBK-L-17155 I Enclosure 2/ Page 44 U.S. Nuclear Regulatory Commission Standard Notes Table 3.5.2-1 Buildings, Structures Within License Renewal Summary of Aging Management Evaluation 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 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&deg;C (<140&deg; 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 "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 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-17155 I Enclosure 2/ Page 46 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Carbon Steel Structural Exposed to Air with Support Borated Water Leakage CNT-CE-Carbon Steel Structural Exposed to Air Indoor Support Uncontrolled CNT-CE-Carbon Steel Structural Exposed to Air Outdoor Support CNT-CE-Fire Penetration Seal Exposed to Air Indoor Fire Barrier Uncontrolled CNT-CE-Reinforced Shelter, Concrete Below Grade Protection CNT-CE-Reinforced Structural Concrete Below Grade Support '1: Material Steel Steel Steel Elastomer Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation +: .** Aging EffectRequiring :Environment Management Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Outdoor (External) Loss of Material ;1, Air Indoor Increased Hardness and Shrinkage Uncontrolled (External) and Loss of Strength Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) 1., Aging 1:i: l'j' I 1 I 1 Table '' ,, ManagE!ment '
+* 1801Vol.'2 '3.X.1 'Nbte1*1 l'I Program Item Item Boric Acid lll.B2-11 Corrosion (T-25) 3.5. 1-55 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Structures 111.A1-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Fire Protection Vll.G-1 3.3.1-61 A Program (A-19) Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05)
+SBK-L-17155 I Enclosure 2/ Page 47 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Shelter, Concrete Below Grade Protection CNT-CE-Reinforced Structural Concrete Below Grade Support CNT-CE-Reinforced Shelter, Concrete Below Grade Protection CNT-CE-Reinforced Structural Concrete Below Grade Support Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation 111,1; Environment Aging 'Effect Requiring Management Soil (External) Expansion and Cracking Soil (External) Expansion and Cracking Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) f. Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item .Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) A, E, Monitoring lll.A1-2 3.5.1-27 Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) A, E, Monitoring lll.A1-2 3.5.1-27 Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A1-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A1-5 Monitoring (T-07) 3.5.1-31 A Program SBK-L-17155 I Enclosure 2/ Page 48 U.S. Nuclear Regulatory Commission Intended Component Type ,Function CNT-CE-Reinforced Shelter, Concrete Below Grade Protection CNT-CE-Reinforced
+* Structural Concrete Below Grade Support CNT-CE-Reinforced Shelter, Concrete Below Grade Protection CNT-CE-Reinforced Structural Concrete Below Grade Support CNT-CE-Reinforced Shelter, Concrete Exposed to Air Indoor Uncontrolled Protection CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring 111 Managerrl'ent 1:11 Increase in Porosity and Soil (External) Permeability, Loss of Strength Increase in Porosity and Soil (External) Permeability, Loss of Strength Soil (External) Loss of Material, Cracking Soil (External) Loss of Material, Cracking Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Aging NUREG I Table '''Managef)1Emt 1801 2 ,' 3.X.1 I Note Program ,, lteri\ Item I Structures lll.A1-7 Monitoring 3.5.1-32 A, 509 Program (T-02) Structures lll.A1-7 Monitoring 3.5.1-32 A, 509 Program (T-02) Structures IJl.A1-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A1-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04)
+SBK-L-17155 I Enclosure 2/ Page 49 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support CNT-CE-Reinforced Concrete Exposed to Air Shelter, Indoor Uncontrolled Protection CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CE-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management 1. Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) ' Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note *I P.rogram ., .,. ltem-i:'i:i I Item Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E 517, Program & (T-03) 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring 3.5.1-27 Program & (T-03) 517, 519 Building Deformation Monitoring Proqram Structures Monitoring Program, Alkali-Silica Reaction lll.A1-2 A, E, (ASR) 3.5.1-27 Monitoring (T-03) 517, 519 Program & Building Deformation SBK-L-17155 I Enclosure 2/ Page 50 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Shelter, Concrete Exposed to Air Protection Indoor Uncontrolled CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CE-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-CE-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CE-Reinforced Concrete Exposed to Air Missile Barrier Outdoor Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment '" [ll1Aging !=ffect Requiring **11**11 Management''* Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) ** Aging NU REG Table II 'ii *I: 1801 Vol. 2 3.X.1 Note Program Item Item Monitoring Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04)
+SBK-L-17155 I Enclosure 2/ Page 5 I U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Shelter, Concrete Exposed to Air Outdoor Protection CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier CNT-CE-Reinforced Structural Concrete Exposed to Air Outdoor Support CNT-CE-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CE-Reinforced Concrete Exposed to Air Missile Barrier Outdoor Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management I* Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Air Outdoor Expansion and Cracking (External) Aging NU REG .Table Management 18011Vol. 2 3.X.1 Note Program Item Item :1 Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures 111.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction lll.A1-2 3.5.1-27 A, E, (ASR) (T-03) 517, 519 Monitoring Program & Building SBK-L-17155 I Enclosure 2/ Page 52 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Concrete Exposed to Air Shelter, Protection Outdoor CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier Material Concrete Concrete ' Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management ' F :1:1*1 I I Air Outdoor Expansion and Cracking (External) Air Outdoor Expansion and Cracking (External) <ii Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item ''' *1*,. Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 53 U.S. Nuclear Regulatory Commission Component Type Intended Function CNT-CE-Reinforced Structural Concrete Exposed to Air Support Outdoor CNT-CE-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CE-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CE-Reinforced Shelter, Concrete Exposed to Air Protection Outdoor CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation 1111 " Agiri'g Effect Requiring I Environment Management Air Outdoor (External) Expansion and Cracking Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Aging NU REG Table :'''''" Management 1801 Vol. 2 3.X.1 Note Program Item Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A1-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 54 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CE-Reinforced Structural Concrete Exposed to Air Support Outdoor CNT-CE-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CE-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CE-Reinforced Shelter, Concrete Exposed to Air Outdoor Protection CNT-CE-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier CNT-CE-Reinforced Structural Concrete Exposed to Air Support Outdoor Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Air Outdoor (External) Loss of Material, Cracking Air Outdoor Loss of Material, Cracking (External) Air Outdoor (External) Loss of Material, Cracking Air Outdoor (External) Loss of Material, Cracking ---*---Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note ' Program .. 1:1: .ltem1 Itel"!' ,,1
+* I Structures lll.A1-10 Monitoring (T-06) 3.5. 1-24 A Program Structures lll.A1-6 Monitoring (T-01) 3.5. 1-26 A Program Structures lll.A1-6 Monitoring (T-01) 3.5. 1-26 A Program Structures 111.A1-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A1-6 Monitoring (T-01) 3.5. 1-26 A Program Structures lll.A1-6 Monitoring (T-01) 3.5. 1-26 A Program SBK-L-17155 I Enclosure 2/ Page 55 U.S. Nuclear Regulatory Commission , Intended Component Type Function CNT-CE-Stainless Steel Structural Exposed to Air Outdoor Support CNT-CEVA-Built-Up Roofing Exposed to Air Shelter, Outdoor Protection CNT-CEVA-Carbon Steel HELB Door Exposed to Air with Shielding Borated Water Leakage CNT-CEVA-Carbon Steel Shelter, Door Exposed to Air with Borated Water Leakage Protection CNT-CEVA-Carbon Steel Structural Door Exposed to Air with Support Borated Water Leakage CNT-CEVA-Carbon Steel HELB Door Exposed to Air Indoor Shielding Uncontrolled Material Stainless Steel Roofing Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment . Management Air Outdoor (External) Loss of Material Air Outdoor Separation, Environmental (External) Degradation, Water In-Leakage Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External Air w/Borated Water Leakage Loss of Material (External Air Indoor Uncontrolled Loss of Material (External) II , Aging I Management 1*11 NU REG 180'1'1Vol:112 1 ,,, ,,Tabl1e111 3.X.1 Note ,,Program :r Item Item !I Structures lll.B2-7 Monitoring (TP-6) 3.5.1-50 A Program Structures Monitoring Program 111.A6-12 3.5.1-44 505, H, Building (TP-7) E, 520 Deformation Monitoring Proaram Boric Acid lll.B2-11 Corrosion (T-25) 3.5.1-55 A Program Boric Acid 111.82-11 Corrosion 3.5.1-55 A Program (T-25) Boric Acid lll.B2-11 Corrosion (T-25) 3.5.1-55 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program SBK-L-17155 I Enclosure 2/ Page 56 U.S. Nuclear Regulatory Commission Intended Component Type, Function CNT-CEVA-Carbon Steel Shelter, Door Exposed to Air Indoor Uncontrolled Protection CNT-CEVA-Carbon Steel Structural Door Exposed to Air Indoor Support Uncontrolled CNT-CEVA-Carbon Steel Structural Exposed to Air with Pressure Borated Water Leakage Barrier CNT-CEVA-Carbon Steel Structural Exposed to Air with Support Borated Water Leakage CNT-CEVA-Carbon Steel Structural Exposed to Air Indoor Pressure Uncontrolled Barrier CNT-CEVA-Carbon Steel Structural Exposed to Air Indoor Support Uncontrolled Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Re,quiring Environment Management Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Aging NU REG Table Management ,1sq1 3.X.1 Note Prb91.'am n '.''I *:11 ,. Item Item Structures lll.A1-12 Monitoring 3.5.1-25 A Program (T-11) Structures 111.A1-12 Monitoring (T-11) 3.5. 1-25 A Program Boric Acid lll.B2-11 Corrosion (T-25) 3.5.1-55 A Program Boric Acid lll.B2-11 Corrosion (T-25) 3.5.1-55 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program SBK-L-17155 I Enclosure 2/Page 57 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Carbon Steel Structural Exposed to Air Outdoor Support CNT-CEVA-Carbon Steel Fire Door Exposed to Air Fire Barrier with Borated Water Leakage CNT-CEVA-Carbon Steel Fire Door Exposed to Air Structural with Borated Water Support Leakage CNT-CEVA-Carbon Steel Fire Door Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CEVA-Carbon Steel Structural Fire Door Exposed to Air Support Indoor Uncontrolled CNT-CEVA-Carbon Steel Fire Door Exposed to Air Fire Barrier Indoor Uncontrolled Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment ' . Air Outdoor (External) Loss of Material Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item 'I'' Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Boric Acid Corrosion lll.B2-11 3.5.1-55 A Program (T-25) Boric Acid Corrosion lll.B2-11 3.5.1-55 A Program (T-25) Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Fire Protection Vll.G-3 Program (A-21) 3.3.1-63 A SBK-L-17155 I Enclosure 2/ Page 58 U.S. Nuclear Regulatory Commission lnterided Component Type Function CNT-CEVA-Carbon Steel Structural Fire Door Exposed to Air Support Indoor Uncontrolled CNT-CEVA-Carbon Steel Structural Tech Spec Door Exposed Pressure to Air with Borated Water Barrier Leakage CNT-CEVA-Carbon Steel Tech Spec Door Exposed Structural to Air with Borated Water Support Leakage CNT-CEVA-Carbon Steel Structural Tech Spec Door Exposed Pressure to Air Indoor Uncontrolled Barrier CNT-CEVA-Carbon Steel Structural Tech Spec Door Exposed Support to Air Indoor Uncontrolled CNT-CEVA-Elastomeric Structural Pressure Seal and Caulk Pressure Exposed to Air Indoor Uncontrolled Barrier Material Steel Steel Steel Steel Steel Elastomer Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment 111,, w 1:1 :i*ill, ,,, :1:111:: 1'1'11 'l:l'l'il:: ' Aging Effect Requi'ring,ll: J1j::' *. Management :1' '1 1* i,"11 Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Increased Hardness and Shrinkage and Loss of Strength (External) :II 1Aglng :1.* 1 * 'I" 1'1 **'*''I I 1' l'i' .* *1111 : : ' : ' : : I ' ' I I 1, ' ' ' :;1'''Note ::I Managementll:' 1'118011'Voll;121, 1l,11.3.ft1:lt 111:']' 'I ''1 ''l:J'I:, 'Ill '*' 'T'l , i. ,, ''''f'''',,,1:1:: liii:J ,,!11:,i:1 , , Progrc:irn, ,,4, 1 , 1 ll'll*'i1llte1T'l]il:]I:, 1 ,1',11lem,*1,,"1i' Fire Protection Vll.G-3 Program (A-21) 3.3.1-63 A Boric Acid Corrosion lll.B2-11 3.5.1-55 A Program (T-25) Boric Acid Corrosion lll.B2-11 3.5.1-55 A Program (T-25) Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Structures Ill.A 1-12 Monitoring (T-11) 3.5.1-25 A Program Structures Monitoring Vll.G-1 3.3.1-61 E, 515 (A-19) Program SBK-L-17155 I Enclosure 2/ Page 59 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Elastomers Expansion I Exposed to Air Outdoor Separation CNT-CEVA-Fire Penetration Seal Exposed Fire Barrier to Air Indoor Uncontrolled CNT-CEVA-Fire Penetration Seal Exposed Fire Barrier to Air Indoor Uncontrolled CNT-CEVA-Penetration Structural Seal Exposed to Air Indoor Pressure Uncontrolled Barrier CNT-CEVA-Reinforced Shelter, Concrete Below Grade Protection CNT-CEVA-Reinforced Structural Concrete Below Grade Support CNT-CEVA-Reinforced Shelter, Concrete Below Grade Protection Material Elastomer Elastomer Elastomer Elastomer Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Air Outdoor Increased Hardness and Shrinkage (External) and Loss of Strength Air Indoor Increased Hardness and Shrinkage Uncontrolled (External) and Loss of Strength Air Indoor Increased Hardness and Shrinkage Uncontrolled (External) and Loss of Strength Air Indoor Increased Hardness and Shrinkage Uncontrolled (External) and Loss of Strength Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) Soil (External) Expansion and Cracking Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note *
+* I 1 Item Item ;;I Structures Vll.G-1 Monitoring 3.3.1-61 E, 515 Program (A-19) Fire Protection Vll.G-1 3.3.1-61 A Program (A-19) Structures Vll.G-1 Monitoring 3.3.1-61 E,515 Program (A-19) Structures Vll.G-1 Monitoring 3.3.1-61 E, 515 Program (A-19) Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A1-2 3.5.1-27 A, E, MonitorinQ (T-03) 517, 519 SBK-L-17155 I Enclosure 2/ Page 60 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Structural Concrete Below Grade Support CNT-CEVA-Reinforced Shelter, Concrete Below Grade Protection CNT-CEVA-Reinforced Structural Concrete Below Grade Support CNT-CEVA-Reinforced Shelter, Concrete Below Grade Protection Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring Management 1:1, Soil (External) Expansion and Cracking Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Soil (External) Permeability, Loss of Strength 111 Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note rl* Program *11 Item 1:1
+* 111 *' "' Program, Alkali-Silica Reaction (ASR) Monitoring Program & Building Deformation Monitorina Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring (T-03) 3.5. 1-27 517, 519 Program & Building Deformation Monitoring Structures lll.A1-5 Monitoring (T-07) 3.5. 1-31 A Program Structures lll.A1-5 Monitoring (T-07) 3.5. 1-31 A Program Structures lll.A1-7 Monitoring (T-02) 3.5. 1-32 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 61 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Structural Concrete Below Grade Support CNT-CEVA-Reinforced Shelter, Concrete Below Grade Protection CNT-CEVA-Reinforced Structural Concrete Below Grade Support CNT-CEVA-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Indoor Uncontrolled Protection CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation !,I: 1:1:1 ,!:I ::1 ' ' '" .111:' Aging Effect Requiring Environment Management I*' : I ; j , ' j Increase in Porosity and Soil (External) Permeability, Loss of Strength Soil (External) Loss of Material, Cracking Soil (External) Loss of Material, Cracking Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Aging NUREG, Table Management 1801 Vol. 2 3.X.1 Note 1: Program ,,,, 1ltem Item Structures lll.A1-7 Monitoring 3.5. 1-32 A, 509 Program (T-02) Structures lll.A1-6 Monitoring 3.5. 1-26 A Program (T-01) Structures lll.A1-6 Monitoring (T-01) 3.5. 1-26 A Program Structures lll.A1-9 Monitoring 3.5. 1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures 111.A1-9 Monitoring 3.5.1-23 A Program (T-04)
+SBK-L-17155 I Enclosure 2/ Page 62 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support CNT-CEVA-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CEVA-Reinforced Concrete Exposed to Air Shelter, Protection Indoor Uncontrolled CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment rvianagement Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction lll.A1-2 3.5.1-27 A, E, (ASR) (T-03) 517, 519 Monitoring Program & Building SBK-L-171 SS I Enclosure 2/ Page 63 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Concrete Exposed to Air Structural Indoor Uncontrolled Support CNT-CEVA-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Protection Indoor Uncontrolled CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier Material 'i' Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Aging NU REG Table Management 1801 Vol,. 2 ':I: + Note Program Item Item Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 64 U.S. Nuclear Regulatory Commission :*: Intended Component Type j*I F'u11ction l,i i'l I:; l'I CNT-CEVA-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-CEVA-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CEVA-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Outdoor Protection CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier CNT-CEVA-Reinforced Concrete Exposed to Air Flood Barrier Outdoor ii Material,, H* ;: Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation I. " Aging Effect Requiring i'I :Environment Management l*I .. :* Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) I.* :j 1-l1NUREG Table' l.Jl!l1 Management 1801 Vol. 2 3.X.1 Note 1' Program Item Item Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction lll.A1-2 3.5.1-27 A, E, (ASR) (T-03) 517, 519 Monitoring Program & Buildina SBK-L-17155 I Enclosure 2/ Page 65 U.S. Nuclear Regulatory Commission Component Type Intended Function CNT-CEVA-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Protection Outdoor CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier Material Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation :'1:1'] ' :lil:j: ii: :pi ,I: ,, Environment Aging Effect Requiring Management Air Outdoor Expansion and Cracking (External) Air Outdoor (External) Expansion and Cracking Air Outdoor Expansion and Cracking (External) :1: +, , . Aging Table" Management 1801 Vol. 2 3.X.1 Note Program Item Item Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring 111.A1-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) 111.A1-2 A, E, Monitoring (T-03) 3.5. 1-27 517, 519 Program & Building Deformation Monitoring Proqram Structures Monitoring Program, Alkali-Silica Reaction lll.A1-2 A, E, (ASR) 3.5.1-27 Monitoring (T-03) 517, 519 Program & Building Deformation SBK-L-17155 I Enclosure 2/ Page 66 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Concrete Exposed to Air Flood Barrier Outdoor CNT-CEVA-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Protection Outdoor CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier CNT-CEVA-Reinforced Concrete Exposed to Air Flood Barrier Outdoor Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Monitoring Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures Ill.A 1-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A1-6 Monitoring (T-01) 3.5.1-26 A Program SBK-L-17155 I Enclosure 2/ Page 67 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CEVA-Reinforced Concrete Exposed to Air Missile Barrier Outdoor CNT-CEVA-Reinforced Shelter, Concrete Exposed to Air Outdoor Protection CNT-CEVA-Reinforced Structural Concrete Exposed to Air Pressure Outdoor Barrier CNT-CEVA-Tech Spec Structural Seal Exposed to Air Indoor Pressure Uncontrolled Barrier CNT-CEVA-Tech Spec Structural Seal Exposed to Air Pressure Outdoor Barrier CNT-CEVA-Thermal Insulation Aluminum Structural Jacketing in Air with Support Borated Water Leakage Material Concrete Concrete Concrete Elastomer Elastomer Aluminum Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring 1 Managerrteni1 1'. ' Air Outdoor (External) Loss of Material, Cracking Air Outdoor Loss of Material, Cracking (External) Air Outdoor (External) Loss of Material, Cracking 'l*'l:ill Air Indoor Increased Hardness and Shrinkage Uncontrolled (External) and Loss of Strength Air Outdoor Increased Hardness and Shrinkage (External) and Loss of Strength Air w/Borated Water Leakage Loss of Material (External) Aging NU REG Table 11' 1Management *1:1 1so,1IV01..2 3:x.1 :!. *Note Program Item Item I Structures lll.A1-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A1-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A1-6 Monitoring (T-01) 3.5.1-26 A Program Structures Vll.G-1 Monitoring (A-19) 3.3.1-61 E, 515 Program Structures Vll.G-1 Monitoring (A-19) 3.3.1-61 E, 515 Program Boric Acid Corrosion lll.B2-6 3.5.1-55 A (TP-3) Program SBK-L-17155 I Enclosure 2/ Page 68 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-Cl-Carbon Steel Door Structural Exposed to Air with Support Borated Water Leakage CNT-Cl-Carbon Steel Door Shelter, Exposed to Air Indoor Uncontrolled Protection CNT-Cl-Carbon Steel Structural Exposed to Air with Support Borated Water Leakage CNT-Cl-Carbon Steel Structural Exposed to Air Indoor Support Uncontrolled CNT-Cl-Conduit Fire Wrap Exposed to Air Indoor Fire Barrier Uncontrolled CNT-Cl-Conduit Fire Wrap Exposed to Air with Fire Barrier Borated Water Leakage Material"" Steel Steel Steel Steel Stainless Steel Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring1,1 Management' Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Nooe Air Indoor Deformation/reduction in Uncontrolled structural capacity (External) directly/indirectly due to the expansion of concrete Nooe Air w/Borated Deformation/reduction in Water Leakage structural capacity (External) directly/indirectly due to the expansion of concrete l:f: Aging NUREG, [I 1,,,,,Table,, 1, ,, ,,,1: ::.18011 Vol!l 2 ' 3.X.1 1' "Note Program Item Item Boric Acid lll.B2-11 Corrosion (TP-25) 3.5.1-55 A Program Structures lll.A4-5 Monitoring 3.5, 1-25 A Program (T-11) Boric Acid lll.B2-11 Corrosion (TP-25) 3.5, 1-55 A Program Structures lll.A4-5 Monitoring (T-11) 3,5, 1-25 A Program Nooe Building lll.B1 .2-7 Deformation (TP-5) 3.5.1-59 A, E, 520 Monitoring Program Nooe Building lll.B2-9 Deformation (TP-4) 3.5, 1-59 A, E, 520 Monitoring Program SBK-L-17155 I Enclosure 2/ Page 69 U.S. Nuclear Regulatory Commission Component Type Intended Function CNT-Cl-Heat Shield Exposed to Air with Fire Barrier Borated Water Leakage CNT-Cl-Radiant Heat Shield Exposed to Air Fire Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-Cl-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support Material Stainless Steel Stainless Steel Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation '*1 .: !* .' ,'11 I*/ :i: 'r 1*11*1'1'1 111, " .,, , .
+* Environment* 11 f1l1l11Aging Effect I' .Iii.''' .I ' ''I LI {I ':11 ,*1*1+1 11 '!'1 ''' I ' ' Ii: ' J 1lfl11 l:ii:l 1 Management1lf ll1H11111 J) :Iii;' '* ,. 1:1:1, il:'i, .1:11:: ,,,*I: Nooe Air w/Borated Deformation/reduction in Water Leakage structural capacity (External) directly/indirectly due to the expansion of concrete Nooe Air Indoor Deformation/reduction in Uncontrolled structural capacity (External) directly/indirectly due to the expansion of concrete Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Aging .. NUREG '1. 111 *i:,:Table /i11 1'1 i:i Me1nagerT)el1t, 'j"1'I , 1'ao;1,vo1' .. 12 Iii 'I. 'I" r1:i :1::r ' *:1: !Note 1 ll',:3.x.1:1,,' 11::1!11' p111'J!l111i l'i:ilili:l11tem,11J.l1 1!,,w.1tem111 * '*;i:1J: 11:1: *I""**' * "I.* .,, T Nooe Building lll.B2-9 Deformation (TP-4) 3.5.1-59 A, E, 520 Monitoring Program Nooe Building lll.B1 .2-7 Deformation (TP-5) 3.5.1 -59 A, E, 520 Monitoring Program Structures lll.A4-3 Monitoring 3.5.1 -23 A Program (T-04) Structures lll.A4-3 Monitoring 3.5.1-23 A Program (T-04) Structures 111.A4-3 Monitoring 3.5.1 -23 A Program (T-04) Structures 111.A4-3 Monitoring 3.5.1-23 A Program (T-04)
+SBK-L-17155 I Enclosure 2/ Page 70 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-Cl-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-Cl-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) ,, Aging ,, NUREG Table Managell!ent 1801 Vol. 2 3.X.1 Note Program Item Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A4-2 A, E, Monitoring 3.5.1-27 Program & (T-03) 517, 519 Building Deformation Monitoring Proaram Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A4-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A4-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A4-2 A, E, Monitoring 3.5.1-27 Program, Alkali-(T-03) 517, 519 I SBK-L-17155 I Enclosure 2/ Page 71 U.S. Nuclear Regulatory Commission :*1 Intended Component Type Function '1'! CNT-Cl-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-Cl-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-Cl-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-Cl-Stainless Steel Structural Exposed to Air with Support Borated Water Leakage Material Concrete Concrete Concrete Concrete Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation ;I t !ill! . n . , . .. . . {l:.1'1.ir*11:1 11'1 ..... 11. tl'!*i" '" ! . *If' 1 *:*:!**A in Effect Re umn *1:1*1' 1111
+* Environment , * .***. r11:'i11'iJ1l11I ,*; ,I I ' I :I:,;. 1,f I, Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete
+* l:11Tableji;,1 *** , Aging 1:i :;l,J:1'MaDagemenf'lil1 1*"t801,:Vol1: 211:1 'I 1 '111 u *.** ,j11'( ''j'1p I' *lh!*11l'l:H1
+* Item ' I' 1'1, *:, ,,, I*:; rogp\lm 1 .. "' *** *f:i:. ., ... I Silica Reaction (ASR) Monitoring Program & Building Deformation Monitoring Proaram Structures lll.A4-4 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A4-4 Monitoring (T-06) 3.5.1-24 A Program Structures llJ.A4-4 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A4-4 Monitoring (T-06) 3.5.1-24 A Program Nooe Structures Monitoring lll.B1.29 Program, (TP-4) 3.5.1-59 A, E, 520 Building Deformation SBK-L-17155 I Enclosure 2/ Page 72 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-Cl-Stainless Steel Structural Exposed to Air Indoor Support Uncontrolled CNT-Cl-Stainless Steel Structural Raw Water Support CNT-CS-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-CS-Reinforced HELB Concrete Exposed to Air Indoor Uncontrolled Shielding Material Stainless Steel Stainless Steel Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Nooe Air Indoor Reduction in structural capacity Uncontrolled directly. Indirectly due to (External) expansion and cracking of concrete Raw Water (External) Loss of Material Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Aging NU REG Table Management 1801 VoL 2 3.X.1 Note Program Item Item Monitoring Program Nooe Structures Monitoring Program, lll.B1 .2-7 Building (TP-5) 3.5.1-59 A, E, 520 Deformation Monitoring Proqram Structures V.01-15 Monitoring (E-01) 3.2.1-7 E, 514 Program ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05)
+SBK-L-17155 I Enclosure 2/ Page 73 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-CS-Reinforced Shelter, Concrete Exposed to Air Indoor Uncontrolled Protection CNT-CS-Reinforced Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CS-Reinforced Structural Concrete Exposed to Air Indoor Uncontrolled Support CNT-CS-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss of Uncontrolled (External) Material (Spalling, Scaling) Air Indoor Uncontrolled Loss of Material (External) Aging 'NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item* ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section 11.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A SBK-L-17155 I Enclosure 2/ Page 74 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-CS-Reinforced HELB Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-CS-Reinforced Shelter, Concrete Exposed to Air Indoor Uncontrolled Protection CNT-CS-Reinforced Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Material Environment Aging Effect Requiring 1'1* 'Management 11. ' Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Aging NU REG Table l*I Management 1801 Vol. :2 3,.X.1 Note Program Item *Item Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 3.3.1-67 A Program (A-91) Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 3.3.1-67 A Program (A-91)
+SBK-L-17155 I Enclosure 2/ Page 75 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air HELB Indoor Uncontrolled Shielding Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring ' Management Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ll.A1-3 A, E, Monitoring (C-04) 3.5.1-15 517, 519 Program Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ll.A1-3 A, E, Monitoring (C-04) 3.5.1-15 517, 519 Program Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program ll.A1-3 3.5.1-15 A, E, (C-04) 517, 519 Alkali-Silica Reaction (ASR)
+SBK-L-17155 I Enclosure 2/ Page 76 U.S. Nuclear Regulatory Commission Component Type Function CNT-CS-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-CS-Reinforced Shelter, Concrete Exposed to Air Protection Indoor Uncontrolled Material Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Req6iring ' Environment Management Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging "I NUREG 'I Table Management1'1 1801 Vol.121'1 3.X.1 Note11 ,,,. Program Item Item Monitoring Program Building Deformation Monitoring Proqram ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ILA1-3 A, E, Monitoring (C-04) 3.5.1-15 517, 519 Program Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ILA1-3 A, E, Monitoring (C-04) 3.5.1-15 517, 519 Program Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 77 U.S. Nuclear Regulatory Commission Component ,J"ype 1 CNT-CS-Reinforced Concrete Exposed to Air Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Indoor Uncontrolled ti. Intended Function Shielding Structural Pressure Barrier Structural Support ,I Material Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Environment ' 1:1 I I I l'i' Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Aging Effect Requiring Management '* Expansion and Cracking Expansion and Cracking Expansion and Cracking 'Aging .1 Management Program ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Proqram ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring NU REG 1801 Vol. 2 Item ILA1-3 (C-04) ILA1-3 (C-04) ll.A1-3 (C-04) Table 3.X.1 Item* 11'\''l 3.5.1-15 3.5.1-15 3.5.1-15 Note A, E, 517, 519 A, E, 517, 519 A, E, 517, 519 SBK-L-17155 I Enclosure 2/ Page 78 U.S. Nuclear Regulatory Commission ,. *I *1 :Ii Intended Component Type Function *I CNT-CS-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-CS-Reinforced HELB Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-CS-Reinforced Shelter, Concrete Exposed to Air Indoor Uncontrolled Protection Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation I Aging Effect Requiring Environment Management *1:1: 'l',1111 1., :i Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Aging NU REG Table *u1:: , Note 1:;1 Management 1801 Vol. 2 3.X.1 Program Item ,Item Program Fire Protection Program Vll.G-28 3.3.1-65 A (A-90) Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 3.3.1-65 A Program (A-90)
+SBK-L-17155 I Enclosure 2/ Page 79 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Reinforced Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CS-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Fire Barrier Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Flood Barrier Indoor Uncontrolled CNT-CS-Reinforced HELB Concrete Exposed to Air Shielding Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation ';' Aging Effect Requiring Environment Management Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Uncontrolled Concrete Cracking and Spalling (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) .. I Aging NU REG Table Management 1801Vol. 2 3.X.1 Note Program Item Item. Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A ASME Section ll.A1-4 XI, Subsection (C-03) 3.5.1-1 A, 516 IWL Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5.1-1 A, 516 IWL Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5.1-1 A, 516 IWL Program SBK-L-17155 I Enclosure 2/ Page 80 U.S. Nuclear Regulatory Commission Component Type 'Intended''' Function . ; . I i : : ' . . : . ; ' . ;
+* I ' I CNT-CS-Reinforced Concrete Exposed to Air Missile Barrier Indoor Uncontrolled CNT-CS-Reinforced Shelter, Concrete Exposed to Air Protection Indoor Uncontrolled CNT-CS-Reinforced Concrete Exposed to Air Shielding Indoor Uncontrolled CNT-CS-Reinforced Structural Concrete Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CS-Reinforced Structural Concrete Exposed to Air Support Indoor Uncontrolled CNT-CS-Airlock Hatch Structural Sight Glass Exposed to Air Pressure Indoor Uncontrolled Barrier .Material 1:k, .: .,,, Concrete Concrete Concrete Concrete Concrete Glass Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation I , '*.'', l1 l*lil;11'\ *11:111'1' ii lllij!l!il ',1!11111*1!1,:li Environment *Aging' Effect Requiring 1 1 11 :I ' . .1 .I. ' Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of (External) Material (Spalling, Scaling) Air Indoor Uncontrolled None (External) ,, ,. *1:1 I NURE1G11jj:11 ill .. ':1;;.j',. *r 'I 111*1 Ag,1rig1*:1111llil':1I 1:,1:i11Tabfe.111 ,,:i.,.I "I '11.Fl,::1: ,,:,:,:1* '' ,, Nbte *,'* I' Management 'II . '1111:1,lil PrograM 111'1''"1 u11:l:l11tem ,' *::1 1:::1* I ' I . .I 'I' 1' ASME Section 11.A1-4 XI, Subsection (C-03) 3.5. 1-1 A, 516 IWL Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5. 1-1 A, 516 IWL Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5. 1-1 A, 516 IWL Program ASME Section 11.A1-4 XI, Subsection (C-03) 3.5. 1-1 A, 516 IWL Program ASME Section 11.A1-4 XI, Subsection (C-03) 3.5.1-1 A, 516 IWL Program V.F-6 None 3.2. 1-52 A (EP-15)
+SBK-L-17155 I Enclosure 2/ Page 81 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Carbon Steel Structural Electrical Penetration Pressure Exposed to Air with Barrier Borated Water Leakage CNT-CS-Carbon Steel Electrical Penetration Structural Exposed to Air with Support Borated Water Leakage CNT-CS-Carbon Steel Structural Electrical Penetration Pressure Exposed to Air Indoor Barrier Uncontrolled CNT-CS-Carbon Steel Electrical Penetration Structural Exposed to Air Indoor Support Uncontrolled CNT-CS-Carbon Steel Structural Equipment Hatch Exposed Pressure to Air with Borated Water Barrier Leakage CNT-CS-Carbon Steel Equipment Hatch Exposed Structural to Air with Borated Water Support Leakage Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation . n.11 f!, 111 , JiV' ,,, *1'' ':;:11r';*1:1,YI , Aging Effect Requiring Environment 11 111 .. 1r1 ', Management ' I 111:-:11:,1"111'1:1':111:1:11: 11:1' jli , 'l*l*I' ' Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) , . Table Aging NU REG + Management 18.01 Vol. 2 3.X.1 Note Program Item 11. Item Boric Acid lll.B2-11 (T-Corrosion 3.5.1-55 A 25) Program Boric Acid 111.B2-11 (T-Corrosion 25) 3.5.1-55 A Program ASME Section ll.A3-1 XI, Subsection (C-12) 3.5.1-18 A IWE Program ASME Section ll.A3-1 XI, Subsection (C-12) 3.5.1-18 A IWE Program Boric Acid 111.B2-11 (T-Corrosion 25) 3.5.1-55 A Program Boric Acid lll.B2-11 (T-Corrosion 25) 3.5.1-55 A Program SBK-L-17155 I Enclosure 2/ Page 82 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Carbon Steel Structural Equipment Hatch Exposed Pressure to Air Indoor Uncontrolled Barrier CNT-CS-Carbon Steel Structural Equipment Hatch Exposed Support to Air Indoor Uncontrolled CNT-CS-Carbon Steel Structural Exposed to Air with Pressure Borated Water Leakage Barrier CNT-CS-Carbon Steel Structural Exposed to Air with Borated Water Leakage Support CNT-CS-Carbon Steel Structural Exposed to Air with Pressure Borated Water Leakage for Barrier HVAC Penetrations CNT-CS-Carbon Steel Exposed to Air with Structural Borated Water Leakage for Support HVAC Penetrations Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation ' r :1: Aging Effect Requiring Environment Management Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Aging NU REG *Table. Management 1801 Vol. 2 3.X.1 Note Program Item Item ASME Section ll.A3-6 XI, Subsection (C-16) 3.5.1-18 A IWE Program ASME Section ll.A3-6 XI, Subsection (C-16) 3.5. 1-18 A IWE Program Boric Acid lll.B2-11 (T-Corrosion 3.5.1-55 A Program 25) Boric Acid lll.B2-11 (T-Corrosion 3.5.1-55 A Program 25) Boric Acid Corrosion lll.B2-11 (T-3.5.1-55 A Program 25) Boric Acid Corrosion lll.B2-11 (T-3.5.1-55 A Program 25)
+SBK-L-17155 I Enclosure 2/ Page 83 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Carbon Steel Structural Exposed to Air Indoor Pressure Uncontrolled Barrier CNT-CS-Carbon Steel Structural Exposed to Air Indoor Support Uncontrolled CNT-CS-Carbon Steel Structural Exposed to Air Indoor Pressure Uncontrolled For HVAC Barrier Penetrations CNT-CS-Carbon Steel Exposed to Air Indoor Structural Uncontrolled For HVAC Support Penetrations CNT-CS-Carbon Steel Mechanical (Piping) Structural Penetration Exposed to Air Pressure with Borated Water Barrier Leakage CNT-CS-Carbon Steel Mechanical (Piping) Structural Penetration Exposed to Air with Borated Water Support Leakage I Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management .. Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Aging NU REG Table ,y; Management 1801 Vol. 2 3.X.1 Note
+* Program Item Item 1. + ASME Section ll.A1-11 XI, Subsection (C-09) 3.5.1-6 A IWE Program ASME Section ll.A1-11 XI, Subsection (C-09) 3.5.1-6 A IWE Program ASME Section XI, Subsection ll.A3-1 3.5.1-18 A IWE Program (C-12) ASME Section XI, Subsection ll.A3-1 3.5.1-18 A IWE Program (C-12) Boric Acid lll.B2-11 (T-Corrosion 3.5.1-55 A Program 25) Boric Acid lll.B2-11 (T-Corrosion 3.5.1-55 A Program 25)
+SBK-L-17155 I Enclosure 2/ Page 84 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Carbon Steel Structural Mechanical (Piping) Pressure Penetration Exposed to Air Barrier Indoor Uncontrolled CNT-CS-Carbon Steel Mechanical (Piping) Structural Penetration Exposed to Air Support Indoor Uncontrolled CNT-CS-Carbon Steel Structural Personnel Hatch Exposed Pressure to Air with Borated Water Barrier Leakage CNT-CS-Carbon Steel Personnel Hatch Exposed Structural to Air with Borated Water Support Leakage CNT-CS-Carbon Steel Structural Personnel Hatch Exposed Pressure to Air Indoor Uncontrolled Barrier CNT-CS-Carbon Steel Structural Personnel Hatch Exposed Support to Air Indoor Uncontrolled Material Steel Steel Steel Steel Steel Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation + . J'I 'lili1, "' 1:1+ Hl1l;ii! *,,. , 1:*' . I' Environment ' 1 ** : ... "1* 1*11.p::.Management.1,1,11,,"," 111 . :L 1-1.I:, *:1 i< , i: ir J ,, ,,, .. ,:,:1,. ir:1:1r ,,1, , ,, Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) . Aging , NU REG Table +, 111Management 1801if\'ol::2j.1:I 1:1nll 3'.x.1 *I "' Npte :1::t1,:, r , *I* ii: :*ii 1111i!l1tem**ji111 :!11 .':Iii, j"J!li!j11111 ltem1l1 '11 I' **,*1*j*I Ill ASME Section XI, Subsection ll.A3-1 3.5.1-18 A IWE Program (C-12) ASME Section XI, Subsection ll.A3-1 3.5.1-18 A IWE Program (C-12) Boric Acid Corrosion lll.B1.1-11 3.5.1-55 A Program (TP-25) Boric Acid Corrosion lll.B1 .1-11 3.5.1-55 A Program (TP-25) ASME Section ll.A3-6 XI, Subsection (C-16) 3.5.1-18 A IWE Program ASME Section ll.A3-6 XI, Subsection (C-16) 3.5.1-18 A !WE Program SBK-L-17155 I Enclosure 2/ Page 85 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Elastomers Structural Electrical Penetration Pressure Assembly Exposed to Air Barrier Indoor Uncontrolled CNT-CS-Mechanical (Piping) Penetration Structural Stainless Steel Flued Head Pressure Exposed to Air Indoor Barrier Uncontrolled CNT-CS-Mechanical (Piping) Penetration Structural Stainless Steel Flued Head Support Exposed to Air Indoor Uncontrolled CNT-CS-Mechanical (Piping) Penetration Structural Stainless Steel Flued Head Pressure Exposed to Air with Barrier Borated Water Leakage CNT-CS-Mechanical (Piping) Penetration Structural Stainless Steel Flued Head Support Exposed to Air with Borated Water Leakage Material Elastomer Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management II ,;: !:1: '" Air Indoor Uncontrolled Loss of Sealing, Leakage Through (External) Containment Air Indoor Uncontrolled Cracking (External) Air Indoor Uncontrolled Cracking (External) Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete . Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item ASME Section XI, Subsection IWE Program, Structures Monitoring ll.A3-7 3.5.1-16 A, E, 520 Program & (C-18) Building Deformation Monitoring Proaram ASME Section ll.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program ASME Section ll.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program Nooe Structures Monitoring lll.B2-9 Program, (TP-4) 3.5.1-59 A, 520 Building Deformation Monitorina SBK-L-17155 I Enclosure 2/ Page 86 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Reinforced Shelter, Concrete Below Grade Protection CNT-CS-Reinforced Structural Concrete Below Grade Support CNT-CS-Reinforced Shelter, Concrete Below Grade Protection CNT-CS-Reinforced Structural Concrete Below Grade Support Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management' Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Soil (External) Material (Spalling, Scaling) Soil (External) Expansion and Cracking Soil (External) Expansion and Cracking Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item *Item Program ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section ll.A1-7 XI, Subsection 3.5.1-1 A IWL Program (C-05) ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ll.A1-3 A, E, Monitoring (C-04) 3.5.1-15 517, 519 Program Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program ll.A1-3 A, E, (C-04) 3.5.1-15 517, 519 Alkali-Silica Reaction (ASR) Monitorinq SBK-L-17155 I Enclosure 21 Page 87 U.S. Nuclear Regulatory Commission *1: i*'I I* Intended Component Type ' Function ' CNT-CS-Reinforced Shelter, Concrete Below Grade Protection CNT-CS-Reinforced Structural Concrete Below Grade Support CNT-CS-Reinforced Shelter, Concrete Below Grade Protection CNT-CS-Reinforced Structural Concrete Below Grade Support ' Material Concrete Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation 'J:i Aging Effect Requiring 'Environment,,J.I: I *l*M I . Management I*! ' 1 I 111:1 1*1:1n, Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Soil (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Soil (External) Permeability, Loss of Strength Increase in Porosity and Soil (External) Permeability, Loss of Strength .I I'." '' I :1:,I Aging1 NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item .,.,. Program Building Deformation Monitoring Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5.1-1 A, 516 IWL Program ASME Section ll.A1-4 XI, Subsection (C-03) 3.5. 1-1 A, 516 IWL Program ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) ll.A1-6 A, 509, Monitoring 3.5.1-15 516, E, Program (C-02) 517, 519 Building Deformation Monitoring Proaram ASME Section XI, Subsection IWL Program ll.A1-6 A, 509, (C-02) 3.5.1-15 516, E, Alkali-Silica 517, 519 Reaction (ASR) Monitorinq SBK-L-17155 I Enclosure 21 Page 88 U.S. Nuclear Regulatory Commission :'!' 1.1 Component Type Intended Function CNT-CS-Stainless Steel Electrical Penetration Structural Assembly Exposed to Air Pressure with Borated Water Barrier Leakage CNT-CS-Stainless Steel Electrical Penetration Structural Assembly Exposed to Air Pressure with Borated Water Barrier Leakage CNT-CS-Stainless Steel Structural Electrical Penetration Assembly Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CS-Stainless Steel Electrical Penetration Structural Assembly Exposed to Air Support Indoor Uncontrolled I' ,', Material. Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation 1;1:, '''1l1111,l1l*!li:;:1!v ' , .,, Environment11:11;, '' Aging Effect Requiring *j}l{l'.IH *il'I ,Management ' ,I: ,. :I* ,,, m11'i'1it' .,,,w111:1 :11, :Iii ,,,1,1111"1 "': 11111., *' Nooe Reduction in structural capacity Air w/Borated Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Air Indoor Uncontrolled Cracking (External) Air Indoor Uncontrolled Cracking (External) ,, Table 1:l,p1 Aging NU REG Management 1801 Vol. 2 3.X.1 Note I, + Program 1,1,tel'Tl
+* Item '* Program Building Deformation Monitoring Program Nooe Structures Monitoring Program, Building lll.B2-9 3.5. 1-59 A, 520 Deformation (TP-4) Monitoring Program Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5. 1-59 A, 520 Deformation Monitoring Program ASME Section ll.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program ASME Section XI, Subsection 11.A3-2 3.5.1-10 A (C-15) IWE Program SBK-L-17155 I Enclosure 2/ Page 89 U.S. Nuclear Regulatory Commission Intended Component Type Function CNT-CS-Stainless Steel Exposed to Air with Shielding Borated Water Leakage CNT-CS-Stainless Steel Structural Exposed to Air with Support Borated Water Leakage CNT-CS-Stainless Steel Exposed to Air Indoor Shielding Uncontrolled CNT-CS-Stainless Steel Structural Exposed to Air Indoor Support Uncontrolled CNT-CS-Stainless Steel Fuel Transfer Tube Expansion I Bellows Exposed to Air Separation with Borated Water Leakage Material Stainless Steel Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Aging Effect Requiring , Environment Management Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Air Indoor Uncontrolled Cracking (External) Air Indoor Uncontrolled Cracking (External) Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Aging NU REG Table Management 1801 'Vol. 2 3.X.1 Note Program Item Item* Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program ASME Section 11.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program ASME Section ll.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program SBK-L-1715 5 I Enclosure 2/ Page 90 U.S. Nuclear Regulatory Commission , '" I :, Component Type I ,,. Function "' CNT-CS-Stainless Steel Fuel Transfer Tube Structural Bellows Exposed to Air Pressure with Borated Water Barrier Leakage CNT-CS-Stainless Steel Fuel Transfer Tube Expansion I Bellows Exposed to Air Separation Indoor Uncontrolled CNT-CS-Stainless Steel Structural Fuel Transfer Tube Bellows Exposed to Air Pressure Indoor Uncontrolled Barrier CNT-CS-Stainless Steel Fuel Transfer Tube Structural Exposed to Air with Pressure Borated Water Leakage Barrier :I ,1*,1,,: ,I, l .. w . . . . 11:-1 Material, '1!11 :l:.::!11 I Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation I Environment Aging Effect Requiring Management Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete Air Indoor Uncontrolled Cracking (External) Air Indoor Uncontrolled Cracking (External) Nooe Air w/Borated Reduction in structural capacity Water Leakage directly. Indirectly due to (External) expansion and cracking of concrete " ' 11 I I: 11"1111' II 'ii ":. ,:,11 :1*'1:1 ,'l'I ', Ii IJ}ging i I l ''. 1w11Table i: ,1JI ;!:1 -11111::*' :i,;  "1 1l1ao'111vo1I. 2 Note1*,: Progr,aT ' II ' Item Item' .1:1: 1'1 '111'1;:*!:1!! Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program ASME Section XI, Subsection ll.A3-2 3.5.1-10 A IWE Program (C-15) ASME Section ll.A3-2 XI, Subsection (C-15) 3.5.1-10 A IWE Program Nooe Structures Monitoring Program, lll.B2-9 Building (TP-4) 3.5.1-59 A, 520 Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 91 U.S. Nuclear Regulatory Commission Component Type CNT-CS-Stainless Steel Fuel Transfer Tube Exposed to Air with Borated Water Leakage CNT-CS-Stainless Steel Fuel Transfer Tube Exposed to Air Indoor Uncontrolled CNT-CS-Stainless Steel Fuel Transfer Tube Exposed to Air Indoor Uncontrolled CNT-CS-Thermal Insulation Stainless Steel Jacketing in Air with Borated Water Leakage Intended Function Structural Support Structural Pressure Barrier Structural Support Structural Support Material Stainless Steel Stainless Steel Stainless Steel Stainless Steel CNT-CS-Reinforced Concrete Exposed to Raw Water Missile Barrier I Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation .. ' 1'f1 1**' 1:1." Environment :11 ;j.' if, . Aging ,Effect Requiring 1 ' *1 ' *11 111* 111 1Mariagement i: , ,, 11:1 :1',''I! <I; Air w/Borated Water Leakage (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air w/Borated Water Leakage Raw Water (External) Nooe Reduction in structural capacity directly. Indirectly due to expansion and cracking of concrete Cracking Cracking Nooe Reduction in structural capacity directly. Indirectly due to expansion and cracking of concrete Cracking due to expansion/ reaction with aggregates Aging Management Program Nooe Structures Monitoring Program, Building Deformation Monitoring Program ASME Section XI, Subsection !WE Program ASME Section XI, Subsection !WE Program Nooe Structures Monitoring Program, Building Deformation Monitoring Program ASME Section XI, Subsection IWL Program Alkali-Silica Reaction (ASR) Monitoring ProQram NU REG 1801 Vol. 2 lll.B2-9 (TP-4) ll.A3-2 (C-15) ll.A3-2 (C-15) lll.B2-9 (TP-4) ll.A1-3 (C-04) Table 3.X.1 Item Note 3.5.1-59 I A, 520 3.5.1-10 I A 3.5.1-10 I A 3.5.1-59 3.5.1-15 A, 520 A E, 517 519 SBK-L-17155 I Enclosure 2/ Page 92 U.S. Nuclear Regulatory Commission Intended Component Function CNT-CS-Reinforced Shelter, Concrete Exposed to Raw Protection Water CNT-CS-Reinforced Structural Concrete Exposed to Raw Pressure Water Barrier CNT-CS-Reinforced Structural Concrete Exposed to Raw Support Water Material Concrete Concrete Concrete Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation ii ,!:i::l!,.,liJ* I '. Aging Effect Requiring I I I ' : I : ' I Environment ,, I Management ., 'I' ill I' Raw Water Cracking due to expansion/ (External) reaction with aggregates Raw Water Cracking due to expansion/ (External) reaction with aggregates Raw Water Cracking due to expansion/ (External) reaction with aggregates I* I
+* 1:i'11:1r1I Aging NU REG Table ;:1"':11::1:: Management 1801 Vol. 2 3.X.1
+* Note :'HI Program Item Item . 1:1 '''i'I Building Deformation Monitoring Program ASME Section XI, Subsection IWL Program A Alkali-Silica Reaction (ASR) ll.A1-3 E, 517 Monitoring 3.5.1-15 Program (C-04) Building E, 519 Deformation Monitoring Program ASME Section XI, Subsection A IWL Program Alkali-Silica Reaction (ASR) ll.A1-3 Monitoring 3.5.1-15 Program (C-04) Building E, 517 Deformation E, 519 Monitoring Proaram ASME Section A XI, Subsection IWL Program ll.A1-3 3.5.1-15 (C-04) Alkali-Silica Reaction (ASR) E, 517 SBK-L-17155 I Enclosure 2/ Page 93 U.S. Nuclear Regulatory Commission :i*i 'i*I :h *1:1:;:111 Intended 1 Component Type. Function I:! ':i Standard Notes ' :ij: Material Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation I! 'i'i!ii:jtl'll'' 111 '':lllt1 :I:' l'i 'II i'!,, Aging Effect Requiring H Environment Management '!:.:i:'.!'.l:;;i:1:::. ' Table 3.5.2-2 Containment Structures Summary of Aging Management Evaluation Note Description Ii', ,, 'j"I . 11r1' II ' Ill 11 'II 'Aging H li!:111 11:1111NUREGli1,:' I ''iii ,:1*1 ***:'(I I :. *1 1' :*'*'!'I' Managem,ent '1,1
+* 118011Yio1. 2, Program 1*11tem Monitoring Program Building Deformation Monitoring Program 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. i:llhable1 I 1.,3:x.1 l1 II
+* Item 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. 1:: 111 Ill di I Note. . J, *Ir r* I ' I 1 1ll':.,;1:li,'I E, 519 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.
+SBK-L-17155 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&deg;C (<140&deg; 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 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 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 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 95 U.S. Nuclear Regulatory Commission Component Type Intended Function MYS -Aluminum STATION Structural BLACKOUT STRUCTURES Support Exposed to Weather MYS -Aluminum STATION Structural BLACKOUT STRUCTURES Support Exposed to Weather MYS -Carbon Steel CONTROL ROOM MAKEUP Structural AIR INTAKE STRUCTURE Support Air Indoor Uncontrolled MYS -Carbon Steel CONTROL ROOM MAKEUP Structural AIR INTAKE STRUCTURE Support Exposed to Weather MYS -Carbon Steel Door ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Carbon Steel Door ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring Material Environment Management Air Outdoor Aluminum (External) Crack Initiation and Growth Air Outdoor Aluminum Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Structures 111.82-7 Monitoring 3.5.1-50 H, 514 Program (Tp-6) Structures 111.82-7 Monitoring 3.5.1-50 A Program (TP-6) Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11)
+SBK-L-17155 I Enclosure 2/ Page 96 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Carbon Steel Door STATION BLACKOUT Structural STRUCTURES Air Indoor Support Uncontrolled MYS -Carbon Steel Door STATION BLACKOUT Structural STRUCTURES Exposed to Support Weather MYS -Carbon Steel ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Carbon Steel ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather MYS -Carbon Steel NON SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Air Indoor Uncontrolled SAFETY RELATED Structural ELECTRICAL MANHOLES Support Exposed to Weather Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation *I *! :i:w 1 * )I; I Requiring :I: Material Environment , 1:1: 11 I II *.I ,, l'i
+* Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Aging NU REG Table Mar.iagement . ,1801 Vol. 2 F 11 3.X.1 Note ' , 'Item*'* ' Item' **** "I *I Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures Monitoring lll.A3-12 3.5.1-25 A (T-11) Program Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures 111.A3-12 Monitoring 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11)
+SBK-L-17155 I Enclosure 2/ Page 97 U.S. Nuclear Regulatory Commission Component Type Intended Function MYS -Carbon Steel SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Air Indoor Uncontrolled MYS -Carbon Steel SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Exposed to Weather MYS -Carbon Steel SERVICE WATER ACCESS Structural VAULT Air Indoor Support Uncontrolled MYS -Carbon Steel STATION BLACKOUT Structural STRUCTURES Air Indoor Support Uncontrolled MYS -Carbon Steel STATION BLACKOUT Shelter, STRUCTURES Exposed to Protection Weather MYS -Carbon Steel STATION BLACKOUT Structural STRUCTURES Exposed to Support Weather Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ' . 1*1 Aging Effect Requiring Material Environment 1" Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Outdoor Steel (External) Loss of Material ' :1:11:'1 Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note',., Program *' Item Item ... , .. Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures Monitoring lll.A3-12 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11)
+SBK-L-17155 I Enclosure 2/ Page 98 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Air Support Indoor Uncontrolled MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Air Support Indoor Uncontrolled MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Air Support Indoor Uncontrolled MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Below Support Grade MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Below Support Grade Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ;/j1: :I: 1 '*1*, !I: 111'J11ili . l* 1 :r Material Environment Aging Effect Requiring '11
+* Management Air Indoor Cracking, Loss of Bond, Concrete Uncontrolled Loss of Material (Spalling, (External) Scaling) Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss Concrete of Material (Spalling, (External) Scaling) Cracking, Loss of Bond, Ground Water/Soil Loss of Material (Spalling, Concrete (External) Scaling) Ground Water/Soil Concrete Expansion and Cracking (External) ,1 Aging*. NU REG 1 Table * 'Managen:ient 1801 Vol. 2 3:X.1 Note Program Item Item Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Program Structures lll.A3-10 Monitoring 3.5.1-24 A (T-06) Program Structures lll.A3-4 Monitoring 3.5.1-31 A (T-05) Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 3.5.1-27 A, E, Monitoring (T-03) 517, 519 Program & Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 99 U.S. Nuclear Regulatory Commission ' Intended Component Type Function Ill. I,',, MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Below Support Grade MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Below Support Grade MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Below Support Grade MYS -Concrete CONTROL ROOM MAKEUP AIR INTAKE STRUCTURE Missile Barrier Exposed to Weather MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Support Exposed to Weather MYS -Concrete CONTROL ROOM MAKEUP AIR Missile Barrier INTAKE STRUCTURE Exposed to Weather Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ,i.,1:1 . n , , i'I '*' I.Ii/Aging Material Environment 11111:1 11:1 l,1[Jl )1:1 1 ifr , II '** " ,.,:1:i,1l:i, 1:1 :IJ :1:1 Increase in Porosity and Ground Water/Soil Permeability, Cracking, Loss Concrete (External) of Material (Spalling, Scaling) Ground Water/Soil Increase in Porosity and Concrete (External) Permeability, Loss of Strength Ground Water/Soil Concrete (External) Loss of Material, Cracking Air Outdoor Cracking, Loss of Bond, Concrete (External) Loss of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Concrete (External) Loss of Material (Spalling, Scaling) Concrete Air Outdoor (External) Expansion and Cracking Aging NUREG Table 1'11 Management 1801 Vol. 2 , :*13.X.1 Note 11' 11 1111* 111lil'1'lteni,ll, :111:i ,I fil,j lteryt1,tll'i Iii ,,1 *i** 111 *1 '.,: **1+ *:I Structures 111.A3-5 Monitoring 3.5.1-31 A Program (T-07) Structures lll.A3-7 Monitoring 3,5.1-32 A, 509 Program (T-02) Structures 111.A3-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitorinq SBK-L-17155 I Enclosure 2/ Page 100 U.S. Nuclear Regulatory Commission i'l":I ' l:i Intended Component Type Function MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Support Exposed to Weather MYS -Concrete CONTROL ROOM MAKEUP AIR Missile Barrier INTAKE STRUCTURE Exposed to Weather MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Support Exposed to Weather MYS -Concrete CONTROL ROOM MAKEUP AIR INTAKE STRUCTURE Missile Barrier Exposed to Weather i'),1 '1:1 Ir Material Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring ' Environment Management 1il1iil 1!1'1.: 11:1J''!:i:' "' "'"''' lil'*!I' * '' I Air Outdoor Expansion and Cracking (External) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking ., '* Table' ' l'!J l:!!:!,1 11.i.*:*:f:: I Aging NU REG i''ll Management 1801 Vol. 2 3.X.1 Note111 , Program Item I.tern ,, :1 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-24 A (T-06) Program Structures Monitoring lll.A3-10 3.5.1-24 A (T-06) Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program SBK-L-17155 I Enclosure 2/ Page 101 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete CONTROL ROOM MAKEUP AIR Structural INTAKE STRUCTURE Support Exposed to Weather MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Fire Barrier TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Fire Barrier TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Fire Barrier TANK Air Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation 1: ,1. '* Aging Effect Requiring Environment Management Air Outdoor (External) Loss of Material, Cracking Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Uncontrolled Loss of Material (Spalling, (External) Scaling) Air Indoor Cracking, Loss of Bond, Uncontrolled Loss of Material (Spalling, (External) Scaling) Air Indoor Concrete Cracking and Uncontrolled (External) Spalling I 'I' 1* I 'I* *:1:1* 1:' '1, NUREG1' :I 1Agjng :1: Tablet ,1: Management
+* 1,1801 Vol'. 2 '3.X.1 Note Program Item item Structures Monitoring 111.A3-6 (T-01) 3.5. 1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures Monitoring lll.A3-9 (T-04) 3.5. 1-23 A Program Structures Monitoring lll.A3-9 (T-04) 3.5.1-23 A Program Fire Protection Vll.G-28 Program (A-90) 3.3. 1-65 A SBK-L-17155 I Enclosure 2/ Page 102 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Fire Barrier TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Fire Barrier TANK Air Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation . Environment Aging Effect Requiring Management Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) 'l'I I I ' FAging NU REG Table .'' Management 1801 Vol. 2 3.X.1 Note Program Item Item Fire Protection Vll.G-28 Program (A-90) 3.3. 1-65 A Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 A, E, Program & (T-03) 3.5.1-27 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 A, E, Program & (T-03) 3.5. 1-27 517, 519 Building Deformation Monitoring Program Fire Protection lll.A3-10 Program (T-06) 3.5. 1-24 E, 513 SBK-L-17155 I Enclosure 2/ Page 103 U.S. Nuclear Regulatory Commission Component Type Intended ''' Function' MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Structural TANK Air Indoor Support Uncontrolled MYS -Concrete ENCLOSURE FOR Fire Barrier CONDENSATE STORAGE TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Air Indoor Uncontrolled MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Below Grade MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation I ' 'l'!'I: I <'''I l:ji ,:i:' ''I'* ,1;!11''1f1:':!il Environment
+* Aging 1
+* I Management
+* 11 ', ;* ,1 :rl:1*1 Increase in Porosity and Air Indoor Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of Material (Spalling, (External) Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss of Material (Spalling, (External) Scaling) Cracking, Loss of Bond, Ground Water/Soil (External) Loss of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) I ;1,l!'FA '. ''I' . rlilt NUREd1l:11'w 'I' ''!*I I * ,,jll' "I' I '*I". *I l:1:i }'4ote *** ,Managemer:it 2111. , 1: 1 1'1, 111 1'11,11'+11'11'' ,,. 'Hill . 'ltem'I;;. . "i ' ),. 1* 1* ' *:1* I .L,.I*, 1:1!,f,l:.:!1, ', ,* "'I I *:I* 11fili'' Fire Protection lll.A3-10 3.5. 1-24 E, 513 Program (T-06) Structures Monitoring lll.A3-10 3.5. 1-24 A (T-06) Program Structures Monitoring lll.A3-10 3.5. 1-24 A (T-06) Program Structures lll.A3-4 Monitoring (T-05) 3.5. 1-31 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5. 1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 104 U.S. Nuclear Regulatory Commission Component Type Intended Function MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Below Grade MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Below Grade MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Below Grade MYS -Concrete ENCLOSURE FOR CONDENSATE STORAGE Missile Barrier TANK Exposed to Weather MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather MYS -Concrete ENCLOSURE FOR Missile Barrier CONDENSATE STORAGE TANK Exposed to Weather Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation l*I *'* '' ,I, Aging Effect Requiring Environment Management Increase in Porosity and Ground Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Water/Soil Increase in Porosity and Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Air Outdoor Cracking, Loss of Bond, Loss of Material (Spalling, (External) Scaling) Air Outdoor Cracking, Loss of Bond, Loss of Material (Spalling, (External) Scaling) Air Outdoor (External) Expansion and Cracking Aging* NU REG' Table I: Management 1801 Vol. 2 3.X:1' Note Program Item Item Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring 3.5. 1-32 A, 509 (T-02) Program Structures lll.A3-6 Monitoring 3.5. 1-26 A Program (T-01) Structures 111.A3-9 Monitoring 3.5. 1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5. 1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5. 1-27 517, 519 Program & Building Deformation Monitorinq SBK-L-17155 I Enclosure 2/ Page 105 U.S. Nuclear Regulatory Commission I 'I ,,, Intended Component Type Function MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather MYS -Concrete ENCLOSURE FOR Missile Barrier CONDENSATE STORAGE TANK Exposed to Weather MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather MYS -Concrete ENCLOSURE FOR Missile Barrier CONDENSATE STORAGE TANK Exposed to Weather :j' Materia1i'I ii , Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring , Environment " Mana,gement ' ii! ni 11: Air Outdoor Expansion and Cracking (External) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) : :, I l*I;! NU REG Table 1'1'f''I:' Aging '"'Ti Management 1801 Vol. 2 3.X.1 Note1',:: ,: Program Item Item ,*,i:,: Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-24 A (T-06) Program Structures Monitoring lll.A3-10 3.5.1-24 A Program (T-06) Stru'ctu res Monitoring lll.A3-6 3.5.1-26 A (T-01) Program SBK-L-17155 I Enclosure 21 Page 106 U.S. Nuclear Regulatory Commission '.;, l'i' .' 1.ntended 1 Component I ',Function MYS -Concrete ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather MYS -Concrete Masonry Unit (CMU) STATION BLACKOUT Fire Barrier STRUCTURES Exposed to Weather MYS -Concrete Masonry Unit (CMU) STATION BLACKOUT Structural STRUCTURES Exposed to Support Weather MYS -Concrete Masonry Unit (CMU) STATION BLACKOUT Fire Barrier STRUCTURES Exposed to Weather MYS -Concrete Masonry Unit (CMU) STATION BLACKOUT Structural STRUCTURES Exposed to Support Weather MYS -Concrete NON SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Air Indoor Uncontrolled Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effe.ct Requiring Material Environment Management . I i ' Concrete Air Outdoor Loss of Material, Cracking (External) Concrete Air Outdoor Cracking Block (External) Concrete Air Outdoor Cracking BLOCK (External) Concrete Air Outdoor Cracking Block (External) Concrete Air Outdoor Cracking BLOCK (External) Air Indoor Cracking, Loss of Bond, Concrete Uncontrolled Loss of Material (Spalling, (External) Scaling) ' " '"*l'J'' ,' ,: 111*.111'1.1.1.JiT ,:i:i:,:.: 1:lf'l11NUREG Table '* 1'u"' ]Y'*. n1:,lf1 , *)Aging i<:: Management I . 1801 Vol. 2 3.X.1 Note"'i'. Program Item Item ';i:: Structures Monitoring 111.A3-6 3.5. 1-26 A (T-01) Program Fire Protection lll.A3-11 3.5.1-43 E, 513 Program (T-12) Fire Protection lll.A3-11 3.5.1-43 E,513 Program (T-12) Structures Monitoring lll.A3-11 3.5.1-43 A, 511 (T-12) Program Structures Monitoring lll.A3-11 3.5.1-43 A, 511 (T-12) Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program SBK-L-17155 I Enclosure 2/ Page 107 U.S. Nuclear Regulatory Commission Intended Component Ty,pe Function MYS -Concrete NON SAFETY RELATED ELECTRICAL DUCT Structural BANKS/MANHOLES Air Support Indoor Uncontrolled MYS -Concrete NON SAFETY RELATED ELECTRICAL DUCT Structural BANKS/MANHOLES Air Support Indoor Uncontrolled MYS -Concrete NON SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Below Grade MYS -Concrete NON SAFETY RELATED ELECTRICAL DUCT Structural BANKS/MANHOLES Below Support Grade MYS -Concrete NON SAFETY RELATED ELECTRICAL DUCT Structural BANKS/MANHOLES Below Support Grade MYS -Concrete NON SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Below Grade Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ' Ir I IJ 1;fi '''i"1111 ''J:ij\1111+1,, Agirig Effect Requiring .Material Management ;,J;I: ' I l'i Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Increase in Porosity and Air Indoor Concrete Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Water/Soil Cracking, Loss of Bond, Concrete (External) Loss of Material (Spalling, Scaling) Concrete Ground Water/Soil Expansion and Cracking (External) Increase in Porosity and Concrete Ground Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Water/Soil Increase in Porosity and Concrete (External) Permeability, Loss of Strength iwi,I'' . , ''''1 i 11:1: 'l'I ','":I: Wrable'r 'j, :11!, I I J}ging I.: ii'' ;j: : 1 1r: NURE!3* !Ii Management ' r1801Vol.2* 3.X.1 Note Program Item Item ., . r Structures Monitoring Program, Alkali-Silica Reaction lll.A3-2 3.5. 1-27 A, E, (ASR) (T-03) 517 Monitoring Program Structures Monitoring IIl.A3-10 3.5.1-24 A Program (T-06) Structures lll.A3-4 Monitoring (T-05) 3.5. 1-31 A Program Structures Monitoring Program, Alkali-Silica Reaction IIl.A3-2 3.5. 1-27 A, E, (ASR) (T-03) 517 Monitoring Program Structures Monitoring lll.A3-5 3.5. 1-31 A Program (T-07) Structures lll.A3-7 Monitoring (T-02) 3.5. 1-32 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 108 U.S. Nuclear Regulatory Commission Cpmponent Type Intended Function MYS -Concrete NON SAFETY RELATED Structural ELECTRICAL DUCT BANKS/MANHOLES Below Support Grade MYS -Concrete NON SAFETY RELATED Structural MANHOLES Exposed to Support Weather MYS -Concrete NON SAFETY RELATED Structural MANHOLES Exposed to Support Weather MYS -Concrete NON SAFETY RELATED Structural MANHOLES Exposed to Support Weather MYS -Concrete NON SAFETY RELATED Structural MANHOLES Exposed to Support Weather MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Air Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment ''i'I'" 1l'l1 Management 1:1.,,, '" l:i Ground Water/Soil (External) Loss of Material, Cracking Air Outdoor Cracking, Loss of Bond, Loss of Material (Spalling, (External) Scaling) Air Outdoor Expansion and Cracking (External) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Air Indoor Cracking, Loss of Bond, Uncontrolled Loss of Material (Spalling, (External) Scaling) Aging NU REG Table Management 1801 Vol. 2 1 Note* .. , Program .Item 1,: ' Item 1.* Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures 111.A3-9 Monitoring 3.5.1-23 (T-04) A Program Structures Monitoring Program, Alkali-lll.A3-2 Silica Reaction 3.5.1-27 A, E, (ASR) (T-03) 517 Monitoring Proqram Structures lll.A3-10 Monitoring 3.5.1-24 A (T-06) Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures Monitoring lll.A3-9 3.5.1-23 (T-04) A Program SBK-L-17155 I Enclosure 2/ Page 109 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Air Indoor Uncontrolled MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Air Indoor Uncontrolled MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Below Grade MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Below Grade Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation +Fl"" 111!1 A'gi'ng Effect Requiring Material Environment Management Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Concrete Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Cracking, Loss of Bond, Ground Water/Soil Concrete (External) Loss of Material (Spalling, Scaling) Concrete Ground Water/Soil Expansion and Cracking (External) 1, Aging 1 .. 'I *+ ,1 111 Management 1
+* 18011Vol. 2 3.X.1 Note , Program *1 *Item Item ,*1:11 Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring 111.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring 111.A3-10 3.5. 1-24 A Program (T-06) Structures 111.A3-4 Monitoring (T-05) 3.5. 1-31 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5. 1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 110 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Below Grade MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Below Grade MYS -Concrete SAFETY RELATED ELECTRICAL Structural DUCT BANKS/MANHOLES Support Below Grade MYS -Concrete SAFETY RELATED MANHOLES Missile Barrier Exposed to Weather MYS -Concrete SAFETY Structural RELATED MANHOLES Support Exposed to Weather MYS -Concrete SAFETY RELATED MANHOLES Missile Barrier Exposed to Weather Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring , Environment Management Increase in Porosity and Ground Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Increase in Porosity and Ground Water/Soil (External) Permeability, Loss of Strength Ground Water/Soil (External) Loss of Material, Cracking Air Outdoor Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) ,f Aging NU REG Table 1ITll *N.ole'I: I Management' 1801 Vol. 2 3.X.1 Program Item Item Structures Monitoring lll.A3-5 3.5.1-31 A (T-07) Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 3.5.1-27 A, E, Monitoring (T-03) 517, 519 Program & Building Deformation Monitoring SBK-L-17155 I Enclosure 2/ Page 111 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete SAFETY RELATED MANHOLES Structural Exposed to Weather Support MYS -Concrete SAFETY RELATED MANHOLES Missile Barrier Exposed to Weather MYS -Concrete SAFETY RELATED MANHOLES Structural Exposed to Weather Support MYS -Concrete SAFETY RELATED MANHOLES Missile Barrier Exposed to Weather Material Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor Expansion and Cracking (External) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-24 A Program (T-06) Structures Monitoring lll.A3-10 3.5.1-24 A Program (T-06) Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program SBK-L-17155 I Enclosure 2/ Page 112 U.S. Nuclear Regulatory Commission Intended Type Function MYS -Concrete SAFETY Structural RELATED MANHOLES Support Exposed to Weather MYS -Concrete SERVICE Structural WATER ACCESS VAULT Air Support Indoor Uncontrolled MYS -Concrete SERVICE WATER ACCESS VAULT Air Structural Support Indoor Uncontrolled MYS -Concrete SERVICE WATER ACCESS VAULT Air Structural Indoor Uncontrolled Support MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment 'I* '*:1:'1!1 Management Air Outdoor (External) Loss of Material, Cracking Air Indoor Cracking, Loss of Bond, Uncontrolled Loss of Material (Spalling, (External) Scaling) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Water/Soil Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) Aging NU REG Table II Management 1801 Vol. 2 3.X.1 ,. Note Program Item Item Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring 111.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-10 3.5.1-24 A Program (T-06) Structures 111.A3-4 Monitoring (T-05) 3.5.1-31 A Program SBK-L-17155 I Enclosure 2/ Page 113 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Below Grade MYS -Concrete SERVICE WATER ACCESS VAULT Structural Below Grade Support MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Below Grade MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Below Grade MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Exposed to Raw Water Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation '' :1; :1: Environment Aging Effect Requiring ' Management Ground Water/Soil (External) Expansion and Cracking Increase in Porosity and Ground Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Water/Soil Increase in Porosity and (External) Permeability, Loss of Strength Ground Water/Soil (External) Loss of Material, Cracking Raw Water Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) 'I. , '',,, , 'NUREG 1Table *I'' 18011\(ol. 2 3.X.1 Note Program Item Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A,E517, Monitoring (T-03) 3.5. 1-27 519 Program & Building Deformation Monitoring Proqram Structures Monitoring lll.A3-5 3.5. 1-31 A Program (T-07) Structures lll.A3-7 Monitoring (T-02) 3.5. 1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 114 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete SERVICE Structural WATER ACCESS VAULT Support Exposed to Raw Water MYS -Concrete STATION Structural BLACKOUT STRUCTURES Support Below Grade MYS -Concrete STATION BLACKOUT STRUCTURES Structural Below Grade Support MYS -Concrete STATION BLACKOUT STRUCTURES Structural Below Grade Support Material Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation II I Aging Effect Requiring Environment Management Raw Water (External) Expansion and Cracking Ground Water/Soil Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) Increase in Porosity and Ground Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item r1 Item Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Proqram Structures 111.A3-4 Monitoring (T-05) 3.5.1-31 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring lll.A3-5 3.5.1-31 A Program (T-07) ---
+SBK-L-17155 I Enclosure 2/ Page 115 U.S. Nuclear Regulatory Commission Intended Component Type *Function MYS -Concrete STATION Structural BLACKOUT STRUCTURES Support Below Grade MYS -Concrete STATION Structural BLACKOUT STRUCTURES Support Below Grade MYS -Concrete STATION Structural BLACKOUT STRUCTURES Support Exposed to Weather MYS -Concrete STATION BLACKOUT STRUCTURES Structural Exposed to Weather Support MYS -Concrete STATION BLACKOUT STRUCTURES Structural Exposed to Weather Support MYS -Concrete STATION Structural BLACKOUT STRUCTURES Support Exposed to Weather Material 1* Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ':l"!i' I r I h1.';i:I:!, 11 I'. 1<'lill' ill1 I Aging Effect Requiring Environment . ) .I. Managemeht1 : 'i'l'I <:i r, t l'j T I ; , 1 . ,f, .' ,,i 'TI i" I Ground Water/Soil Increase in Porosity and (External) Permeability, Loss of Strength Ground Water/Soil (External) Loss of Material, Cracking Air Outdoor Cracking, Loss of Bond, (External) Loss of Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Increase in Porosity and Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking 1,n'jil 111Aging {*' i''1.11 1!'i1*11 INtJREGl' I 1111:* . t I. , .. ,, . ' *, 11'*1
+* Table ' I : I ' I : I , * * '
+* I' 1181011i110L 2. '* 1 *" Note . ' ' "'" 11 l 'fl' Item .,. I , . :11 111 Program iii ii i', *.iii! Item' '!',: I ,j.
+* Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures Monitoring Program, Alkali-Silica lll.A3-2 3.5.1-27 A, E, Reaction (ASR) (T-03) 517 Monitoring Program Structures Monitoring lll.A3-10 3.5.1-24 A Program (T-06) Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program SBK-L-17155/Enclosure2/Page 116 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete Sump CONTROL ROOM MAKEUP Structural AIR INTAKE STRUCTURE Support Exposed to Raw Water MYS -Concrete Sump CONTROL ROOM MAKEUP Structural AIR INTAKE STRUCTURE Support Exposed to Raw Water MYS -Concrete Sump NON SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Exposed to Raw Water MYS -Concrete Sump NON SAFETY RELATED ELECTRICAL DUCT Structural BANKS/MANHOLES Support Exposed to Raw Water MYS -Concrete Sump SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Exposed to Raw Water Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation ' Aging Effect Requiring ,1 Material Environment Management Cracking, Loss of Bond, Raw Water Concrete (External) Loss of Material (Spalling, Scaling) Concrete Raw Water Expansion and Cracking (External) Raw Water Cracking, Loss of Bond, Concrete (External) Loss of Material (Spalling, Scaling) Concrete Raw Water Expansion and Cracking (External) Raw Water Cracking, Loss of Bond, Concrete (External) Loss of Material (Spalling, Scaling) . Aging * *:; NUREG ' Table T '' Management ,, 1801 Vol. 2 3.X.1 Note., Program Item Item Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A, 509 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A, 509 Program Structures Monitoring Program, Alkali-Silica Reaction lll.A3-2 3.5.1-27 A, E, (ASR) (T-03) 517 Monitoring Program Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 117 U.S. Nuclear Regulatory Commission Intended Component Type Function MYS -Concrete Sump SAFETY RELATED Structural ELECTRICAL DUCT Support BANKS/MANHOLES Exposed to Raw Water MYS -EPDM Roof ENCLOSURE FOR Shelter, CONDENSATE STORAGE Protection TANK Exposed to Weather MYS -EPDM Roof STATION Shelter, BLACKOUT STRUCTURES Protection Exposed to Weather MYS -Penetration Seal ENCLOSURE FOR Shelter, CONDENSATE STORAGE Protection TANK Exposed to Weather MYS -Seismic Isolation Joint SAFETY RELATED Expansion/ ELECTRICAL DUCT BANKS/MANHOLES Air Separation Indoor Uncontrolled Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Aging Effect Requiring Material Environment Management Raw Water Concrete (External) Expansion and Cracking Separation, Environmental Roofing Air Outdoor Degradation, Water In-(External) Leakage Air Outdoor Separation, Environmental Roofing (External) Degradation, Water In-Leakage Increased Hardness and Elastomer Air Outdoor Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness and Elastomer Uncontrolled Shrinkage and Loss of (External) Strength Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program It.em Item ''I' Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Proqram Structures Monitoring Program, Building lll.A6-12 3.5.1-44 A, 505, Deformation (TP-7) 520 Monitoring Program Structures lll.A6-12 Monitoring (TP-7) 3.5.1-44 A, 505, Program Structures Monitoring Vll.G-2 3.3.1-61 E, 515 Program (A-20) Structures Vll.G-1 Monitoring 3.3.1-61 E, 515 Program (A-19)
+SBK-L-17155 I Enclosure 2/ Page 118 U.S. Nuclear Regulatory Commission ,Intended Component Type,. I*: .. , Function ''':1' 1*1 " MYS -Stainless Steel ENCLOSURE FOR Structural CONDENSATE STORAGE Support TANK Exposed to Weather Standard Notes 11 1: Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation " ri'.', 1 11:1 i:1' *11 1*, \I:!** Agihg Effect Requiring Material Environment Management Stainless Air Outdoor Loss of Material Steel (External) Table 3.5.2-4 Miscellaneous Yard Structures Summary of Aging Management Evaluation Note Description , 1, , *.* 111r1: 11 illil1t.JuFi.EG I '' Management 1801 Vol. 2 Program Item Structures Monitoring 111.82-7 (TP-6) Program 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. Table 3.X.1 Item 3.5.1-50 D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. 1,.: .i, 1:11111::J 111 1:1 r Note11'':.,.i A 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&deg;C (<140&deg; F); water chemistry and temperature will be maintained by the Water Chemistry Program.
+SBK-L-17155 /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 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. 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 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 120 U.S. Nuclear Regulatory Commission I*; I' Intended ,*I Component Type ,1.I' Function " PST -(Structural) Fire Proofing -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -(Structural) Fire Proofing -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -(Structural) Fire Proofing -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -(Structural) Fire Proofing -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Built-Up Roofing -COG-Shelter, Exposed to Air Outdoor Protection PST -Built-Up Roofing -EFP-Shelter, Exposed to Air Outdoor Protection Material Non-Metallic Fire-Proofing Non-Metallic Fire-Proofing Non-Metallic Fire-Proofing Non-Metallic Fire-Proofing Roofing Roofing Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation , I i ' 1 11: ifr'*'* iii'.,,,,, ' .. :, l1iil'Agjng Environmerit, ,.i:J, ,11'l'ill'1'i:Jlil1Management I'**** I'll' *fl t*:1:*]!!1'j:!1!" l'l'l'I' ,, .. ij* .11:1 .IJ;l,H!,:ii*1ll 1*l*1u*.::* *i:i *;':'':1:1:. ,!:11*'. '.i:l*1 :':1:1:' I '''l:':'I Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage ,,Aging , ...*. Table NUREG 1801. ' . Management .. , w vo1n:ltemji'.': 111*13.x;1 Note *''"I' **
+* T *Ir .1:11111111 i;;1:111: l!I ,* 1:11.*1111::1 n 11fr1:1ii:;i:1.th1I !;:*: Item 1;<i :';T I:*: ;:t 1:** Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 C, 506 Structures Vll.G-29 Monitoring (A-91) 3.3.1-67 C, 506 Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 C, 506 Structures Vll.G-29 Monitoring (A-91) 3.3.1-67 C, 506 Program Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Program Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505,E, (TP-7) 520 Building Deformation Monitoring SBK-L-17155 I Enclosure 2/ Page 121 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Built-Up Roofing -FSB-Shelter, Exposed to Air Outdoor Protection PST -Built-Up Roofing -PAB-Shelter, Exposed to Air Outdoor Protection PST -Built-Up Roofing -PCEW-Shelter, Exposed to Air Outdoor Protection PST -Built-Up Roofing -PHA-Shelter, Exposed to Air Outdoor Protection Material Roofing Roofing Roofing Roofing Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation " Aging Effect Requiring Environment Management Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Aging Table NUREG 1801 Management Vol. 2 Item 3.X.1 Note Program Item Program Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Program Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Proaram Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E,520 Deformation Monitoring Program Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 122 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Built-Up Roofing -TFA-Shelter, Exposed to Air Outdoor Protection PST -Built-Up Roofing -WPS-Shelter, Exposed to Air Outdoor Protection PST -Carbon Steel -COG-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -COG-Structural Exposed to Air Outdoor Support PST -Carbon Steel -CEHMS-Structural Exposed to Air Outdoor Support PST -Carbon Steel Door -COG-Structural Exposed to Air Indoor Support Uncontrolled Material Roofing Roofing Steel Steel Steel Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Separation, Environmental Air Outdoor Degradation, Water In-(External) Leakage Air Indoor Uncontrolled Loss of Material (External) Air Outdoor (External) Loss of Material Air Outdoor (External) Loss of Material Air Indoor Uncontrolled Loss of Material (External) Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note 1 .' Program Item Structures Monitoring Program lll.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Proqram Structures Monitoring Program 111.A6-12 3.5.1-44 H, 505, Building (TP-7) E, 520 Deformation Monitoring Proqram Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A Program SBK-L-17155 I Enclosure 2/ Page 123 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Carbon Steel Door -COG-Structural Exposed to Air Outdoor Support PST -Carbon Steel Door -EFP-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel Door -EFP-Structural Exposed to Air Outdoor Support PST -Carbon Steel Door -FSB-HELB Exposed to Air Indoor Shielding Uncontrolled PST -Carbon Steel Door -FSB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel Door -FSB-Structural Exposed to Air Outdoor Support Material* Steel Steel Steel Steel Steel Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor (External) Loss of Material Air Indoor Uncontrolled Loss of Material (External) Air Outdoor (External) Loss of Material Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Outdoor (External) Loss of Material Aging NUREG 1801 Table ':1: t1: Management Vol. 2 Item 3.X.1 Note Program Item Structures lll.A1-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A5-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A5-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A5-12 Monitoring (T-11) 3.5.1-25 A, 503 Program SBK-L-17155 I Enclosure 21 Page 124 U.S. Nuclear Regulatory Commission I' I Intended 1, I Component Type Function ,, '1*T PST -Carbon Steel Door -FSB-HELB in Air with Borated Water Shielding Leakage PST -Carbon Steel Door -FSB-Structural in Air with Borated Water Support Leakage PST -Carbon Steel Door -PAB-HELB Exposed to Air Indoor Shielding Uncontrolled PST -Carbon Steel Door -PAB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel Door -PAB-Structural Exposed to Air Outdoor Support PST -Carbon Steel Door -PAB-HELB in Air with Borated Water Shielding Leakage Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' 1] 1,1 l.j , ,,1, , ,1:rl , Aging Effect Requiring Material 1' i*ll , 11'1 'Iii' Management " '''Jiii, I'll ':' ",:, '''1y1 I !*Ill I 1111111'1"11 I, li1'1 1111 ,,,, Air w/Borated Steel Water Leakage Loss of Material (External) Air w/Borated Steel Water Leakage Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air w/Borated Steel Water Leakage Loss of Material (External) Aging Table NUREG 1801 Management Vol. 2 Item:, 3.X.1 Note Program Jtem " '"r:!* Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Boric Acid 111.82-11 Program (T-25) 3.5.1-55 A SBK-L-17155 I Enclosure 2/ Page 125 U.S. Nuclear Regulatory Commission Component Type Intended Function PST -Carbon Steel Door -PAB-Structural in Air with Borated Water Support Leakage PST -Carbon Steel Door -HELB PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Carbon Steel Door -Structural PCEW-Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel Door -Structural PCEW-Exposed to Air Outdoor Support PST -Carbon Steel Door -WPB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel Door -WPB-Structural Exposed to Air Outdoor Support Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Material Environment Aging Effect Requiring Management Air w/Borated Steel Water Leakage Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Aging " Table i'I Management NUREG 1801 3.X.1 Note Program Vol. 2 Item Item Boric Acid 111.82-11 Program (T-25) 3.5.1-55 A Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures 111.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12
+* Monitoring (T-11) 3.5.1-25 A, 503 Program SBK-L-17155 I Enclosure 2/ Page 126 U.S. Nuclear Regulatory Commission Component Type Intended Function PST -Carbon Steel Door -WPB-Structural in Air with Borated Water Support Leakage PST -Carbon Steel -EFP-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -EFP-Shelter, Exposed to Air Outdoor Protection PST -Carbon Steel -EFP-Structural Exposed to Air Outdoor Support PST -Carbon Steel Fire Door -CDG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Carbon Steel Fire Door -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled Material Steel Steel Steel Steel Steel Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,:1* I* Environment Aging Effect Requiring Management Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Outdoor Loss of Material (External) Air Outdoor (External) Loss of Material Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Aging Table Management NUREG 1801 3.X.1 Note Program Vol. 2 Item Item Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures lll.A3-12 Monitoring (T-11) 3.5. 1-25 A, 503 Program Fire Protection Vll.G-3 Program (A-21) 3.3.1-63 A Fire Protection Vll.G-3 Program (A-21) 3.3.1-63 A SBK-L-17155 I Enclosure 2/ Page 127 U.S. Nuclear Regulatory Commission Component Type PST -Carbon Steel Fire Door -FSB-Exposed to Air Indoor Uncontrolled PST -Carbon Steel Fire Door -FSB-in Air with Borated Water Leakage PST -Carbon Steel Fire Door -PAB-Exposed to Air Indoor Uncontrolled PST -Carbon Steel Fire Door -PAB-in Air with Borated Water Leakage PST -Carbon Steel Fire Door -PCEW-Exposed to Air Indoor Uncontrolled PST -Carbon Steel Fire Door -WPB-Exposed to Air Indoor Uncontrolled Intended Function Fire Barrier Fire Barrier Fire Barrier Fire Barrier Fire Barrier Fire Barrier Material Steel Steel Steel Steel Steel Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 'II Environment '11 , ' 1"111 '1*1*11:,'' Table111 l'I 11n11 Ir j;i ,,, 1 '. Jl*li:11: ',, ' l'I 1: !i b.x.11:111 'I '1,; 1,,1,,li;girig pffect fl.equ,1.rin.g '1,1,,1 *Iii* 1,1vol'Y2]*1*t em l:!,11 Ii lil!11tem'111111, ',, r. , Managementill' 111 :1! , "11111 Program l:j:j' , *ti 1*i:l.1*1*'1*11l1111 , , * * 'i*i' {] 1 l!I: ' I ,, , i;1 Air Indoor Uncontrolled (External) Air w/Borated Water Leakage (External) Air Indoor Uncontrolled (External) Air w/Borated Water Leakage (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Loss of Material Loss of Material Loss of Material Loss of Material Loss of Material Loss of Material Fire Protection Program Boric Acid Program Fire Protection Program Boric Acid Program Fire Protection Program Fire Protection Program Vll.G-3 (A-21) lll.B2-11 (T-25) Vll.G-3 (A-21) lll.B2-11 (T-25) Vll.G-3 (A-21) Vll.G-3 (A-21) 3.3.1-63 A 3.5.1-55 A 3.3.1-63 A 3.5.1-55 A 3.3.1-63 A 3.3.1-63 A SBK-L-17155 I Enclosure 2/ Page 128 U.S. Nuclear Regulatory Commission I Intended Component Type I Function PST -Carbon Steel Fire Door -WPB-in Air with Borated Water Fire Barrier Leakage PST -Carbon Steel -FSB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -FSB-in Air Structural with Borated Water Leakage Support PST -Carbon Steel -PAB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -PAB-Structural Exposed to Air Outdoor Support PST -Carbon Steel -PAB-in Air Structural with Borated Water Leakage Support Material Steel Steel Steel Steel Steel Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation r . . *:r!!ll 1"'.ill Environment'!: I 'I' ' ' ' * "111: ' Management. " 111 I I* .&deg;1!11 11: /11'1 'I* *1il!l*lll: '11i::l'1!1ili11* *:1:1' Air w/Borated Water Leakage Loss of Materfal (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Outdoor (External) Loss of Material Air w/Borated Water Leakage Loss of Material (External) Aging, *:1: Table NUREG 1801 Management voi. 211tem : :1 3:X.1 11' Note * '*' ,': ;;j1tehi , '! I iii! ' ::i1:' \1: Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Structures lll.A5-12 Monitoring (T-11) 3.5.1-25 A Program Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A SBK-L-17155 I Enclosure 2/ Page 129 U.S. Nuclear Regulatory Commission ;11 Intended Component Type 'l1r 'Function *I* I I '*. ' PST -Carbon Steel -PCEW-Exposed to Air Indoor Flood Barrier Uncontrolled PST -Carbon Steel -PCEW-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -PCEW-Structural Exposed to Air Outdoor Support PST -Carbon Steel -PHA-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -PHA-Shelter, Exposed to Air Outdoor Protection PST -Carbon Steel -PHA-Structural Exposed to Air Outdoor Support Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Material Environment Management .*1, Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air Outdoor Steel (External) Loss of Material Aging, ' Table
+* I' ''I: 'I{ NUREG 1801 ' ... 'I Management Vol. 2 Item 3.X.1 Note1, 1 Program Item ' l 1 ':l: Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures 111.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program SBK-L-17155 I Enclosure 2/ Page 130 U.S. Nuclear Regulatory Commission ' Component Type " 'Intended Function PST -Carbon Steel -TFA-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -TFA-Shelter, Exposed to Air Outdoor Protection PST -Carbon Steel -TFA-Structural Exposed to Air Outdoor Support PST -Carbon Steel -TFA-in Air Structural with Borated Water Leakage Support PST -Carbon Steel -WPB-Structural Exposed to Air Indoor Support Uncontrolled PST -Carbon Steel -WPB-Shelter, Exposed to Air Outdoor Protection ' Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Material Environment Aging Effect Requiring Management Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel Loss of Material (External) Air Outdoor Steel (External) Loss of Material Air w/Borated Steel Water Leakage Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material Aging Table :11 Management NUREG 1801 .,. 3.X.1 Note Program Vol. 2 Item Item Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program Boric Acid 111.82-11 Program (T-25) 3.5.1-55 A Structures 111.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program SBK-L-17155 I Enclosure 2/ Page 131 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Carbon Steel -WPB-Structural Exposed to Air Outdoor Support PST -Carbon Steel -WPB-in Structural Air with Borated Water Leakage Support PST -Conduit Fire Wrap -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Conduit Fire Wrap -PAB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Conduit Fire Wrap -PAB-in Air with Borated Water Fire Barrier Leakage PST -Conduit Fire Wrap -WPB-Exposed to Air Indoor Fire Barrier Uncontrolled Material1 Steel Steel Aluminum Aluminum Aluminum Aluminum Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor (External) Loss of Material Air w/Borated Water Leakage Loss of Material (External) Air Indoor Nef\e Uncontrolled Deformation/reduction in (External) structural capacity Air Indoor Nef\e Uncontrolled Deformation/reduction in (External) structural capacity Air w/Borated Water Leakage Loss of Material (External)) Nef\e Air Indoor Deformation/reduction in Uncontrolled structural capacity (External) Aging 1:1 Table NUREG 1801 Management Vol. 2 Item I* 3.X.1 Note Program Item :*j*I Structures lll.A3-12 Monitoring (T-11) 3.5. 1-25 A, 503 Program Boric Acid lll.B2-11 Program (T-25) 3.5.1-55 A Nef\e Building lll.B2-4 Deformation (TP-8) 3.5. 1-58 A, E, 520 Monitoring Program Nef\e Building lll.B2-4 Deformation (TP-8) 3.5. 1-58 A, E, 520 Monitoring Program Boric Acid lll.B2-6 Program (TP-3) 3.5. 1-55 A Nef\e Building lll.B2-4 Deformation (TP-8) 3.5. 1-58 A, E, 520 Monitoring Program SBK-L-17155 I Enclosure 2/ Page 132 U.S. Nuclear Regulatory Commission Component Type PST -Conduit Fire Wrap -in Air with Borated Water Leakage PST -Elastomers Exposed to Air Indoor Uncontrolled PST -Elastomers Exposed to Air Indoor Uncontrolled PST -Elastomers Exposed to Air Outdoor PST -Elastomers Exposed to Air Outdoor PST -Elastomers Exposed to Air Outdoor Intended Function Fire Barrier Control Bldg Habitability Flood Barrier Expansion/ Separation Shelter, Protection Expansion/ Separation Material Aluminum Elastomer Elastomer Elastomer Elastomer Elastomer Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Air w/Borated Water Leakage (External)) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) 111 1:1+ ' *l'l'i'I . *I: .,, :I ilAging Effect'Requiring 1'* 1: Management 1:'; Loss of Material Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Aging Management Program Boric Acid Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program NUREG 1801 Vol. 2 Item lll.B2-6 (TP-3) Vll.G-1 (A-19) Vll.G-1 (A-19) Vll.G-2 (A-20) Vll.G-2 (A-20) Vll.G-2 (A-20) I Table 3.X.1 Item 3.5.1-55 3.3. 1-61 3.3. 1-61 3.3.1-61 3.3. 1-61 3.3.1-61 Note A E, 515 E, 515 E, 515 E, 515 E, 515 SBK-L-17155 I Enclosure 2/ Page 133 U.S. Nuclear Regulatory Commission Component Type PST -Elastomers Exposed to Air Outdoor PST -Elastomers Exposed to Air Outdoor PST -Elastomers Exposed to Air Outdoor PST -Elastomers Exposed to Air Outdoor PST* Elastomers -Exposed to Air Outdoor PST* Elastomers -Exposed to Air Outdoor Intended Function Shelter, Protection Expansion/ Separation Shelter, Protection Expansion/ Separation Shelter, Protection Expansion/ Separation Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation , fl . 'i'I'' Material 1 Elastomer Elastomer Elastomer Elastomer Elastomer Elastomer ,Environment jl:, :111:1 " *I* Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) Aging Effect Requiring Management Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength ::I" ':l:1:1'.""*l' .. '*h1*1:1' "'1*1*1*," . " 1 :* I'
+* Table" Program Vol. 2* 1tem 1 3.X.1
+* Item Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Vll.G-2 (A-20) Vll.G-2 (A-20) Vll.G-2 (A-20) Vll.G-2 (A-20) Vll.G-2 (A-20) Vll.G-2 (A-20) 3.3.1-61 3.3.1 -61 3.3.1-61 3.3.1-61 3.3.1-61 3.3.1-61 11 :11*1 I j!' 1:1' 1Note.1 *, 'I . , E, 515 E, 515 E, 515 E, 515 E, 515 E, 515 SBK-L-17155 I Enclosure 2/ Page 134 U.S. Nuclear Regulatory Commission Intended Com'ponent Type Function PST -Elastomers -PCEW-Shelter, Exposed to Air Outdoor Protection PST -Elastomers -PHA-Expansion/ Exposed to Air Outdoor Separation PST -Elastomers -PHA-Shelter, Exposed to Air Outdoor Protection PST -Elastomers -TFA-Expansion/ Exposed to Air Outdoor Separation PST -Elastomers -TFA-Shelter, Exposed to Air Outdoor Protection PST -Elastomers -WPB-Expansion/ Exposed to Air Outdoor Separation Material Elastomer Elastomer Elastomer Elastomer Elastomer Elastomer Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,1'1'1' Environment . Aging Effect Requiring I, Air Outdoor Increased Hardness, (External) Shrinkage and Loss of Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Aging I Table I ' I ' I : I ; I : ' I ; Management NUREG 1801 3.X.1 II ,ff . Vol. 2 Item Note .. r' Program Item Structures Vll.G-2 Monitoring 3.3. 1-61 E, 515 Program (A-20) Structures Vll.G-2 Monitoring 3.3. 1-61 (A-20) E, 515 Program Structures Vll.G-2 Monitoring 3.3.1-61 Program (A-20) E, 515 Structures Vll.G-2 Monitoring 3.3. 1-61 Program (A-20) E, 515 Structures Vll.G-2 Monitoring 3.3.1-61 E, 515 Program (A-20) Structures Vll.G-2 Monitoring 3.3. 1-61 E, 515 Program (A-20)
+SBK-L-17155 I Enclosure 2/ Page 135 U.S. Nuclear Regulatory Commission I I :j* Intended Component Type Function PST -Elastomers -WPB-Shelter, Exposed to Air Outdoor Protection PST -Fire Penetration Seal -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Fire Penetration Seal -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Fire Penetration Seal -FSB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Fire Penetration Seal -PAB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Fire Penetration Seal -PCEW-Exposed to Air Indoor Fire Barrier Uncontrolled I Material Elastomer Elastomer Elastomer Elastomer Elastomer Elastomer Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation *1 1* 11Y*, ; ' ! ' Aging Effect Requiring "111 1 Environment Management I ' l*I* I I I' 'ii T .( 1j: "'I' :l"lli* :1 Air Outdoor Increased Hardness, (External) Shrinkage and Loss of Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength I ,.,., I Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 P.rogram Item I Structures Vll.G-2 Monitoring (A-20) 3.3.1-61 E, 515 Program Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A SBK-L-17155 I Enclosure 2/ Page 136 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Fire Penetration Seal -WPB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Lubrite Plate -PAB-Structural Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Flood Barrier COG-Below Grade PST -Reinforced Concrete -Structural COG-Below Grade Support PST -Reinforced Concrete -COG-Below Grade Flood Barrier Material Elastomer Lubrite Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,. ' 111. ,, Aging Effect Requiring Environment Management Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Uncontrolled Loss of Mechanical Function (External) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) .Table' I Aging NUREG 1801 Management 3.X.1 Note Program Vol. 2 Item Item Fire Protection Vll.G-1 Program (A-19) 3.3.1-61 A Structures 111.82-2 Monitoring (TP-1) 3.5.1-52 A Program Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A1-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 137 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural COG-Below Grade Support PST -Reinforced Concrete -Flood Barrier COG-Below Grade PST -Reinforced Concrete -Structural COG-Below Grade Support PST -Reinforced Concrete -Flood Barrier COG-Below Grade PST -Reinforced Concrete -Structural COG-Below Grade Support ' Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' Environment Aging Effect Requiring Management Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength ' Aging* 1,,
+* 1*Table1, .. :'I' ' Vol. 2 lteni 3.X.1 Note Program *item Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A1-2 AE, 517, Monitoring (T-03) 3.5.1-27 519 Program Building Deformation Monitoring Proaram Structures lll.A1-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A1-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A1-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A1-7 Monitoring (T-02) 3.5.1-32 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 138 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -COG-Below Grade Flood Barrier PST -Reinforced Concrete -Structural COG-Below Grade Support PST -Reinforced Concrete -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural COG-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural COG-Exposed to Air Indoor Uncontrolled Support :. Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 11 I
+* Ii II :I l,' I I '. '.' l,f*j:i:;: Environment Agmg Eft'.ect Requmng Management Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) li 1Hi'!1 Aging ' ,, 111Table '"ti I" I 'l'*r,t .*!< j NUREG 1801 . I Management vo1. 21tem'1 .3.X.1 Note Program Item Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5.1-23 A Program (T-04)
+SBK-L-17155 I Enclosure 2/ Page 139 U.S. Nuclear Regulatory Commission Component Type ' " Intended Iii Function ij' I ' PST -Reinforced Concrete -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural COG-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural COG-Exposed to Air Indoor Support Uncontrolled Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation , ,, **. ''l .. , , l {'"'II Material Environment *'Aging I Management ' 11" ' ' ' i ' "I' Air Indoor Concrete Cracking and Concrete Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Concrete Uncontrolled (External) Spalling Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Air Indoor Concrete Uncontrolled Expansion and Cracking (External) ''I' 'j'l'l'I' ,,1 :!1.1i:!1J:i.11. ::!:*:1:1 1';1;1*::1; [T ,,. , .. 1! I'' ',, ' Note 'i 1.Management11.j,1 '1111 'vb1t1 '1 1ili:l3.X.tl:i1;' Program'1
+* 1teln'' *'' T **,. 'l , :.;1t,:c1,1.1.,:1:*:11, Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring 111.A1-2 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) 111.A1-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 140 U.S. Nuclear Regulatory Commission ,, Intended Component Type Function PST -Reinforced Concrete -COG-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural COG-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Missile Barrier COG-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, COG-Exposed to Air Outdoor Protection PST -Reinforced Concrete -COG-Exposed to Air Outdoor Missile Barrier Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation l , I ' : i'i ,I Aging' Effect Requiring Environment Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking !l ' I 'i' jq ;i':1: ,:hi. .pl:1:1:1:r:*1 .,1 1.1. ti I II Agirig'1:1'!1:1,,11 Tablei:I ,, 'I' ' ,j, ' NUREG '1801 ,, Management ,:, Vol. 2 Item''' '\ 3;x.1 *'' Note Program Item' ,;:1. Structures lll.A1-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A1-10 Monitoring (T-06) 3.5. 1-24 A Program Structures lll.A1-9 Monitoring 3.5. 1-23 A Program (T-04) Structures lll.A1-9 Monitoring 3.5. 1-23 A Program (T-04) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring (T-03) 3.5. 1-27 517, 519 Program Building Deformation Monitoring Program SBK-L-17155 /Enclosure2/Page 141 U.S. Nuclear Regulatory Commission I I Component Type Intended Function PST -Reinforced Concrete -Shelter, COG-Exposed to Air Outdoor Protection PST -Reinforced Concrete -COG-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, COG-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier COG-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, COG-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,,,,, I 1l *111 ;.J. *1*1 Environment " Aging Effect Requiring Management Air Outdoor (External) Expansion and Cracking Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) Air Outdoor Loss of Material, Cracking (External) ,j;, 1:. Aging NUREG 1801 Table Management 3.X.1 Note Program Vol. 2 Item Item Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A1-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Proa ram Structures lll.A1-10 Monitoring 3.5.1-24 (T-06) A Program Structures lll.A1-10 Monitoring 3.5.1-24 A Program (T-06) Structures lll.A1-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A1-6 Monitoring 3.5.1-26 A Program (T-01)
+SBK-L-17155 I Enclosure 2/ Page 142 U.S. Nuclear Regulatory Commission 1:1; / Component Type Intended Function PST -Reinforced Concrete -Structural CDG-Exposed to Raw Water Support PST -Reinforced Concrete -Structural CDG-Exposed to Raw Water Support PST -Reinforced Concrete -Structural CEHMS-Below Grade Support PST -Reinforced Concrete -Structural CEHMS-Below Grade Support Material " Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' Environment Aging Effect Requiring Management ' ' Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water (External) Expansion and Cracking Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) 1
+* Agir\g' I 'I;: '1111:/'i'lil'*l"I'' . 'l!I.' ,!1' ti'; 11:11'1 I! r Table' Management , NUREG 1801 3.X.1 Vol. 2 Item Note: .. 1 '' '/',:l:j: I Program Item ... : *I Structures 111.A1-4 Monitoring 3.5.1-31 A, 512 Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A1-2 A, 512, E Monitoring (T-03) 3.5.1-27 '517, Program 519 Building Deformation Monitoring Proqram Structures 111.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) 111.A3-2 A, E, Monitoring (T-03) 3.5.1 -27 517, 519 Program Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 143 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural CEHMS-Below Grade Support PST -Reinforced Concrete -Structural CEHMS-Below Grade Support PST -Reinforced Concrete -Structural CEHMS-Below Grade Support PST -Reinforced Concrete -CEHMS-Exposed to Air Missile Barrier Outdoor PST -Reinforced Concrete -CEHMS-Exposed to Air Missile Barrier Outdoor Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking 1:1 Ag/ng1 );111: I ''1:1 1;; i!li I 111 Table. NUREG 1801 Management Vol. 2 Item 3.X.1 ' Note Program Item Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-9 Monitoring 3.5.1-23 A (T-04) Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-27 (T-03) 517, 519 Program Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 144 U.S. Nuclear Regulatory Commission ! Component "f;ype Intended II', Function " :1 ! PST -Reinforced Concrete -CEHMS-Exposed to Air Missile Barrier Outdoor PST -Reinforced Concrete -CEHMS-Exposed to Air Missile Barrier Outdoor PST -Reinforced Concrete -Flood Barrier EFP-Below Grade PST -Reinforced Concrete -Structural EFP-Below Grade Support PST -Reinforced Concrete -Flood Barrier EFP-Below Grade !1.11' Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation iil:1: IT 11111'1' ''['111'1"1' 1'l'l"IT1''"1' ! 'llfl :: 11 ,,,,+ 1 * ! : 111:11:+1 .. '1*1<<1'"';1 l'i!l:if'I: Environment Ag1,ng Efl'.ect1Req\J1m'lg'11 fl Management ,, *, Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) 111 11 NUREG'[1sot ii . , : ' I 1'1* 1' Aging .. r I '1:1i:Taplei; . !' ' ],Ill,,, 111 IJl"I fl Note 1*k,Management '1:i 1:*1:i,vol'.:1211i0ln'mJ1, 1 '111P,r6gram,!!l':)l1! 1l1vHl:11111,. "n:u11j::!'1 '"':11:1 : 11 :1:1:1' 1f:.1.,J*i:; Structures lll.A3-10 Monitoring (T-06) 3.5. 1-24 A Program Structures 111.A3-6 Monitoring (T-01) 3.5, 1-26 A Program Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 145 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural EFP-Below Grade Support PST -Reinforced Concrete -Flood Barrier EFP-Below Grade PST -Reinforced Concrete -Structural EFP-Below Grade Support PST -Reinforced Concrete -Structural EFP-Below Grade Support PST -Reinforced Concrete -Structural EFP-Below Grade Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring Management Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength {jAging ':1: .Ii 1*1'1 Table ,, 'I I NUREG 1801 Management Vol. 2 Item 3.X.1 Note Program Item Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proa ram Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program SBK-L-17155 /Enclosure2/Page 146 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -EFP-Below Grade Flood Barrier PST -Reinforced Concrete -Structural EFP-Below Grade Support PST -Reinforced Concrete -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural EFP-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural EFP-Exposed to Air Indoor Uncontrolled Support Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note Program Item .. , Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04)
+SBK-L-17155 I Enclosure 2/ Page 147 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural EFP-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural EFP-Exposed to Air Indoor Support Uncontrolled Material ,,, Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,, Aging Effect Requiring Environment Management Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging Table ,,, NUREG 1801 Management Vol. 2 Item 3.X.1 Note Program Item Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 148 U.S. Nuclear Regulatory Commission 1:1 Intended Component Type **Function 'I: PST -Reinforced Concrete -EFP-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural EFP-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Missile Barrier EFP-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, EFP-Exposed to Air Outdoor Protection PST -Reinforced Concrete -EFP-Exposed to Air Outdoor Missile Barrier I ,,, Material ii' Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation }I ' 111 1lli '' ' 1:1 . i:I Ill ''Jil Aging Effect* Requiring 11i,lll Environment *:I ',11.11 'I" *:1*1
+* n Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking Aging I I* NUREG 1801 *** Table Management 'Jr3cX; 1 Note * ,, program'l'1iil:1M* . VoL 21itemjj1*1 il'ljl *'' i.1,I,,., *I L1 .. , iii'] :J!l:ll'I :: 1:IJl''il :* ''iH ltem,)!'''I' i' Structures lll.A3-10 Monitoring (T-06) 3.5, 1-24 A Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5, 1-23 A Program (T-04) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5, 1-27 517, 519 Program Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 149 U.S. Nuclear Regulatory Commission Intended Component Type, Function PST -Reinforced Concrete -Shelter, EFP-Exposed to Air Outdoor Protection PST -Reinforced Concrete -EFP-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, EFP-Exposed to Air Outdoor Protection PST -Reinforced Concrete -EFP-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, EFP-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' ' ' '"11 ,, ti : ,j1l':11'!! ' Effect Requiring ljj' Environment Management Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Air Outdoor Loss of Material, Cracking (External) 1 ,l*I :li.,4_'i' ,. 'I' ''', !j:I 1: ,,, Table''\' 1:11 ' l'''I I gmg NUREG 1801 1' 11 Manage'ment ' *Ir 3.x.1 Note Program Vol. 2 Item Item Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring 111.A3-2 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures ll\.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01)
+SBK-L-17155 I Enclosure 2/ Page 150 U.S. Nuclear Regulatory Commission ",,,1;, 'I Intended Component Type Function PST -Reinforced Concrete -Structural EFP-Exposed to Raw Water Support PST -Reinforced Concrete -Structural EFP-Exposed to Raw Water Support PST -Reinforced Concrete -Flood Barrier FSB-Below Grade PST -Reinforced Concrete -Structural FSB-Below Grade Support PST -Reinforced Concrete -Flood Barrier FSB-Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ii',' 1:i: ,:1111 1, ' :1;1:* *j*I* ;.:.I*;* . ,:1:: :f*' I:' ' ' i: Environmeht11:1 ,, , i:i,,,l:v:1, 111 g Ji,, 1:1.*," Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water (External) Expansion and Cracking Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) , Aging , ':, _,!11_i:1,,,, 1111:1': Management , ,,.NUREG , ,, ' ''Iii }I Note ,,,i, ,,:Vol. 2 Item :h ,, Ii' 1:1: ':1111it, 1il'jli1!lli;1 111: ''Item **' Structures lll.A3-4 Monitoring 3.5.1-31 A, 512 Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) 111.A3-2 A, 512, Monitoring (T-03) 3.5.1-27 E, 517, Program 519 Building Deformation Monitoring Proqram Structures lll.A5-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A5-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program lll.A5-2 A, E, Alkali-Silica 3.5.1-27 Reaction (ASR) (T-03) 517, 519 Monitoring Program SBK-L-17155 I Enclosure 2/ Page 151 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural FSB-Below Grade Support PST -Reinforced Concrete -Flood Barrier FSB-Below Grade PST -Reinforced Concrete -Structural FSB-Below Grade Support PST -Reinforced Concrete -Structural FSB-Below Grade Support Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,, , Aging Effect Requiring Environment Management Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength ': Table :1: Aging ' ' Management
+* NUREG 1801 3.X.1 Note Vol. 2 Item Program Item Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) 111.A5-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proa ram Structures lll.A5-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A5-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A5-7 Monitoring (T-02) 3.5.1-31 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 152 U.S. Nuclear Regulatory Commission '* Intended Component Type Function I* PST -Reinforced Concrete -Structural FSB-Below Grade Support PST -Reinforced Concrete -FSB-Below Grade Flood Barrier PST -Reinforced Concrete -Structural FSB-Below Grade Support PST -Reinforced Concrete -FSB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural FSB-Exposed to Air Indoor Support Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1:: ', Aging Effect Requiring Environment*'' ' : , Management ;:I 1:1 . 111'1 .'li'l!I l*11:'"11l:ff 'I *'1'tl'''1ii' 111 Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Aging NUREG 1801 Table Management Vol .. 2.ltem I'' 3.X.1 Note ,., ,,,, .,1 Pr9gram , : :j:I I ;' 1 ::::p,., 111:1'i'*'l}*!,:!:1 Structures Ill.AS-? Monitoring (T-02) 3.5.1-31 A, 509 Program Structures 111.AS-6 Monitoring (T-01) 3.5.1-26 A Program Structures 111.AS-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 3.3.1-67 A Program (A-91) Fire Protection Vll.G-29 3.3.1-67 A Program (A-91) Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A SBK-L-17155 I Enclosure 2/ Page 153 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -FSB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural FSB-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -FSB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural FSB-Exposed to Air Indoor Uncontrolled Support Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation :: Aging Effect Requiring ***' ;.;Environment Management Air Indoor Cracking, Loss of Bond, Loss Uncontrolled of Material (Spalling, Scaling) (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled of Material (Spalling, Scaling) (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Concrete Cracking and Uncontrolled Spalling (External) Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Aging NUREG 1801 Table Management 3.X.1 Note ; Program Vol. 2 Item Item Structures lll.A5-9 Monitoring (T-04) 3.5.1-23 A Program Structures lll.A5-9 Monitoring (T-04) 3.5.1-23 A Program Structures lll.A5-9 Monitoring 3.5.1-23 A Program (T-04) Fire Protection Vll.G-28 Program (A-90) 3.3.1-65 A Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90)
+SBK-L-17155 I Enclosure 2/ Page 154 U.S. Nuclear Regulatory Commission .Intended Component Type h function . :1:1 :* PST -Reinforced Concrete -FSB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural FSB-Exposed to Air Indoor Support Uncontrolled Material I,' Concrete Concrete Concrete 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: ,11 {'-gir:i,9 Environment 11* 1'::1 " Manageinen't" '!;, 1"*11 I ' Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) 111 Ag'ing1 , . i]li.,. * :111 *** I I 'I: I ilil 11f N:u 1 I !I !f:;, I' Management{I' ,: . 'Vc'I' 211tehl 1" : '1* :,.!, ,I, I l,j1j::: :** ii! J.il:, .i:I',,' :l\J'.:11' 1111111!11: I: **1 1: l r . : , . . i Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A5-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Proqram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A5-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A5-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 155 U.S. Nuclear Regulatory Commission Component Type PST -Reinforced Concrete -FSB-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -FSB-Exposed to Air Outdoor PST -Reinforced Concrete -FSB-Exposed to Air Outdoor Intended Function Fire Barrier Shielding Structural Support Missile Barrier Shelter, Protection Material Concrete Concrete Concrete Concrete Concrete PST -Reinforced Concrete -FSB-Exposed to Air Outdoor Missile Barrier I Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Outdoor (External) Air Outdoor (External) Air Outdoor (External) I . Aging Effect Requiring Management Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) Expansion and Cracking I *Aging ' Management Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Buildinq **I I I NUREG 1801 Vol. 2 Item lll.A5-10 (T-06) lll.A5-10 (T-06) lll.A5-10 (T-06) lll.A5-9 (T-04) lll.A5-9 (T-04) lll.A5-2 (T-03) Table 3.X.1 Item 3.5.1-24 3.5.1-24 3.5.1-24 3.5.1-23 3.5.1-23 3.5.1-27 Note A A A A A A, E, 517, 519 SBK-L-17155 I Enclosure 2/ Page 156 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Shelter, FSB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier FSB-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, FSB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier FSB-Exposed to Air Outdoor Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1, Environment Aging Effect Requiring Man'agement Air Outdoor (External) Expansion and Cracking Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) Aging l'I ,11 " :1:1', /', ' Table Management ''11 NUREG'1801 " 3.X.1 ;, ,, Vol. 2 Item Note Program Item Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A5-2 Monitoring 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Proaram Structures lll.A5-10 Monitoring 3.5.1-24 (T-06) A Program Structures lll.A5-10 Monitoring 3.5.1-24 A Program (T-06) Structures lll.A5-6 Monitoring 3.5.1-26 A Program (T-01)
+SBK-L-17155 I Enclosure 2/ Page 157 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Shelter, FSB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Structural FSB-Exposed to Raw Water Support PST -Reinforced Concrete -Structural FSB-Exposed to Raw Water Support PST -Reinforced Concrete -Flood Barrier PAB-Below Grade PST -Reinforced Concrete -Structural PAB-Below Grade Support 1:1 *1:' ii' .J Material 111 ,,: I Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging .Effect Requiring *11 Environment Management I!! :, ', ::11:, :j11 .I* Air Outdoor Loss of Material, Cracking (External) Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water (External) Expansion and Cracking Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Aging Table I *l*I NUREG 1801 .i:I: Management Vol. 2 Item 3.X.1 Note I Program Item Structures lll.A5-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A5-4 Monitoring 3.5.1-31 A, 512 Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A5-2 A, 512, Monitoring (T-03) 3.5.1-27 E, 517, Program 519 Building Deformation Monitoring Proaram Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05)
+SBK-L-17155 I Enclosure 2/ Page 158 U.S. Nuclear Regulatory Commission I Intended Com.ponent Type Function PST -Reinforced Concrete -Flood Barrier PAB-Below Grade PST -Reinforced Concrete -Structural PAB-Below Grade Support PST -Reinforced Concrete -Flood Barrier PAB-Below Grade PST -Reinforced Concrete -Structural PAB-Below Grade Support :I :* , I Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation I ' I lili Aging Effect Requiring :ii 11 '" Management 11i11 i.1 Iii' rilil 11: ,;;;: :11 Ground Water/Soil Expansion and Cracking (External) Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Aging Table n'''i1 NUREG 1801 Management 3.X.1 Note Vol. 2 Item :item Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proqram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures 111.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program SBK-L-17155 I Enclosure 2/ Page 159 U.S. Nuclear Regulatory Commission I 1:,*, Intended 'I Component Type Function PST -Reinforced Concrete -Structural PAB-Below Grade Support PST -Reinforced Concrete -Structural PAS-Below Grade Support PST -Reinforced Concrete -PAB-Below Grade Flood Barrier PST -Reinforced Concrete -Structural PAS-Below Grade Support PST -Reinforced Concrete -PAS-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PAS-Exposed to Air Indoor Support Uncontrolled ,, Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' I ':i!!:'f I '!:::': I: 1 I :IJtFil" :1;, I 'I' ,11 , Aging .E:ttei;t Requiring ,:, Environment I, 1::1 * '11*i1[,:lil .. ,1:1f I Ii 11 11 , , ,, : , ''"1'h Hi!: '.11:i,I. '''1'1 H1i:1 i'I::'"' !ll:i11il l'i:''l*Jili iJ
+* Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) ,,,. Aging , , NUREG 1B01iil: lt'"'Mahage'ment ' 't + Note i'I' 'V i '21,{1' ,i,'iji I', o,. em: 11'*,''1tem'1:''', ' I R ' ' ' 11' lfl ,1111*1il111l1;1ilil1,1111l*,:1:1111111i:ll111 di* ,:i"'ii . iH : :1:, , 1:l.1:1JI ''"I ,,, ,,,**h:1., Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A SBK-L-17155 I Enclosure 2/ Page 160 U.S. Nuclear Regulatory Commission 1: Intended Component Type Function PST -Reinforced Concrete -PAB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PAS-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -PAS-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PAS-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -PAS-Exposed to Air Indoor Fire Barrier Uncontrolled I Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation I Aging Effect Requiring Environment Management Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Uncontrolled Expansion and Cracking (External) Aging Table 1, 1;1:1:1,:1: NUREG 1801 Management Vol. 21tem 3.X.1 Note Program Item Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 161 U.S. Nuclear Regulatory Commission " Intended Component Type Funetion I :I: PST -Reinforced Concrete -Structural PAB-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -PAS-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PAB-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Missile Barrier PAB-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, PAB-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation I ,J, '\" *1 , 1:1 !i1,,:f ;I ilA 11ii11'* 1:111111:1ili1:1: , ';Ir'. '1, 1Jjj ,;li'1:1 Environment , {'-gang Effect Requmr;ig 'I' 11: , Management
+* 11. '1' k Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) 'I' . . 'A . ' ,,,,. 1::* ;J:i ili1ili! 1::' 'f ,111::J'i 1'1,.;gmg :ii1*1,( l:JI 1 'Ii NUREG.i1801':jil '1'1 j:i. I' Note : 111111v<:m 2. 1t0r.T{' . * *, .. 3,.X.1 iJi1. I* 'j:' '1'*:1 .:;11,ti:, :1 *I' 'Item. *Ii\ ** I ';I Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures 111.A3-9 Monitoring 3.5.1-23 A Program (T-04)
+SBK-L-17155 I Enclosure 2/ Page 162 U.S. Nuclear Regulatory Commission Component Type Intended Function PST -Reinforced Concrete -Missile Barrier PAB-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, PAB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier PAB-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, PAB-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Management I*' **: Air Outdoor (External) Expansion and Cracking Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 Monitoring 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Proqram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 Monitoring 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Proaram Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-10 Monitoring 3.5.1-24 A Program (T-06)
+SBK-L-17155 I Enclosure 2/ Page 163 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -PAB-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, PAB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -PCEW-Below Grade Flood Barrier PST -Reinforced Concrete -Structural PCEW-Below Grade Support PST -Reinforced Concrete -PCEW-Below Grade Flood Barrier Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation II f:J 1:1. l:i', ' ,.1 Environment 1.Aging1Effect Requiring Management Air Outdoor (External) Loss of Material, Cracking Air Outdoor (External) Loss of Material, Cracking Ground Cracking, Loss of Bond, Loss Water/Soil of Material (Spalling, Scaling) (External) Ground Cracking, Loss of Bond, Loss Water/Soil of Material (Spalling, Scaling) (External) Ground Water/Soil Expansion and Cracking (External) Aging NUREG 1so11: Table Management 3.X.1 Note Progra.m Vol. 2 Item Item Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures 111.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A Program Structures 111.A3-4 Monitoring (T-05) 3.5.1-31 A Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 164 U.S. Nuclear Regulatory Commission 1: ,, Intended Component Type Function PST -Reinforced Concrete -Structural PCEW-Below Grade Support PST -Reinforced Concrete -Flood Barrier PCEW-Below Grade PST -Reinforced Concrete -Structural PCEW-Below Grade Support PST -Reinforced Concrete -Structural PCEW-Below Grade Support PST -Reinforced Concrete -Structural PCEW-Below Grade Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation , ''II'::,,,,, 1:1 ,, 'Aging Effect Requiring 111 1 1 .ji11ManagelT)ent ll,,iij' 111 " ,1, 1:1l::,:r*"'l',.'j1'*''**I*, :l1l *!:1J11l*1, *:* 1,+ Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Table '*11*1* Aging NUREG 1801 Management Vol. 2 ., , 3.X.1 Note J1,1 1:1('1 ' "H 11111',' 1l*i'IFl'I ' Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program ----
+SBK-L-17155 I Enclosure 2/ Page 165 U.S. Nuclear Regulatory Commission Component Type Intended Function ,, 1:1' PST -Reinforced Concrete -PCEW-Below Grade Flood Barrier PST -Reinforced Concrete -Structural PCEW-Below Grade Support PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -HELB PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural PCEW-Exposed to Air Indoor Support Uncontrolled Material ::* Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1; I II '' I T1 ' II' Ill ,, '' 1' , ,', ,, 1!1:1:1: ,, . '',*ii'' ' l'l,,,,1'.' ,,, l'I'' Environment , , :11 1 Management111 :111 ,, ' ' Ii Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) 1'1 I!' ''1Aging r:I I*' ji!I {j ; :1:l*l*l'i1*1 1:, ' ' 'I' :Table ;: ,,,, ,1 ,,, " ''I' ,, NUREG'1:?B0111Fi 111'1'11'3)<!:1,,:, { 111:, Note 1:1 'Management** I' i:i_:r1*I '1 I '''i'I :*,**r1 :. '.*;I 11 .1,11,.1.:11 .*l:i 1'.11 ,,:''''1'1tem1' ''I: 11111Rrogram111'11:1.1 '1:1'11'1:, '*'' I ' , ,, r*: 'Ti*l*I ... , .. ,,I"'* .. l.,j . ' Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A SBK-L-17155 I Enclosure 2/ Page 166 U.S. Nuclear Regulatory Commission Intended Cornponent Type Function PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -HELB PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural PCEW-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -HELB PCEW-Exposed to Air Indoor Uncontrolled Shielding l'i Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Material Environment Management Air Indoor Cracking, Loss of Bond, Loss Concrete Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Concrete Uncontrolled of Material (Spalling, Scaling) (External) Air Indoor Cracking, Loss of Bond, Loss Concrete Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Concrete Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Concrete Cracking and Concrete Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Concrete Uncontrolled (External) Spalling Aging i: Table NUREG 1801 Management Vol. 2 Item 3.X.1 Program Item 1:, Structures 111.A3-9 Monitoring 3.5. 1-23 A Program (T-04) Structures lll.A3-9 Monitoring (T-04) 3.5. 1-23 A Program Structures lll.A3-9 Monitoring 3.5. 1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5. 1-23 A Program (T-04) Fire Protection Vll.G-28 3.3. 1-65 A Program (A-90) Fire Protection Vll.G-28 3.3. 1-65 A Program (A-90)
+SBK-L-17155/Enclosure2/Page167 U.S. Nuclear Regulatory Commission ,.!: 1:: Component Type PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled Intended Function Shielding Structural Support Fire Barrier HELB Shielding Mate'rial Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) I*!; Aging Effect Requiring Management Concrete Cracking and Spalling Concrete Cracking and Spalling Expansion and Cracking Expansion and Cracking Aging Management Program Fire Protection Program Fire Protection Program Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program 1*11;1 NUREG 1801 Vol. 2 Item Vll.G-28 (A-90) Vll.G-28 (A-90) lll.A3-2 (T-03) lll.A3-2 (T-03) Table 3.X.1 Item 3.3.1-65 3.3.1-65 3.5.1-27 3.5.1-27 ;i'':!:11::i:, Note',:,, A A A, E, 517, 519 A, E, 517, 519 SBK-L-17155 I Enclosure 2/ Page 168 U.S. Nuclear Regulatory Commission Component Type PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Uncontrolled Intended Function Shielding Structural Support Fire Barrier HELB Shielding Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) 111' I* I ' ,!; ,I,,' :1 Aging Effect Requiring 111 Management-* '
+* I Expansion and Cracking Expansion and Cracking Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Aging Management Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program Structures Monitoring Program Structures Monitoring Program NUREG 1801 Vol. 2 Item lll.A3-2 (T-03) lll.A3-2 (T-03) lll.A3-10 (T-06) lll.A3-10 (T-06) 'Table I 3.X.1 Item 3.5.1-27 3.5.1-27 3.5.1-24 3.5.1-24 Note A, E, 517, 519 A, E, 517, 519 A A SBK-L-17155 I Enclosure 21 Page 169 U.S. Nuclear Regulatory Commission *1:* Intended Component Type Function PST -Reinforced Concrete -PCEW-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural PCEW-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Missile Barrier PCEW-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, PCEW-Exposed to Air Outdoor Protection PST -Reinforced Concrete -PCEW-Exposed to Air Outdoor Missile Barrier Material ' Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment I , :1:1:1.l!f!il; !l'it l![i ****. ' :l!I , *,11 * *1*1 Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking Aging NUREG 1801 Table 1:1 Management 3.X.1 Note " ,Program Vol. 2 Item Item I: I Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 170 U.S. Nuclear Regulatory Commission 'I Component Type Intended Function PST -Reinforced Concrete -Shelter, PCEW-Exposed to Air Outdoor Protection PST -Reinforced Concrete -PCEW-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, PCEW-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier PCEW-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, PCEW-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) Air Outdoor Loss of Material, Cracking (External) Ag'ing NUREG 1801 Table ,, 'Iii Management 3.X.1 , I : , , Program Vol. 2 Item Item Note i: *: ' Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-2( Program (T-03) 517, 519 Building Deformation Monitoring Proqram Structures lll.A3-10 Monitoring 3.5.1-24 (T-06) A Program Structures lll.A3-10 Monitoring 3.5.1-24 A Program (T-06) Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01)
+SBK-L-17155 I Enclosure 2/ Page 171 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural PCEW-Exposed to Raw Water Support PST -Reinforced Concrete -Structural PCEW-Exposed to Raw Water Support PST -Reinforced Concrete -Flood Barrier PHA-Below Grade PST -Reinforced Concrete -Structural PHA-Below Grade Support PST -Reinforced Concrete -Flood Barrier PHA-Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,,,,,, 111,::111, Aging Req'uiring ,:,. Environment I!:* 11 , ,11 '!:1 Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water Expansion and Cracking (External) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) 'Aging Table NUREG 1801 Management Vol. 2 lfom J;X.1 Note Pr9g,ram, 1'','"*: " , ".:!': l:!*l'i]JI 1;:11:11.,!tem.,, Structures lll.A3-4 Monitoring 3.5.1-31 A, 512 Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) A, 512, Monitoring 111.A3-2 3.5.1-27 E, 517, Program (T-03) 519 Building Deformation Monitoring Program Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program lll.A3-2 3.5.1-27 A, E, Alkali-Silica (T-03) 517, 519 Reaction (ASR) Monitoring ProQram SBK-L-17155 I Enclosure 2/ Page 172 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural PHA-Below Grade Support PST -Reinforced Concrete -Flood Barrier PHA-Below Grade PST -Reinforced Concrete -Structural PHA-Below Grade Support PST -Reinforced Concrete -Structural PHA-Below Grade Support Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment. Aging Effect Requiring Management Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength i' Aging NUREG 1801 Table :r Management Vol. 2 Item 3.X.1 Note Program Item. Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures 111.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 173 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural PHA-Below Grade Support PST -Reinforced Concrete -PHA-Below Grade Flood Barrier PST -Reinforced Concrete -Structural PHA-Below Grade Support PST -Reinforced Concrete -PHA-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PHA-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -PHA-Exposed to Air Indoor Fire Barrier Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' ' I : ' 1i:1:1111N!l ' 11:1,11 : I I:' 1:1:1'11:1' Aging Effect Requiring Environment Management Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) I'', !11;1,1:!Aging . 1,:11,,, ,1; I Table NUREG.'1801 Management Vol. 2 Item 3.X.1 Note Program Item Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01). 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04)
+SBK-L-17155 I Enclosure 2/ Page 174 U.S. Nuclear Regulatory Commission Intended Comphnent Type Function PST -Reinforced Concrete -Structural PHA-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -PHA-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PHA-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -PHA-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -Structural PHA-Exposed to Air Indoor Uncontrolled Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation I I iF *I* ' Effect Requiring, . J M *Aging t 1 Environmenrl 11 Ii! : 'l!F .1i:q. ! Mdnagement 1 1il'111 . . anagemen 1 * '.i 'I' .,1,11 *1111 IJ l1',uf!f!l:l'l11:i:'l't:1111 ''1,1:1:W':1:,,-, .,. , '!f!:l.1 I ,!I :1!!:*1 I* Air Indoor Cracking, Loss of Bond, Loss Structures Uncontrolled Monitoring (External) of Material (Spalling, Scaling) Program Air Indoor Concrete Cracking and Fire Protection Uncontrolled (External) Spalling Program Air Indoor Concrete Cracking and Fire Protection Uncontrolled (External) Spalling Program Structures Monitoring Program Alkali-Silica Air Indoor Reaction (ASR) Uncontrolled Expansion and Cracking Monitoring (External) Program Building Deformation Monitoring Proqram Structures Monitoring Program Air Indoor Uncontrolled Expansion and Cracking Alkali-Silica (External) Reaction (ASR) Monitoring Program NUREG 1801 Table I 'I Vol. 2 Item 1, , 3.X.1. Note ,,,1, 1'1:i:''* :1: :l:1!l*i: ,,,1,,!: ' .. 111.A3-9 3.5. 1-23 A (T-04) Vll.G-28 3.3. 1-65 A (A-90) Vll.G-28 3.3. 1-65 A (A-90) lll.A3-2 A, E, 3.5. 1-27 (T-03) 517, 519 lll.A3-2 A, E, 3.5. 1-27 (T-03) 517, 519 SBK-L-17155 I Enclosure 2/ Page 175 U.S. Nuclear Regulatory Commission Component Type PST -Reinforced Concrete -PHA-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PHA-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -PHA-Exposed to Air Outdoor PST -Reinforced Concrete -PHA-Exposed to Air Outdoor Intended Function Fire Barrier Structural Support Shelter, Protection Shelter, Protection Material Concrete Concrete I Concrete I Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1:1:' :111 ',1111 .,11: Environment1 ** :i!li 1A. g .* g. f:iHect Requiring, I .I 'I' 'l'l'il: ,: Management. ., :::1*:: II :l:H:l1 <j11I: : *l:'":i: ' 'I Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor I Expansion and Cracking (External) Aging , Management 11 Program Building Deformation Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program NUREG 1801 I Table Vol. 2 Item 3.X.1 *i :i, 'I* , ,,,:1111j.ltem Note lll.A3-10 (T-06) I 3.5.1-24 IA I lll.A3-10 (T-06) I 3.5.1-24 IA 111.A3-9 I 3.5.1-23 IA (T-04) 111.A3-2 I 3.5.1-27 A, E, (T-03) 517, 519 SBK-L-17155 I Enclosure 2/ Page 176 U.S. Nuclear Regulatory Commission Intended ' Component Type Function PST -Reinforced Concrete -Shelter. PHA-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Shelter, PHA-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Flood Barrier TFA-Below Grade PST -Reinforced Concrete -Structural TFA-Below Grade Support PST -Reinforced Concrete -Flood Barrier TFA-Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,1, l:' 'l:'I" ' ''i' ,,, ' 1:. , Aging' Effect Requiri'ng 1 Environment Management ! ' I ' ' Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) Table ,,1 Aging NUREG 1801 ,Management Vol. 2 Item 3.X.1 Note' Program Item Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 177 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural TFA-Below Grade Support PST -Reinforced Concrete -Flood Barrier TFA-Below Grade PST -Reinforced Concrete -Structural TFA-Below Grade Support PST -Reinforced Concrete -Structural TFA-Below Grade Support PST -Reinforced Concrete -Structural TFA-Below Grade Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ;1: 'I Aging Effect Requiring Environment Management Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Aging Table NUREG 1801 Management Vol. 2 Item 3.X.1 Note Program Item Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program SBK-L-17155 I Enclosure 2/ Page 178 U.S. Nuclear Regulatory Commission Intended Component Type '" , 1,111 Function . " 1, PST -Reinforced Concrete -TFA-Below Grade Flood Barrier PST -Reinforced Concrete -Structural TFA-Below Grade Support PST -Reinforced Concrete -TFA-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -TFA-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural TFA-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -TFA-Exposed to Air Indoor Fire Barrier Uncontrolled :r* Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation t t 111 11[:'.1 Material Environment ' Management 1:11.1:'11 11 :1111 '' I ' * ,,, .,, ;i'l;,1 JI Ground Concrete Water/Soil Loss of Material, Cracking (External) Ground Concrete Water/Soil Loss of Material, Cracking (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Loss Concrete Uncontrolled (External) of Material (Spalling, Scaling) + ,,* I t!l:1: Aging i; :1, 1'1i11[ :1: I 1:, 1:1,Manager:nrnt,1,1, NUREG 180,11'n ;111 '' 11.1, ... :111 ,1.,1 Program* t11 'llllJ1'1:1!1l111111 *'*l:i!ll11f:I::,,, '.: :; :\Item 'l1,1 lij: 11*1 .' ' * ,I.' I :: *I; Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 Program (A-91) 3.3. 1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04)
+SBK-L-171 SS I Enclosure 2/ Page 179 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -TFA-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural TFA-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -TFA-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -TFA-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural TFA-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -TFA-Exposed to Air Indoor Fire Barrier Uncontrolled I I Material ' Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 'I i+i ' ' '' Effect '' ,*11 Environment 1 l'l:!Jli; 111 '1 I, I I :I: * :':1:j:1 *l111:l:,:i:p11fDitl ,11 *1111: ':11 'I' , , Air Indoor Cracking, Loss of Bond, Loss Uncontrolled of Material (Spalling, Scaling) (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled of Material (Spalling, Scaling) (External) Air Indoor Concrete Cracking and Uncontrolled Spa I ling (External) Air Indoor Concrete Cracking and Uncontrolled Spa I ling (External) Air Indoor Concrete Cracking and Uncontrolled Spalling (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging Table 1lil,j1:jll*.::1:1; NUREG 1801 Management 3.X.1 Vol. 2 Item Program Item ' Structures lll.A3-9 Monitoring 3.5.1-23 A (T-04) Program Structures lll.A3-9 Monitoring 3.5.1-23 A (T-04) Program Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 A 3.3.1-65 Program (A-90) Structures Monitoring Program Alkali-Silica lll.A3-2 A, E, Reaction (ASR) (T-03) 3.5.1-27 517, 519 Monitoring Program Building SBK-L-17155 I Enclosure 2/ Page 180 U.S. Nuclear Regulatory Commission Component Type Intended Function PST -Reinforced Concrete -TFA-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural TFA-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -TFA-Exposed to Air Indoor Fire Barrier Uncontrolled Material Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation !.t I H ,,, Environment Aging Effect,Requiripg Management Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Aging Management NUREG 1801 3.X.1 Note Vol. 2 Item Program ,,, Item Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proqram Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 181 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -TFA-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural TFA-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -Missile Barrier TFA-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, TFA-Exposed to Air Outdoor Protection PST -Reinforced Concrete -TFA-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, TFA-Exposed to Air Outdoor Protection Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' II 1:! Aging Effect Requiring Environment Management Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking Air Outdoor Expansion and Cracking (External) ,,, Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note Program Item Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) . Structures lll.A3-2 Monitoring (T-03) 3.5.1-27 A Program Structures Monitoring Program Alkali-Silica lll.A3-2 3.5.1-27 A, E, Reaction (ASR) (T-03) 517, 519 Monitoring Program Building SBK-L-17155 I Enclosure 2/ Page 182 U.S. Nuclear Regulatory Commission Component Type Intended Function PST -Reinforced Concrete -Missile Barrier TFA-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, TFA-Exposed to Air Outdoor Protection PST -Reinforced Concrete -Missile Barrier TFA-Exposed to Air Outdoor PST -Reinforced Concrete -Shelter, TFA-Exposed to Air Outdoor Protection PST -Reinforced Concrete -WPB-Below Grade Flood Barrier Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation II ' I*; 1:'':1:.i:* "' :[:i: IJ'* Aging Effect Requiring 111 Environment Management Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Increase in Porosity and Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) Air Outdoor Loss of Material, Cracking (External) Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) n1 1*,,111:11 , , 1:1, ' ' II' 11! rl I ll ''*
+* I ''!"'* 1 >r" l'I '
+* 11] *:,f ,. :: 'l' 111'r Table 1:k Managementi*ll , , NUREC?;,1,so11, ' 3.X.1
+* Note Program 111Nol. 2' Item Item Deformation Monitoring Program Structures lll.A3-10 Monitoring 3.5.1-24 A Program (T-06) Structures lll.A3-10 Monitoring 3.5.1-24 A Program (T-06) Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01) Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01) Structures Monitoring lll.A3-4 3.5.1-31 (T-05) A Program SBK-L-17155 I Enclosure 2/Page 183 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural WPB-Below Grade Support PST -Reinforced Concrete -WPB-Below Grade Flood Barrier PST -Reinforced Concrete -Structural WPB-Below Grade Support PST -Reinforced Concrete -WPB-Below Grade Flood Barrier Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation :1: T *I Aging Effect Requiring Environment Management Ground Cracking, Loss of Bond, Loss Water/Soil (External) of Material (Spalling, Scaling) Ground Water/Soil Expansion and Cracking (External) Ground Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Aging NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note Program Item Structures lll.A3-4 Monitoring 3.5.1-31 A Program (T-05) Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proa ram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program SBK-L-17155 I Enclosure 2/ Page 184 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Reinforced Concrete -Structural WPS-Below Grade Support PST -Reinforced Concrete -Structural WPS-Below Grade Support PST -Reinforced Concrete -Structural WPB-Below Grade Support PST -Reinforced Concrete -Flood Barrier WPS-Below Grade PST -Reinforced Concrete -Structural WPS-Below Grade Support PST -Reinforced Concrete -WPS-Exposed to Air Indoor Fire Barrier Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,,,, , 'l 'I'll:('' i' ::1 Environment Aging Effect Requiring 11' ,,, ' llMana,gemen.t 1:1 ,,,, Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Loss of Material (External) Agir;ig ,,, ::IJ, fr,j:I ,,,,, ITable, Management *NU REG 1,801 ix.1 Note Program Vol. 2 Item , Item '1;:;, Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures 111.A3-6 Monitoring (T-01) 3.5.1-26 A Program Fire Protection Vll.G-29 3.3.1-67 A Program (A-91)
+SBK-L-17155 I Enclosure 2/ Page 185 U.S. Nuclear Regulatory Commission '' Intended Component Type Function PST -Reinforced Concrete -WPB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural WPB-Exposed to Air Indoor Support Uncontrolled PST -Reinforced Concrete -WPB-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -WPB-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural WPB-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -WPB-Exposed to Air Indoor Fire Barrier Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ' ' ' Aging Effect Requiring Environment 1: 1* Management Air Indoor Uncontrolled Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Aging NUREG 1801 Table Management 1 Note Program Vol. 2 Item 11tem Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Fire Protection Vll.G-29 Program (A-91) 3.3.1-67 A Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90)
+SBK-L-17155 I Enclosure 2/ Page 186 U.S. Nuclear Regulatory Commission Component Type * ' ' Intended Function'!' PST -Reinforced Concrete -WPS-Exposed to Air Indoor Shielding Uncontrolled PST -Reinforced Concrete -Structural WPS-Exposed to Air Indoor Uncontrolled Support PST -Reinforced Concrete -WPS-Exposed to Air Indoor Fire Barrier Uncontrolled PST -Reinforced Concrete -WPS-Exposed to Air Indoor Shielding Uncontrolled "Material ''" :1: Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 11111:,,111 qi, ,1111 it.l,.11'111111111 Environment Agmg Effect , 1 Management Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) 1il1 i1'!11i*1 111111-lillllillllll"llllli llr 11*11lirab11e/1 1[:1i
+* Management I '13 x I" .*, 1. Note 1yo1.l 21tem t * *111111 111,1_ !], .. 'I' . ' Program Item' Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 187 U.S. Nuclear Regulatory Commission Component Type PST -Reinforced Concrete -WPS-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -WPS-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -WPS-Exposed to Air Indoor Uncontrolled PST -Reinforced Concrete -WPS-Exposed to Air Indoor Uncontrolled Intended Function 1::. Structural Support Fire Barrier Shielding Structural Support Material Concrete Concrete Concrete Concrete PST -Reinforced Concrete -I Missile Barrier I Concrete WPS-Exposed to Air Outdoor Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation I'. + . :1: 1: .I I j' ,I" I I ' ' ' : I ! Environment ,., .. " .. '.''I ,,. ,1'1!1;:11 {Ir Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) I Air Outdoor (External) Expansion and Cracking Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) I Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) Aging . NURE. G '1801-,' : '131x 11'.i' : . Note ')' . I ... ' *. '1:1'1 'I'll * ' '' *; *: r: I ,, l''n1:1Table l'l*I*.* M .. a. nager:nent1l''l'i, Item *I.Ii lte' m :1*111i:"*\ 1*l!l1i:.1. , ::.1 I '.,,, I '"1:1**1:: 'I' *1*1*1* :1 I. . '::. "," ' ::* *'1.:.'Program '''1" 111 i 11* '-!-,,,,,,11111 "' I* , .1 ... I''*):'.**} ,1 I ., !,,* Structures Monitoring Program Alkali-Silica Reaction (ASR) Monitoring Program Building Deformation Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program lll.A3-2 (T-03) lll.A3-10 (T-06) lll.A3-10 (T-06) lll.A3-10 (T-06) lll.A3-9 (T-04) 3.5.1-27 3.5.1-24 3.5.1-24 3.5. 1-24 3.5.1-23 A, E, 517, 519 A A A A SBK-L-17155 I Enclosure 2/ Page 188 U.S. Nuclear Regulatory Commission ;*I Component Typ,e Intended Function PST -Reinforced Concrete -Shelter, WPS-Exposed to Air Outdoor Protection PST -Reinforced Concrete -WPS-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, WPS-Exposed to Air Outdoor Protection PST -Reinforced Concrete -WPS-Exposed to Air Outdoor Missile Barrier ,;1 Material Concrete Concrete Concrete Concrete Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation IH' :;* Environment Aging Effect Requiring ' Management \l l'i' 111 Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor (External) Expansion and Cracking Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) '1''*'Aging 'l ;1: 'y, i'I, li' . ' ' Table *, *!::t1!1: Management NUREG 1801 3.X.1 Note.i11:il:f'! Vol. 2 Item ' :II Program Item '
+* 1:1:1 Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program Alkali-Silica Reaction (ASR) 111.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program Building Deformation Monitoring Proaram Structures Monitoring Program Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring 3.5.1-27 Program (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 189 U.S. Nuclear Regulatory Commission ,. *intended Component Type Function 1:1 PST -Reinforced Concrete -Shelter, WPB-Exposed to Air Outdoor Protection PST -Reinforced Concrete -WPB-Exposed to Air Outdoor Missile Barrier PST -Reinforced Concrete -Shelter, WPB-Exposed to Air Outdoor Protection PST -Stainless Steel -COG-Structural Exposed to Air Indoor Support Uncontrolled PST -Stainless Steel -COG-Shelter, Exposed to Raw Water Protection PST -Stainless Steel -CEHMS-Structural Exposed to Air Outdoor Support Material ,, Concrete Concrete Concrete Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation : Aging Effect Requiring Environment Management ''.* :. Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Air Outdoor Loss of Material, Cracking (External) Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Raw Water Loss of Material (External) Air Outdoor (External) Loss of Material II '1:1,l:J:,. '. 111:1 l'I *. *l.1 *:* NUREG11ao1 * .** Tabre. Management Vol. 2 Item 3.X.1 Note I( Program Item 1''" I Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01) Nooe Building 111.82-8 Deformation (TP-5) 3.5.1-59 C, E, 520 Monitoring Program Structures Vll.H2-18 Monitoring 3.3.1-80 E, 512 Program (Ap-55) Structures 111.82-7 Monitoring (TP-6) 3.5.1-50 c Program SBK-L-17155 I Enclosure 2/ Page 190 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Stainless Steel -FSB-Structural Exposed to Air Indoor Support Uncontrolled PST -Stainless Steel -FSB-Shelter, Exposed to Raw Water Protection PST -Stainless Steel -FSB-Shelter, Exposed to Treated Borated Water Protection PST -Stainless Steel -FSB-Shelter, Exposed to Treated Borated Water Protection PST -Stainless Steel -FSB-Structural Fuel Transfer Tube in Air with Support Borated Water Leakage PST -Stainless Steel -FSB-Structural Fuel Transfer Tube in Air Indoor Support Uncontrolled Material Stainless Steel Stainless Steel Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation ,; ::':1!.j !*1:1 'l:I Environment Aging Effect Requiring Management' Air Indoor Nooe Uncontrolled Deformation/reduction in (External} structural capacity Raw Water (External) Loss of Material Treated Borated Cracking Water (External) Treated Borated Loss of Material Water (External) Air w/Borated Nooe Water Leakage Deformation/reduction in (External) structural capacity Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity h Aging 'i::' 1.l,:1*1 :1:1 I' ,, NUREG 1801 Table , Managemept 111 Vol. 21tem 3.X.1 Note Program lt!'!m Nooe Building lll.B2-8 Deformation (TP-5) 3.5.1-59 C, E, 520 Monitoring Program Structures Vll.H2-18 Monitoring (Ap-55) 3.3.1-80 E, 512 Program Water Chemistry lll.A5-13 A, 3.5.1-46 Program (T-14) 507,518 Water Chemistry 111.A5-13 3.5.1-46 A,518 Program (T-14) Nooe Building lll.B2-9 Deformation (TP-5) 3.5.1-59 A, E, 520 Monitoring Program Nooe Building lll.B2-8 Deformation (TP-5) 3.5.1-59 C, E, 520 Monitoring Program SBK-L-17155 /Enclosure2/Page 191 U.S. Nuclear Regulatory Commission Intended Component Type l'I ,., ,Function,, 'I I 1:1 ' 1:. PST -Stainless Steel -FSB-in Structural Air with Borated Water Leakage Support PST -Stainless Steel -PAB-Structural Exposed to Air Indoor Support Uncontrolled PST -Stainless Steel -PAB-Shelter, Exposed to Raw Water Protection PST -Stainless Steel -PAB-in Structural Air with Borated Water Leakage Support PST -Stainless Steel -WPB-Structural Exposed to Air Indoor Support Uncontrolled PST -Stainless Steel -WPB-Shelter, Exposed to Raw Water Protection Material Stainless Steel Stainless Steel Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 1, 11 1Jff 1'1' 'l'i '1'1'' , 1" ' 11". , "' , Aging Effect It Environment
+* Management: 1.,li *1 , Air w/Borated Nooe Water Leakage Deformation/reduction in (External) structural capacity Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Raw Water (External) Loss of Material Air w/Borated Nooe Water Leakage Deformation/reduction in (External) structural capacity Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Raw Water (External) Loss of Material '\ 11:1 nr' , ,1'j:'W':1:111'i'k ; 11:1 NUREG:,1so11:i:I 111 , VoJ.',2 1tMm1'" '':( 1,1111 :1: Note item'' 11i' ''V ,.,,1,, ,,,, , Program IJ11111 '1111:! ' ,,, "'1 ' Hii:'' Nooe Building lll.B2-9 Deformation (TP-5) 3.5.1-59 A, E, 520 Monitoring Program Nooe Building lll.B2-8 Deformation (TP-5) 3.5.1-59 C, E, 520 Monitoring Program Structures Vll.H2-18 Monitoring (Ap-55) 3.3.1-80 E, 512 Program Nooe Building lll.B2-9 Deformation (TP-5) 3.5.1-59 A, E, 520 Monitoring Program Nooe Building lll.B2-8 Deformation (TP-5) 3.5.1-59 C, E, 520 Monitoring Program Structures Vll.H2-18 Monitoring (Ap-55) 3.3.1-80 E, 512 Program SBK-L-17155 I Enclosure 2/ Page 192 U.S. Nuclear Regulatory Commission Intended Component Type Function PST -Stainless Steel -WPB-in Structural Air with Borated Water Leakage Support PST -Tech Spec CEVA Seal -Structural EFP-Exposed to Air Indoor Pressure Uncontrolled Barrier PST -Tech Spec CEVA Seal -Structural EFP-Exposed to Air Outdoor Pressure Barrier PST -Tech Spec CEVA Seal -Structural FSB-Exposed to Air Indoor Pressure Uncontrolled Barrier PST -Tech Spec CEVA Seal -Structural PAB-Exposed to Air Indoor Pressure Uncontrolled Barrier PST -Tech Spec CEVA Seal -Structural PAB-Exposed to Air Outdoor Pressure Barrier Material Stainless Steel Elastomer Elastomer Elastomer Elastomer Elastomer Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation 'I: Aging Effect Requidng Environment Management Air w/Borated NeRe Water Leakage Deformation/reduction in (External) structural capacity Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, (External) Shrinkage and Loss of Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, (External) Shrinkage and Loss of Strength *1 *' ' Aging NUREG 1801 Table Management 3.X.1 Note Program Vol. 2 Item Item NeRe Building lll.B2-9 Deformation (TP-5) 3.5.1-59 A, E, 520 Monitoring Program Structures Vll.G-1 Monitoring (A-19) 3.3.1-61 E, 515 Program Structures Vll.G-2 Monitoring (A-20) 3.3.1-61 E, 515 Program Structures Vll.G-1 Monitoring (A-19) 3.3.1-61 E, 515 Program Structures Vll.G-1 Monitoring (A-19) 3.3.1-61 E, 515 Program Structures Vll.G-2 Monitoring (A-20) 3.3.1-61 E, 515 Program SBK-L-17155 I Enclosure 2/ Page 193 U.S. Nuclear Regulatory Commission Intended* Component Type Function PST -Tech Spec CEVA Seal -Structural PCEW-Exposed to Air Indoor Pressure Uncontrolled Barrier PST -Tech Spec CEVA Seal -Structural Pressure PCEW-Exposed to Air Outdoor Barrier PST -Tech Spec Control Room Control Bldg Seal -CDG-Exposed to Air Habitability Indoor Uncontrolled PST -Tech Spec Fuel Storage Structural Building Seal -FSB-Exposed to Pressure Air Indoor Uncontrolled Barrier PST -Thermal Insulation Structural Aluminum Jacketing -FSB-in Air Support with Borated Water Leakage PST -Thermal Insulation Structural Aluminum Jacketing -PAB-in Support Air with Borated Water Leakage ' Material Elastomer Elastomer Elastomer Elastomer Aluminum Aluminum Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Environment Aging Effect Requiring Management Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Outdoor Increased Hardness, Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air Indoor Increased Hardness, Uncontrolled Shrinkage and Loss of (External) Strength Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Aging NUREG 1801 Table Management 3.X.1 Note' Program Vol. 2 Item Item Structures Vll.G-1 Monitoring (A-19) 3.3. 1-61 E, 515 Program Structures Vll.G-2 Monitoring 3.3. 1-61 E, 515 Program (A-20) Structures Vll.G-1 Monitoring (A-19) 3.3. 1-61 E, 515 Program Structures Vll.G-1 Monitoring (A-19) 3.3. 1-61 E, 515 Program Boric Acid lll.B2-6 Program (TP-3) 3.5. 1-55 A Boric Acid lll.B2-6 Program (TP-3) 3.5.1-55 A SBK-L-17155 I Enclosure 2/ Page 194 U.S. Nuclear Regulatory Commission *intended* Component Type Function PST -Thermal Insulation Structural Aluminum Jacketing -TFA-in Air Support with Borated Water Leakage PST -Thermal Insulation Structural Aluminum Jacketing -WPB-in Support Air with Borated Water Leakage Material Aluminum Aluminum Table 3.5.2-5 Primary Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air w/Borated Water Leakage Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) *I* ,1,,1, ,1 Aging
+* NUREG 1801 Table. Management 3.X.1 Note Program Vol. 2 Item . Item Boric Acid lll.B2-6 Program (TP-3) 3.5.1-55 A Boric Acid lll.B2-6 Program (TP-3) 3.5.1-55 A 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 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. 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&deg;C (<140&deg; 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 "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.
+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 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. 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 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 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 197 U.S. Nuclear Regulatory Commission Intended Component Type Function ASME Class 1 -Constant & Variable Load Spring Hangers -Structural Exposed to Air Indoor Support Uncontrolled ASME Class 1 -Constant & Variable Load Spring Hangers -Structural in Air with Borated Water Support Leakage ASME Class 1 -Lubrite -Structural Exposed to Air Indoor Uncontrolled Support ASME Class 1 -Pipe Supports -Structural Concrete -Exposed to Air Indoor Support Uncontrolled ASME Class 1 -Stainless Steel -Exposed to Air Indoor Structural Uncontrolled Support Material Steel Steel Lubrite Concrete Stainless Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation Aging 'Effect Requiring Environment Management Air Indoor Uncontrolled Loss of Mechanical Function (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Mechanical Function (External) Air Indoor Reduction in Concrete Anchor Uncontrolled Capacity (External) Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Aging .. NUREG I Table Management, 1801 2
+* 3.X.1 Note Program Item Item ASME Section XI, Subsection 111.81 .1-2 3.5.1-54 A IWF Program (T-28) Boric Acid Corrosion 111.81 .1-14 3.5.1-55 A Program (T-25) ASME Section 111.81 .1-5 XI,, Subsection 3.5.1-56 A IWF Program (T-32) Structures Monitoring Program, Alkali-111.81 .1-1 Silica Reaction (T-29) 3.5.1-40 A, E, 517 (ASR) Monitoring Program Nooe Structures Monitoring Program, 111.81 .1-9 3.5.1-59 A, E, 520 Building (TP-5) 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 Evaluation 1 1 t d d 1: . f:I 1 / 1 . A . . Eff t R . . Aging
+* NUREG Table Component Type Fn ent.e Material 1Environ1ment:!11il 11,il' gingM. ec equtmng Management 1801 Vol. *2 .3.X.1 Note unc ion 1 :i , .. iJil!, anagemen ,, . , p ,*1t . ''i* <<"'It 'I' . I' ,.. ,., .... ', :1:.1,1.1, * .i 1.,
+* T * .rogram 111. . .e(Tl ,1,1:: 1::1: .. , em * :1:11* I iii *1* ,,l,1 I . ,, ,!.;, .I. ,, I * ,I, Id Nooe Structures . . Monitoring ASME Class 1 -Stam less Steel St t 1 St . 1 Air w/Borated Nooe p 111 B1 1 10 -in Air with Borated Water ess Water Leakage Deformation! in (T.P-4) -3.5. 1-59 A, E, 520 Leakage PP (External) structural capacity 0 & gt* e1orma ion Monitoring Program ASME Class 1 Support -Carbon St t 1 Air Indoor ASME Section 111 B1 1 _13 Steel -Exposed to Air Indoor Steel Uncontrolled Loss of Material XI, Subsection 3.5.1-53 A Uncontrolled PP (External) IWF Program ASME Class 1 Support -Carbon St t 1 Air w/Borated Boric Acid 111 B1 1_14 Steel -in Air with Borated Steel Water Leakage Loss of Material Corrosion 3.5. 1-55 A Water Leakage PP (External) Program ASME Class 2/3 -.constant and Air Indoor ASME Section Variable Load Spring Hangers -Structural . . . lll.B1 .2-2 E d t A 1 d S rt Steel Uncontrolled Loss of Mechanical Function XI, Subsection (T 28) 3.5. 1-54 A xpose o 1r n oar uppo (External) IWF Program -Uncontrolled ASME Class 2/3 -.constant & Air w/Borated Boric Acid Variable Load Spring Hangers -Structural St 1 W t L k L f M t . 1 C . 111.B1 .2-11 3 5 1 55 A . A' 'th B t d W t S rt ee a er ea age ass o a eria orros1on (T 25) . . -Lin ktr wt ora e a er uppo (External) Program -ea age ASME Class 2/3 -Lubrite -St t I Air Indoor ASME Section Ill B1 2_3 Exposed to Air Indoor Lubrite Uncontrolled Loss of Mechanical Function XI, Subsection 3.5.1-56 A Uncontrolled PP (External) IWF Program SBK-L-17155 I Enclosure 2/ Page 199 U.S. Nuclear Regulatory Commission Component Type Intended Function ASME Class 2/3 Pipe Supports Structural -Concrete -Exposed to Air Support Indoor Uncontrolled ASME Class 2/3 -Stainless Steel -Exposed to Air Indoor Structural Uncontrolled Support ASME Class 2/3 -Stainless Structural Steel -in Air with Borated Support Water Leakage ASME Class 2/3 -Stainless Structural Steel -in Raw Water Support ASME Class 2/3 -Stainless Structural Steel -in Raw Water Support Material Concrete Stainless Steel Stainless Steel Stainless Steel Stainless Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation 'i'i Environment . Aging 'Effe.c:t Management Air Indoor Reduction in Concrete Anchor Uncontrolled Capacity (External) Air Indoor Nooe Uncontrolled Deformation/ reduction in (External) structural capacity Air w/Borated Water Leakage None (External) Raw Water Loss of Material (External) Raw Water (External) Loss of Material Aging NU REG Table Management 1801*Vol.2 1:13.X.1 '"1: Note Program Item Item Structures Monitoring Program, Alkali-111.81 .2-1 Silica Reaction (T-29) 3.5.1-40 A, E, 517 (ASR) Monitoring Program Nooe Structures Monitoring Program, 111.81 .2-7 3.5.1-59 A, E, 520 Building (TP-5) Deformation Monitoring Program Boric Acid 111.81 .2-11 Corrosion (TP-25) 3.5.1-55 A Program ASME Section 111.81.1-11 H, 509, XI, Subsection 3.5.1-49 IWF Program (TP-10) 514 ASME Section 111.81 .1-11 XI, Subsection (TP-10) 3.5.1-49 A, 509 IWF Program SBK-L-17155 I Enclosure 2/ Page 200 U.S. Nuclear Regulatory Commission Intended Component Type Function l*j .:1: ASME Class 2/3 -Stainless Structural Steel -in Treated Water Support ASME Class 2/3 Support -Structural Carbon Steel -Exposed to Air Support Indoor Uncontrolled ASME Class 2/3 Support Structural Carbon Steel -in Air with Support Borated Water Leakage Baral Poison Sheet in Spent Absorb Fuel Racks -in Treated Water Neutrons Emergency Diesel Generator Structural (EOG) -Concrete -Exposed to Support Air Indoor Uncontrolled Emergency Diesel Generator Structural (EOG) -Lubrite -Exposed to Support Air Indoor Uncontrolled Material Ii Stainless Steel Steel Steel Bora I Concrete Lubrite Table 3.5.2-6 Supports Summary of Aging Management Evaluation :I; ;1:1:!i 11 Environment ' 1 Management .,. 1 .1: .i: . , I . . " ::: Treated Borated Loss of Material Water (External) Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Treated Borated Reduction of Neutron Absorbing Water (External) Capacity and Loss of Material Air Indoor Reduction in Concrete Anchor Uncontrolled Capacity (External) Air Indoor Uncontrolled Loss of Mechanical Function (External) , *f *"' . *11 ., 1111'1INUREG i1: I 1:1* 1:1:1 ijAging '" i .1:j1;1 " I I *.:, 'I ::Note :111, ' ' ':Ii 1 ao1 lv;o1.;.2, . 3.X.1 , .. ,, 'I I'' 1 Item' ,, *1:.: ' .. 11 ,. I',,. 'Program "'ilil' 11 1111 ltelljl 1.
+* Water Chemistry lll.A5-13 3.5.1-46 A Program (T-14) ASME Section lll.B1.2-10 XI, Subsection (T-24) 3.5.1-53 A IWF Program Boric Acid lll.B1 .2-11 Corrosion (TP-25) 3.5.1-55 A Program Baral Monitoring Vll.A2-5 3.3.1-13 A Program (A-88) Structures Monitoring Program, Alkali-lll.B4-1 Silica Reaction (T-29) 3.5.1-40 A, E, 517 (ASR) Monitoring Program Structures lll.B4-2 Monitoring (TP-1) 3.5.1-52 A Program SBK-L-17155 I Enclosure 2/ Page 201 U.S. Nuclear Regulatory Commission ., ,: '.I Intended *'component Type Function Emergency Diesel Generator (EOG) Support -Carbon Steel -Structural Exposed to Air Indoor Support Uncontrolled HVAC System Components -Structural Exposed to Air Outdoor Support HVAC System Components -Structural Exposed to Air Outdoor Support HVAC System Components -Structural Exposed to Air Outdoor Support l*I Material Steel Concrete Concrete Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation ' :, ',iJ 1'1 t*' :1:1'! I 1111:11,1 'ij., *
+* 11 :1'111111" :I Management 1:! ,,, . , ' *'j'I ' l::l:l'l:l"i:i'':* i'l'!:HJ: 'li1 :1:111: Air Indoor Uncontrolled Loss of Material (External) Air Outdoor Reduction in Concrete Anchor (External) Capacity Air Outdoor Expansion and cracking (External) Air Outdoor Deformation/reduction in (External) structural capacity :1 Aging NU REG Table Management 1801,Vol.2 1*:J.X.1Vci/. 1:1 Note '*** Prog,ram ;;,, 1:. j;1:': I ' ,' : T :.. . ,1 111 : Structures Monitoring 111.84-10 3.5.1-39 A Program (T-30) Structures Monitoring Program, Alkali-111.84-1 Silica Reaction 3.5.1-40 A, E, 517 (ASR) (T-29) Monitoring Program Structures Monitoring Program, Alkali Silica Reaction (ASR) 111.84-1 A,E, Monitoring 3.5.1-27 Program & (T-29) 517, 519 Building Deformation Monitoring Program Building Deformation lll.B4-1 3.5.1-61 A, E, 520 Monitoring (T-29) Program SBK-L-17155 I Enclosure 2/ Page 202 U.S. Nuclear Regulatory Commission 'Intended Component Type Function 1:i HVAC System Components -Structural Exposed to Air Indoor Support New Fuel Storage Racks Support -Carbon Steel -Structural Exposed to Air Indoor Support Uncontrolled New Fuel Storage Racks Structural Support -Carbon Steel -in Air Support with Borated Water Leakage Non-ASME -Constant and Variable Load Spring Hangers -Structural Exposed to Air Indoor Support Uncontrolled Non-ASME -Constant and Variable Load Spring Hangers -Structural in Air with Borated Water Support Leakage . ' Material w1: **. Steel Steel Steel Steel Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation ,'.!.' Aging Effect Requiring " Environment Management Air Indoor Deformation/reduction in (External) structural integrity Air Indoor Uncontrolled Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Mechanical Function (External) Air w/Borated Water Leakage Loss of Material (External) ';!Aging 1:1 :1: *1 '1 ''111 111.1J*1,,:111: Table .:rl:r 1 Management . 1801 Vol. 2 3.X.1 Program Item Item Note, j;i Building Deformation /11.84-1 3.5.1-61 A, E, 519 Monitoring (T-29) Program Structures Monitoring Vll.A1-1 3.3.1-86 A Program (A-94) Boric Acid lll.B5-8 Corrosion (T-25) 3.5.1-55 A Program Structures Monitoring lll.B1.2-2 3.5.1-54 H, 514 Program (T-28) Boric Acid Corrosion lll.B1 .2-11 3.5.1-55 A Program (T-25)
+SBK-L-17155 I Enclosure 2/ Page 203 U.S. Nuclear Regulatory Commission *1. Intended Component Type Function. Non-ASME Piping & Components -Concrete -Structural Exposed to Air Indoor Support Uncontrolled Non-ASME Piping & Structural Components -Concrete -Support Exposed to Air Outdoor Non-ASME Piping & Components -Lubrite -Structural Exposed to Air Indoor Support Uncontrolled Non-ASME -Stainless Steel -Structural Exposed to Air Indoor Support Uncontrolled Material Concrete Concrete Lubrite Stainless Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation * '1'1 :i:' I I Aging ,Effect Requiring Environment ' 1111 . I :J: .1 *1 +111.:IJ .. '1' Air Indoor Reduction in Concrete Anchor Uncontrolled Capacity (External) Air Outdoor Reduction in Concrete Anchor (External) Capacity Air Indoor Uncontrolled Loss of Mechanical Function (External) Nooe Air Indoor Deformation/reduction in Uncontrolled structural integrity (External) Aging NU REG 'Table 11so1 vo1. 2 * . .
+* Management 3.X;1 Note 1,f 1_1,1w Program*, ,i1' Ii :1* Structures Monitoring Program, Alkali-111.82-1 Silica Reaction (T-29) 3.5.1-40 A, E, 517 (ASR) Monitoring Program Structures Monitoring Program, Alkali-111.82-1 Silica Reaction (T-29) 3.5.1-40 A,E,517 (ASR) Monitoring Program Structures Monitoring 111.82-2 3.5.1-52 A (TP-1) Program Nooe Structures Monitoring Program, & 111.81 .2-8 Building (TP-4) 3.5.1-59 A, E, 520 Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 204 U.S. Nuclear Regulatory Commission " *' Componenf Type Intended 'Function Non-ASME Support -Carbon Structural Steel -Exposed to Air Indoor Support Uncontrolled Non-ASME Support -Carbon Structural Steel -Exposed to Air Outdoor Support Non-ASME Support -Carbon Structural Steel -in Air with Borated Support Water Leakage Panels -Aluminum -Exposed Structural to Air Indoor Uncontrolled Support Panels -Aluminum -in Air with Structural Borated Water Leakage Support Panels -Carbon Steel -Structural Exposed to Air Indoor Support Uncontrolled *I Material '1!11 ;!'I Steel Steel Steel Aluminum Aluminum Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation 1Eriv,ironment Aging Effect Requiring r'. ,, Management 1* 1. 1111 Air Indoor Uncontrolled Loss of Material (External) Air Outdoor Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Noo* Uncontrolled Deformation/reduction in (External) structural capacity Air w/Borated Water Leakage Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Aging ,\'1l':1:ri NU REG Table Management 1801Vol.2 3.X.1 Note"':,. Program Item Item Structures lll.B2-10 Monitoring (T-30) 3.5.1-39 A Program Structures lll.B2-10 Monitoring 3.5.1-39 A Program (T-30) Boric Acid lll.B2-11 Corrosion (T-25) 3.5.1-55 A Program Noo* Structures Monitoring Program & lll.B3-2 3.5.1-58 A, E, 520 Building (TP-8) Deformation Monitoring Program Boric Acid lll.B3-4 Corrosion (T-3) 3.5.1-55 A Program Structures lll.B3-7 Monitoring (T-30) 3.5.1-39 A Program SBK-L-17155 I Enclosure 2/ Page 205 U.S. Nuclear Regulatory Commission Intended Component Type, ,1, Function ' I Panels -Carbon Steel -Exposed Structural to Air Outdoor Support Panels -Carbon Steel -in Air Structural with Borated Water Leakage Support Panels -Concrete -Exposed to Structural Air Indoor Uncontrolled Support Panels -Concrete -Exposed to Structural Air Outdoor Support Material ':1: .:1* '.1:. Steel Steel Concrete Concrete Table 3.5.2-6 Supports Summary of Aging Management Evaluation !'],''* .:11'1'11''.,:I' ' 11Vl ,11'11i.1'Jt' Aging Effect Environment Management ' ' Air Outdoor Loss of Material (External) Air w/Borated Water Leakage Loss of Material (External) Air Indoor Reduction in Concrete Anchor Uncontrolled Capacity (External) Air Outdoor Reduction in Concrete Anchor (External) Capacity ,'1'1*1 111' ' ' i!]:irNGREGill11: 'l' "*'' 'If ": 1!1, I *I* I 11 I I :,j;Tabl'e* : 1 111 Ii: Management 1:. '' 1801 Yol. 21* I 3.X.111IJI Ii; '] ll'i1:1 '':I
+* Ji: Pr()g.ram1'it!I
+* 11i']i'1 .'*' i:I ,,.,,*, .. Item 1. . .,.,,,,, Structures lll.B3-7 Monitoring 3.5.1-39 A Program (T-30) Boric Acid lll.B3-8 Corrosion (T-25) 3.5. 1-55 A Program Structures Monitoring Program, Alkali-lll.B3-1 Silica Reaction (T-29) 3.5. 1-40 A, E, 517 (ASR) Monitoring Program Structures Monitoring Program, Alkali-lll.B3-1 Silica Reaction (T-29) 3.5. 1-40 A, E, 517 (ASR) Monitoring Program SBK-L-17155 I Enclosure 2/ Page 206 U.S. Nuclear Regulatory Commission Intended Component Type Function Platform -Concrete -Exposed Structural to Air Indoor Uncontrolled Support Platform -Concrete -Exposed Structural to Air Outdoor Support Platform Supports -Carbon Structural Steel -Exposed to Air Indoor Support Uncontrolled Platform Supports -Carbon Structural Steel -Exposed to Air Outdoor Support Platform Supports -Carbon Structural Steel -Exposed to Air Indoor Support Uncontrolled Material Concrete Concrete Steel Steel Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation ; ;-;I j'l:I: Jl:i 1;i.1; 111' _:j:i Aging Effect Requiring I Environment Management Air Indoor Reduction in Concrete Anchor Uncontrolled (External) Capacity Air Outdoor Reduction in Concrete Anchor (External) Capacity Air Indoor Uncontrolled Loss of Material (External) Air Outdoor Loss of Material (External) Air Indoor Deformation/reduction in Uncontrolled structural capacity (External) 1 .* Aging NUREG''lii 11 **:*Table I:! I 1801 Vol. 2 ., ' Management 1* 3.X.1 Note Program Item *lte.m Structures Monitoring Program, Alkali-111.85-1 Silica Reaction 3.5.1-40 A,E,517 (ASR) (T-29) Monitoring Program Structures Monitoring Program, Alkali-111.85-1 Silica Reaction (T-29) 3.5.1-40 A,E,517 (ASR) Monitoring Program Structures 111.85-7 Monitoring (T-30) 3.5.1-39 A Program Structures 111.85-7 Monitoring 3.5.1-39 A, 503 Program (T-30) Structures 111.85-7 Monitoring (T-30) 3.5.1-59 E, 520 Program, BD SBK-L-17155 I Enclosure 2/ Page 207 U.S. Nuclear Regulatory Commission Intended Component Type Function Platform Supports -Carbon Structural Steel -Exposed to Air Support Outdoor Platform Supports -Carbon Structural Steel -in Air with Borated Support Water Leakage Spent Fuel Rack Support -Structural Stainless Steel -in Treated Water Support Thermal Insulation Aluminum Structural Jacketing -Exposed to Air Support Indoor Uncontrolled Thermal Insulation Stainless Structural Steel Jacketing -Exposed to Air Support Indoor Uncontrolled Material Steel Steel Stainless Steel Aluminum Stainless Steel Table 3.5.2-6 Supports Summary of Aging Management Evaluation "
+* Aging Effect Requ.iring Environment Management Air Outdoor Deformation/reduction in (External) structural capacity Air w/Borated Water Leakage Loss of Material (External) Treated Borated Cracking Water (External) Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Air Indoor Nooe Uncontrolled Deformation/reduction in (External) structural capacity Aging NU REG Table Management 1801 Yol. 2 3.X.1 Note Program Item Item Structures lll.B5-7 Monitoring (T-30) 3.5.1-61 E, 520 Program, BD Boric Acid lll.B5-8 Corrosion (T-25) 3.5.1-55 A Program Water Chemistry Vll.A2-7 3.3.1-90 A, 507 Program (A-97) Nooe Building lll.B2-4 Deformation (TP-8) 3.5.1-58 A, E, 520 Monitoring Program Nooe Building lll.B2-8 Deformation (TP-4) 3.5.1-59 A, E, 520 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&deg;C (<140&deg; 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-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 (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 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 Intended Component Type Function TUR -Aluminum -in Air Indoor Structural Uncontrolled Support TUR -Built-Up Roofing -Structural Exposed to Air Outdoor Support TUR -Carbon Steel -Exposed Structural to Air Outdoor Support TUR -Carbon Steel -in Air Structural Indoor Uncontrolled Support TUR -Concrete (Sump) -Structural Exposed to Raw Water Support Material Aluminum Roofing Steel Steel Concrete Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Indoor Uncontrolled None (External) Air Outdoor Separation, Environmental (External) Degradation, Water In-Leakage Air Outdoor Loss of Material (External) Air Indoor Uncontrolled Loss of Material (External) Raw Water Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item None 111.83-2 3.5.1-58 A Structures Ill .A6-12 Monitoring 3.5.1-44 H, 505 Program, (TP-7) Structures Ill .A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures Ill .A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures Ill .A3-4 Monitoring 3.5.1-31 A, 509 Program (T-05)
+SBK-L-17155 I Enclosure 2/ Page 211 U.S. Nuclear Regulatory Commission Intended Component Type Function TUR -Concrete (Sump) -Structural Exposed to Raw Water Support TUR -Concrete -Exposed to Air Structural Outdoor Support TUR -Concrete -Exposed to Air Structural Outdoor Support TUR -Concrete -Exposed to Air Structural Outdoor Support ,!j Material Concrete Concrete Concrete Concrete Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation I Aging Effect Requiring Environment Management Raw Water (External) Expansion and Cracking Air Outdoor Cracking, Loss of Bond, Loss of (External) Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) *.Aging I. NUREG Table *:1:,:;:r: 3.x.1 ,:j' Managemen.t 1801 Vol. 2 :. Note* Program Item Item Structures Monitoring Program, Alkali-Ill .A3-2 Silica Reaction (T-03) 3.5.1-27 A, 517 (ASR) Monitoring Program Structures Ill .A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Ill .A3-2 3.5.1-27 A, 517 Silica Reaction (T-03) (ASR) Monitoring Structures Ill .A3-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 212 U.S. Nuclear Regulatory Commission Component Type Intended Function TUR -Concrete -Exposed to Air I Structural Outdoor Support TUR -Concrete -in Air Indoor Uncontrolled TUR -Concrete -in Air Indoor Uncontrolled TUR -Concrete -in Air Indoor Uncontrolled I Structural Support Structural Support I Structural Support TUR -Concrete Masonry Units -I Structural in Air Indoor Uncontrolled Support Material I Concrete I Concrete Concrete I Concrete I Concrete Block Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation Environment I Air Outdoor (External) Air Indoor I Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor I Uncontrolled (External) Air Indoor I Uncontrolled (External) * :i:1.I: : Aging Effect Requiring Management I Loss of Material, Cracking Aging Management Program 1 Structures Monitoring Program --Cracking, Loss of Bond, Loss of M .t . I . I Structures Material (Spalling, Scaling) Expansion and Cracking Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Cracking Structures Monitoring Program, AlkaliSilica Reaction (ASR) Monitoring Structures Monitoring Program Structures Monitoring Program NU REG 1801 Vol. 2 Item Ill .A3-6 (T-01) Ill .A3-9 (T-04) Ill .A3-2 (T-03) I Ill .A3-10 (T-06) I Ill .A3-11 (T-12) Table 3.X.1 Item 3.5.1-26 3.5.1-23 3.5.1-27 I 3.5.1-24 I 3.5.1-43 Note A A A, 517 IA IA SBK-L-17155 I Enclosure 2/ Page 213 U.S. Nuclear Regulatory Commission Component Type Intended Function TUR -Fire Penetration Seal -in Fire Barrier Air Indoor Uncontrolled TUR -Fire Penetration Seal -in Fire Barrier Air Indoor Uncontrolled TUR -Penetration Seal -Structural Exposed to Air Outdoor Support Material Elastomer Elastomer Elastomer Table 3.5.2-7 Turbine Building Summary of Aging Management Evaluation I' 1,i; .1,., '* ,I* Environment Aging Effect Requiring Management Air Indoor Increased Hardness, Shrinkage Uncontrolled (External) and Loss of Strength Air Indoor Increased Hardness, Shrinkage Uncontrolled (External) and Loss of Strength Air Outdoor Increased Hardness, Shrinkage (External) and Loss of Strength Aging NU REG Table Management 1801 Vol. 2 3.X.1 Note Program Item Item Fire Protection Vll.G-1 3.3.1-61 A Program (A-19) Structures Vll.G-1 Monitoring 3.3.1-61 E, 514 Program (A-19) Structures Vll.G-2 Monitoring 3.3.1-61 E, 515 Program (A-20)
+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-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&deg;C (<140&deg; 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-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 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 2/ Page 215 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Built-Up Roofing -SERVICE WATER COOLING Shelter, TOWER Including Switchgear Protection Rooms in Air Outdoor WCS -Built-Up Roofing -SERVICE WATER Shelter, PUMPHOUSE in Air Outdoor Protection WCS -Carbon Steel Door -SERVICE WATER COOLING Shelter, TOWER Including Switchgear Protection Rooms in Air Outdoor WCS -Carbon Steel Door -SERVICE WATER COOLING Structural TWR Including Swgr Rms in Air Support Indoor Uncontrolled WCS -Carbon Steel Door -SERVICE WATER Structural PUMPHOUSE in Air Indoor Support Uncontrolled WCS -Carbon Steel Door -Shelter, SERVICE WATER Protection PUMPHOUSE in Air Outdoor Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Material Environment Management Separation, Environmental Air Outdoor Roofing (External) Degradation, Water In-Leakage Separation, Environmental Roofing Air Outdoor Degradation, Water In-(External) Leakage Steel Air Outdoor Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel (External) Loss of Material *:11 Aging NUREG.11801 Tab Management Vol. 2 Item 3.X.1 Note Program Item I Structures Monitoring Program, Building lll.A6-12 H, 505, Deformation (TP-7) 3.5.1-44 E, 520 Monitoring Program Structures Monitoring Program, Building lll.A6-12 3.5.1-44 H, 505, Deformation (TP-7) E, 520 Monitoring Program Structures Monitoring lll.A3-12 3.5.1-25 A, 503 (T-11) Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A Program Structures lll.A3-12 Monitoring (T-11) 3.5.1-25 A, 503 Program SBK-L-17155 I Enclosure 2/ Page 216 U.S. Nuclear Regulatory Commission Component Type Intended Function WCS -Carbon Steel Fire Door -SERVICE WATER COOLING Fire Barrier TWR Including Swgr Rms in Air Indoor Uncontrolled WCS -Carbon Steel Fire Door -SERVICE WATER Fire Barrier PUMPHOUSE in Air Indoor Uncontrolled WCS -Carbon Steel -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms in Support Air Outdoor WCS -Carbon Steel -SERVICE Structural WATER COOLING TOWER in Support Raw Water WCS -Carbon Steel -SERVICE Structural WATER COOLING TOWER in Support Raw Water WCS -Carbon Steel -SERVICE Structural WATER COOLING TOWER in Support Raw Water Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation 1:l ''I: '*' :, . Fl"I' Material Environment ''Aging Effect Requiring Management Air Indoor Steel Uncontrolled Loss of Material (External) Air Indoor Steel Uncontrolled Loss of Material (External) Steel Air Outdoor Loss of Material (External) Raw Water Steel (External) Loss of Material Raw Water Steel (External) Loss of Material Raw Water Steel (External) Loss of Material Aging n* .Jable Management NUREG 18P1 *:3.X.1 Note Program Vol. 2 Item ltein Fire Protection Vll.G-3 3.3. 1-63 A Program (A-21) Fire Protection Vll.G-3 3.3. 1-63 A Program (A-21) Structures Monitoring lll.A3-12 3.5. 1-25 A, 503 (T-11) Program Structures 111.A6-11 Monitoring (T-21) 3.5.1-47 E, 511 Program Structures lll.A6-11 Monitoring (T-21) 3.5.1-47 E, 511 Program Structures 111.A6-11 Monitoring (T-21) 3.5.1-47 H, 511 Program SBK-L-17155 I Enclosure 2/ Page 217 U.S. Nuclear Regulatory Commission Component Type WCS -Carbon Steel -SERVICE WATER COOLING TOWER in Raw Water WCS -Carbon Steel -SERVICE WATER COOLING TWR Including Swgr Rms in Air Indoor Uncontrolled WCS -Carbon Steel -SERVICE WATER PUMPHOUSE in Air Indoor Uncontrolled WCS -Carbon Steel -SERVICE WATER PUMPHOUSE in Raw Water WCS -Carbon Steel -SERVICE WATER PUMPHOUSE in Raw Water WCS -Carbon Steel -SERVICE WATER PUMPHOUSE in Raw Water Intended Function Structural Support Structural Support Structural Support Structural Support Structural Support Structural Support Material Steel Steel Steel Steel Steel Steel Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Raw Water (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Raw Water (External) Raw Water (External) Raw Water (External) . I -; ... , .Table .. , * . Agmg NUREG 180,111 1 :::,3* x*. I ' * * ' ' 'II I 1:11:1!11.,. *, *1* '.A. g __ in_ g
+* I . ' M_
+* anagemen_ t. *I.* "Vol_:_,z_ ltery:i_ wi" I'' . ,, Item* .. ; . *:1:1: Management ''"1**' 1*1, * *l:i1Program ,, *1:. , "I* l:i:."1 :1 *1* " '1* I .. J, *,*1*::1:i:1: *1;1 :1; . !* ' ' ' 1. iii I Ii. Note 1: Loss of Material Loss of Material Loss of Material Loss of Material Loss of Material Loss of Material Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program lll.A6-11 (T-21) lll.A3-12 (T-11) lll.A3-12 (T-11) lll.A6-11 (T-21) lll.A6-11 (T-21) lll.A6-11 (T-21) 3.5.1-47 I E, 511 3.5.1-25 I A 3.5.1-25 I A 3.5. 1-47 I E, 511 3.5. 1-47 I E, 511 3.5.1-47 I H, 511 SBK-L-17155 I Enclosure 2/ Page 218 U.S. Nuclear Regulatory Commission *1;. , Intended' Component Type Function '',' 1 ' ' WCS -Carbon Steel -SERVICE Structural WATER PUMPHOUSE in Raw Support Water WCS -Carbon Steel -SERVICE Shelter, WATER PUMPHOUSE Siding in Air Indoor Uncontrolled Protection WCS -Carbon Steel -SERVICE Shelter, WATER PUMPHOUSE Siding in Air Outdoor Protection WCS -Concrete -Structural CIRCULATING WATER PUMPHOUSE Below Grade Support WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE Below Grade Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation ,I ,I :j:'J',, ,' ,,, j.11, :t Aging Effect Requirir;ig ,, , Material Environment Management '1 '!:'" ii: ; ' Raw Water Steel (External) Loss of Material Air Indoor Steel Uncontrolled Loss of Material (External) Air Outdoor Steel Loss of Material (External) Ground Cracking, Loss of Bond, Loss Concrete Water/Soil (External) of Material (Spalling, Scaling) Ground Concrete Water/Soil Expansion and Cracking (External) ,;p,, ''IA. I :I l'l'I 'if:, ''11 'I ilJ1:1j 11'*1T bl I:*, i 1:11:, ,,mog 'i: ,;lil:i :1:1 NUREG*l1 aotl ii ,1, ,., , a 1e,, lffl Note Management :::,, ::1ti:**l1*t.1 t'11l**1 'I'' ,: ' 113.X.11:1 i' Program. ,. ' 1 Nol;1 2 Item ,' 1!,,:'::111,i I, ., I* ltem1. :. 1:1, ' " Structures lll.A6-11 Monitoring (T-21) 3.5.1-47 E, 511 Program Structures lll.A3-12 Monitoring 3.5.1-25 A Program (T-11) Structures lll.A3-12 Monitoring 3.5.1-25 A, 503 Program (T-11) Structures 111.A3-4 Monitoring 3.5. 1-31 A Program (T-05) Structures Monitoring Program , Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5. 1-27 517, 519 Program & Building Deformation Monitoring Proaram SBK-L-17155 I Enclosure 2/ Page 219 U.S. Nuclear Regulatory Commission lntende'd tlii ' Component Type Function WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE Below Grade WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE Below Grade WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE Below Grade WCS -Concrete -CIRCULATING WATER Structural PUMPHOUSE in Air Indoor Support Uncontrolled WCS -Concrete -CIRCULATING WATER Structural PUMPHOUSE in Air Indoor Support Uncontrolled " 1:111 i:. 1Material 111 1*1 ' Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation '1'1Environment Aging Effect Requiring 11 ;(:1 :I::. Ah:', 1 I; Management ,1*1 .. 1!' ""' ,,, ,,. Ground Increase in Porosity and Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Water/Soil Permeability, Loss of (External) Strength Ground Water/Soil Loss of Material, Cracking (External) Air Indoor Uncontrolled Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) (External) Air Indoor Uncontrolled Expansion and Cracking (External) .1 I J1 lJ I 1*1 :j ,.'"J:,'i'' l*lll,,1':1 "'1'1' tTablel".i:i:' ,;j: 111: il:I, . ' Aging:iJ , . NUREG 1801 'I' 'Ii .Iii Management1 3.X.1 1Notelil'I'' Vol. 2 Item Program Item , t1/m1****., :1 Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures Monitoring lll.A3-9 3.5.1-23 A (T-04) Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Proqram SBK-L-17155 I Enclosure 2/ Page 220 U.S. Nuclear Regulatory Commission Intended Component Type Function *1:1 WCS -Concrete -CIRCULATING WATER Structural PUMPHOUSE in Air Indoor Support Uncontrolled WCS -Concrete -Shelter, CIRCULATING WATER PUMPHOUSE in Air Outdoor Protection WCS -Concrete -CIRCULATING WATER Shelter, Protection PUMPHOUSE in Air Outdoor WCS -Concrete -Shelter, CIRCULATING WATER Protection PUMPHOUSE in Air Outdoor WCS -Concrete -Shelter, CIRCULATING WATER PUMPHOUSE in Air Outdoor Protection Material 'I' Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation ii! I 11m '1:1:1,!i I I'll', ' ' A in 'I Effect Re uirin , Environment . I *,:l.g lgl, l'l.1.1." 1111*.q :* .. 1: *lgl*I: !*1'l1 1 Management1:1 *1 {
+* I J .I . Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor Loss of Material, Cracking (External) ;i.1 Aging Table 111:1 NUREG 180,1, .1: '3.:X.1 H1: Management V I I 111* Note H. :I. ' , .,: ' ' ilj I ii:?  "/Tu:m !*,:," l1f ' 11:1 1:1!: },. 1.:1!ji1*.;1:-* ep11n1. i' Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures 111.A3-9 Monitoring 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-6 Monitoring 3.5.1-26 A Program (T-01)
+SBK-L-17155 I Enclosure 2/ Page 221 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE in Raw Water WCS -Concrete -CIRCULATING WATER Structural Support PUMPHOUSE in Raw Water WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE in Raw Water WCS -Concrete -Structural CIRCULATING WATER Support PUMPHOUSE in Raw Water WCS -Concrete -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms Support Below Grade Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation I Aging Effect Requiring Environment Management Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water Expansion and Cracking (External) Raw Water Increase in Porosity and (External) Permeability, Loss of Strength Raw Water (Extern a!) Loss of Material Ground Water/Soil Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) *,Agiri'9'J, ilt, ,11!1,. *11i:l:1*1*1:t::l1* ,, + ii ,I'' .. NUREG 18011 Management Vol. 2 Item 3.X.1 Note .. Program Item Structures lll.A3-4 Monitoring (T-05) 3.5.1-31 A, 509 Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A Program Structures lll.A6-7 Monitoring (T-20) 3.5.1-45 E, 511 Program Structures Monitoring lll.A3-4 3.5.1-31 A Program (T-05)
+SBK-L-17155 I Enclosure 2/ Page 222 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Concrete -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms Support Below Grade WCS -Concrete -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms Support Below Grade WCS -Concrete -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms Support Below Grade WCS -Concrete -SERVICE WATER COOLING TOWER Structural Including Switchgear Rooms Support Below Grade WCS -Concrete -SERVICE WATER COOLING TOWER Missile Barrier Including Switchgear Rooms in Air Outdoor Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Effect Requiring' 'l Material Environment Management Ground Concrete Water/Soil Expansion and Cracking (External) Ground Increase in Porosity and Concrete Water/Soil Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Ground Increase in Porosity and Concrete Water/Soil Permeability, Loss of (External) Strength Ground Concrete Water/Soil Loss of Material, Cracking (External) Cracking, Loss of Bond, Loss Concrete Air Outdoor (External) of Material (Spalling, Scaling) *';1::1l'i1Agin'g II l:i: :li:ll'"' '1:l:::,,:al:111l:1:*1:1::1 l' ,11 1:1: .liable ;;* ' Management . NLJREG, 1801, '*3.X.1 " Note iJ Vol. 2 Item *Item Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) A, E, Monitoring lll.A3-2 3.5.1-27 Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-5 Monitoring (T-07) 3.5.1-31 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A, 509 Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-9 Monitoring (T-04) 3.5.1-23 A Program SBK-L-17155 I Enclosure 2/ Page 223 U.S. Nuclear Regulatory Commission r ' *I* !:I Component Type Intended Function WCS -Concrete -SERVICE WATER COOLING TOWER Shelter, Including Switchgear Rooms in Protection Air Outdoor WCS -Concrete -SERVICE WATER COOLING TOWER Missile Barrier Including Switchgear Rooms in Air Outdoor WCS -Concrete -SERVICE WATER COOLING TOWER Shelter, Including Switchgear Rooms in Protection Air Outdoor WCS -Concrete -SERVICE WATER COOLING TOWER Including Switchgear Rooms in Missile Barrier Air Outdoor ,, :i: Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation ;1: Aging Effect Requiring Environmer:it Management ii. Jfli] ' ljjlll ,. 'I' Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Air Outdoor (External) Expansion and Cracking Increase in Porosity and Air Outdoor (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) 'Aging I* l'.I . ' '".*'*I* .,.1 . l'li'll1''1111li . NUREG 1801' Table* *'*1' Ji ,::,-:.:Ii :j:l'*11: Management 3.X.1 . "Ir Vol. 2 Item Notet'*i!ii:I Program Item :I:: :J:1 Structures Monitoring lll.A3-9 3.5.1-23 A Program (T-04) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Proaram Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 224 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Concrete -SERVICE WATER COOLING TOWER Shelter, Including Switchgear Rooms in Protection Air Outdoor WCS -Concrete -SERVICE WATER COOLING TOWER Missile Barrier Including Switchgear Rooms in Air Outdoor WCS -Concrete -SERVICE WATER COOLING TOWER Shelter, Including Switchgear Rooms in Protection Air Outdoor WCS -Concrete -SERVICE Structural WATER COOLING TOWER in Raw Water Support WCS -Concrete -SERVICE Ultimate Heat WATER COOLING TOWER in Sink Raw Water WCS -Concrete -SERVICE Structural WATER COOLING TOWER in Support Raw Water Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation iji ' *'*1: I 11
+* Aging Effect Requiring Material Environment Increase in Porosity and Concrete Air Outdoor Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Concrete Air Outdoor Loss of Material, Cracking (External) Concrete Air Outdoor Loss of Material, Cracking (External) Cracking, Loss of Bond, Loss Raw Water Concrete (External) of Material (Spalling, Scaling) Cracking, Loss of Bond, Loss Raw Water Concrete (External) of Material (Spalling, Scaling) Raw Water Concrete (External) Expansion and Cracking Aging Table :1:, NUREG 1801 Management 3.X.1 Note Vol. 2 Item Program Item Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-6 Monitoring (T-01) 3.5. 1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5. 1-26 A Program Structures lll.A3-4 Monitoring 3.5. 1-31 A, 509 (T-05) Program Structures lll.A3-4 Monitoring 3.5.1-31 A, 509 (T-05) Program Structures Monitoring Program, Alkali-.Silica Reaction (ASR) lll.A3-2 3.5.1-27 A, E, Monitoring (T-03) 517, 519 Program & Building Deformation Monitorina SBK-L-17155 I Enclosure 2/ Page 225 U.S. Nuclear Regulatory Commission ll' Component Type Intended Function WCS -Concreti;! -SERVICE WATER COOLING TOWER in Ultimate Heat Raw Water Sink WCS -Concrete -SERVICE Structural WATER COOLING TOWER in Support Raw Water WCS -Concrete -SERVICE Ultimate Heat WATER COOLING TOWER in Sink Raw Water WCS -Concrete -SERVICE Structural WATER COOLING TOWER in Support Raw Water Material 1''*: Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Effect Requiring 1 Environment Management ',,' '1'111111111 111 11*., ':j, " ::i Raw Water Expansion and Cracking (External) Raw Water Increase in Porosity and (External) Permeability, Loss of Strength Raw Water Increase in Porosity and (External) Permeability, Loss of Strength Raw Water (External) Loss of Material I ' Aging NUREG 1801 1, Tablerll Management Vol. 2 Item 3.X.1 Program Item Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A Program Structures lll.A3-7 Monitoring (T-02) 3.5.1-32 A Program Structures lll.A6-7 Monitoring (T-20) 3.5.1-45 E, 511 Program SBK-L-17155 I Enclosure 2/ Page 226 U.S. Nuclear Regulatory Commission ,, I:' ' l: Intended I' Comppnent Type Function WCS -Concrete -SERVICE Ultimate Heat WATER COOLING TOWER in Sink Raw Water WCS -Concrete -SERVICE WATER COOLING TWR Fire Barrier Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Structural Including Swgr Rms in Air Support Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Fire Barrier Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Structural Including Swgr Rms in Air Support Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Fire Barrier Including Swgr Rms in Air Indoor Uncontrolled Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation .1: t 1:1, I *: Aging Effect Requiring Material, ill , Environment Management ii* Raw Water Concrete (External) Loss of Material Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Loss of Material (External) Air Indoor Concrete Uncontrolled Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) (External) Air Indoor Concrete Uncontrolled Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Indoor Concrete Uncontrolled Concrete Cracking and (External) Spalling I 1 11 :lb .:I: :i,(' Table' 11 \I 'I" 'II: :1,1' NUREG 1801 Management Vol. 2 Item, 3.X.1 I I: Note ''"l''I Program Item '" ' j'I J!1:.ll: Structures lll.A6-7 Monitoring (T-20) 3.5.1-45 E, 511 Program Fire Protection Vll.G-29 3.3.1-67 A Program (A-91) Fire Protection Vll.G-29 3.3.1-67 A Program (A-91) Structures Monitoring lll.A3-9 3.5, 1-23 A (T-04) Program Structures Monitoring lll.A3-9 3.5.1-23 A Program (T-04) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90)
+SBK-L-17155 I Enclosure 2/ Page 227 U.S. Nuclear Regulatory Commission *1:; Component Type r ,i;11 Intended .Function ***1 ' 1:1: ;,,, WCS -Concrete -SERVICE WATER COOLING TWR Structural Including Swgr Rms in Air Support Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Fire Barrier Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Structural Including Swgr Rms in Air Support Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Fire Barrier Including Swgr Rms in Air Indoor Uncontrolled 1;1; Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation 'ii ', I* .. *. 'Ji j:i'J:ii1 11 11 ::j:1'':*1*1;, ' Effect 'Requiring Material Environment Management ' 1 Air Indoor Concrete Uncontrolled Concrete Cracking and (External) Spalling Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Air Indoor Concrete Uncontrolled Expansion and Cracking (External) Air Indoor Concrete Uncontrolled Concrete Cracking and (External) Spalling T1*1:(H:*:1*1 ' I 1:1l: !;. I .,ii 1ii'fi!' llrli' 1'!1111 ji:llJ.i "*' i ,, *r:*. ":' !'1,*,,:i:1* ' , *. 1;111A9ingl,* Iii , ':rab!e 1,1, 11 ,, ' "' *I j:j1': 1: NUREG11801 ** , *Management H' 11 V ol.1 2 Item ., ':' .. l'I Note 11' Program Item 'jl! 'l'Jlli' f' 1: ' *::: 1::1: Fire Protection Vll.G-28 3.3. 1-65 A Program (A-90) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5. 1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5. 1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Fire Protection Vll.G-28 3.3. 1-65 A Program (A-90)
+SBK-L-17155 I Enclosure 2/ Page 228 U.S. Nuclear Regulatory Commission Component Type WCS -Concrete -SERVICE WATER COOLING TWR Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER COOLING TWR Including Swgr Rms in Air Indoor Uncontrolled WCS -Concrete -SERVICE WATER PUMPHOUSE Below Grade WCS -Concrete -SERVICE WATER PUMPHOUSE Below Grade Intended Function Structural Support Fire Barrier Structural Support Structural Support Structural Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Environment Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Ground Water/Soil (External) Ground Water/Soil (External) l;:l*i . Aging Effect Requiring 1.1 Management Concrete Cracking and Spalling Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling) Cracking, Loss of Bond, Loss of Material (Spalling, Scaling) Expansion and Cracking Aging Management'" ',Program Fire Protection Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program Structures Monitoring Program, Silica Reaction (ASR) Monitoring Program & Building Deformation Monitoring Program NUREG 1801 Vol. 2 Item Vll.G-28 (A-90) lll.A3-10 (T-06) lll.A3-10 (T-06) lll.A3-4 (T-05) lll.A3-2 (T-03) Table '' 3.X.1 Item 3.3.1-65 3.5.1-24 3.5.1-24 3.5.1-31 3.5.1-27 N.ote A A A A A,E, 517, 519 SBK-L-17155 I Enclosure 2/ Page 229 U.S. Nuclear Regulatory Commission I ,*1 Component Type, ,Intended I ! fiuriction* WCS -Concrete -SERVICE Structural WATER PUMPHOUSE Below Support Grade WCS -Concrete -SERVICE Structural WATER PUMPHOUSE Below Support Grade WCS -Concrete -SERVICE Structural WATER PUMPHOUSE Below Support Grade WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Indoor Uncontrolled Support WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled !'Jlaterial *1+1 *ii' Concrete Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Effect II:' 1:['lilJli:i1ll'l1[ 1:!:1::'1i:lil11l:11111111:1:J;1W jll 111:1*1'11 ,,, , .. Environment '1il NUREG 1,11.BOt' 11 3:X.1 'Ii '!111!1iNote .1' M , t, ,. ,* :.: 'Management 1. : "1 p ' ,, Vol. 2 Item '*1 Item 1 ' 1*i.1t.':iV:1 . ,1 , . rogram * ' . l*I 'lfJl:i;1':::*,1:1* Ground Increase in Porosity and Structures 111.A3-5 Water/Soil Permeability, Cracking, Loss Monitoring (T-07) 3.5.1-31 A (External) of Material (Spalling, Scaling) Program Ground Increase in Porosity and Structures lll.A3-7 Water/Soil Permeability, Loss of Monitoring (T-02) 3.5.1-32 A, 509 (External) Strength Program Ground Structures lll.A3-6 Water/Soil Loss of Material, Cracking Monitoring (T-01) 3.5.1-26 A (External) Program Air Indoor Fire Protection Vll.G-29 Uncontrolled Loss of Material Program (A-91) 3.3.1-67 A (External) Air Indoor Fire Protection Vll.G-29 Uncontrolled Loss of Material 3.3.1-67 A (External) Program (A-91) Air Indoor Cracking, Loss of Bond, Loss Structures lll.A3-9 Uncontrolled Monitoring 3.5.1-23 A (External) of Material (Spalling, Scaling) Program (T-04)
+SBK-L-17155 I Enclosure 2/ Page 230 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Indoor Uncontrolled Support WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Indoor Uncontrolled Support WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Support Indoor Uncontrolled Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment I' 1F,:i:I Management I', , 1 ,I Air Indoor Cracking, Loss of Bond, Loss Uncontrolled (External) of Material (Spalling, Scaling) Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Uncontrolled Expansion and Cracking (External) Air Indoor Uncontrolled Expansion and Cracking (External) Aging NUREG 1801 Table Management 3.X.1 Note Program Vol. 2 Item Item Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Proqram Structures Monitoring Program, Alkali-Silica Reaction (ASR) lll.A3-2 A, E, Monitoring (T-03) 3.5.1-27 517, 519 Program & Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 231 U.S. Nuclear Regulatory Commission ,., Intended Component Type Function WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Indoor Uncontrolled Support WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Air Support Indoor Uncontrolled WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Missile Barrier Outdoor . 'l Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation Aging Effect Requiring Environment Management Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Concrete Cracking and Uncontrolled (External) Spalling Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Indoor Increase in Porosity and Uncontrolled Permeability, Cracking, Loss (External) of Material (Spalling, Scaling) Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Aging I* " '1; *'"'1',!I NUREG 1801 Table Management Vol. 2 Item 3.X.1 Note Program Item Fire Protection Vll.G-28 3.3. 1-65 A Program (A-90) Fire Protection Vll.G-28 3.3.1-65 A Program (A-90) Structures lll.A3-10 Monitoring (T-06) 3.5. 1-24 A Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-9 Monitoring 3.5.1-23 A Program (T-04)
+SBK-L-171 SS I Enclosure 2/ Page 232 U.S. Nuclear Regulatory Commission *111:1. , "I Intended 1Type 1: Function WCS -Concrete -SERVICE Shelter, WATER PUMPHOUSE in Air Protection Outdoor WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Missile Barrier Outdoor WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Shelter, Outdoor Protection WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Missile Barrier Outdoor ii 11* Material ,1:1.1 *t *I Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation ,., Aging Effect Requiring *1Environment Management I :11 *:I* 'j,, Air Outdoor Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Air Outdoor Expansion and Cracking (External) Air Outdoor Expansion and Cracking (External) Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) , 111'1:111:1T , , '1:1 11 t , '' 'I' t* ,,JF111 '' 'I** Table ** 111 11 ' , ' .. Agmg I . , 1NUREG11ao1' ! I I ! 11 ' I Management* 3.X.1 Note 1,: Program Vol. 2 Item Item . I*, . :r i Structures 111.A3-9 Monitoring (T-04) 3.5.1-23 A Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program Structures lll.A3-10 Monitoring (T-06) 3.5.1-24 A Program SBK-L-17155 I Enclosure 2/ Page 233 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Concrete -SERVICE Shelter, WATER PUMPHOUSE in Air Protection Outdoor WCS -Concrete -SERVICE WATER PUMPHOUSE in Air Missile Barrier Outdoor WCS -Concrete -SERVICE Shelter, WATER PUMPHOUSE in Air Protection Outdoor WCS -Concrete -SERVICE Structural WATER PUMPHOUSE in Raw Water Support WCS -Concrete -SERVICE WATER PUMPHOUSE in Raw Structural Water Support Material Concrete Concrete Concrete Concrete Concrete Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation 1:i; .* !1, 1:1 '1 Environment
+* 1,1,,.1 M ,,,,*1 ... "*'' .,,,,h t''''"j"*' .1 ... 11i:1t1t1 , *
+* anagemen
+* 1.i ,, :1r1 'I :I . y ':i'I fl:!:,. Air Outdoor Increase in Porosity and (External) Permeability, Cracking, Loss of Material (Spalling, Scaling) Air Outdoor (External) Loss of Material, Cracking Air Outdoor (External) Loss of Material, Cracking Raw Water Cracking, Loss of Bond, Loss (External) of Material (Spalling, Scaling) Raw Water Expansion and Cracking (External) }','* "'*A: ... ,. .. 1.* ,J .. 1,:,", , .,.: ' Table. ' :::11:!' '"' gmg" 11!: l'E ''NUREGl1aofli, 'ii' ' ,,.,,*j1 'ji''v. 11,211t 111:,J1, n11.1.3:x.1w* ,
+* Note .... ,: ... ,, 1&deg;**."*I II j:il ,* 111111' :111Program''' +" 1 :1 ' ,. ' 'I: '*'l'l:',*:I* I** I 1*':'1** ,**,,1*!***11, .. ,i* Structures llLA3-10 Monitoring (T-06) 3.5.1-24 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-6 Monitoring (T-01) 3.5.1-26 A Program Structures lll.A3-4 Monitoring 3.5.1-31 A, 509 Program (T-05) Structures Monitoring Program, Alkali-Silica Reaction (ASR) Monitoring lll.A3-2 3.5.1-27 A, E, Program & (T-03) 517, 519 Building Deformation Monitoring Program SBK-L-17155 I Enclosure 2/ Page 234 U.S. Nuclear Regulatory Commission Component Type WCS -Concrete -SERVICE WATER PUMPHOUSE in Raw Water WCS -Concrete -SERVICE WATER PUMPHOUSE in Raw Water WCS -Fire Penetration Seal -SERVICE WATER COOLING TWR including Swgr Rms in Air Indoor Uncontrolled WCS -Fire Seal -SERVICE WATER PUMPHOUSE in Air Indoor Uncontrolled WCS -Penetration Seal -SERVICE WATER COOLING TOWER Including Switchgear Rooms in Air Outdoor WCS -Penetration Seal -SERVICE WATER PUMPHOUSE in Air Outdoor Intended Function Structural Support Structural Support Fire Barrier Fire Barrier Shelter, Protection Shelter, Protection Material Concrete Concrete Elastomer Elastomer Elastomer Elastomer Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation 'l'I 1,1,,:1:1., \ ,, . . , 1
+* Aging . , * ',,'',I ,Managem1ent}' Environment ,.,1:1:k!I: 1 :1' :I! 'j':',1 l!I* ,1, , P1rogram,'li'l,l;j!1, 1:i ;:. 1'' ' ',J1' * ' Raw Water (External) Raw Water (External) Air Indoor Uncontrolled (External) Air Indoor Uncontrolled (External) Air Outdoor (External) Air Outdoor (External) Increase in Porosity and Permeability, Loss of Strength Loss of Material Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Increased Hardness, Shrinkage and Loss of Strength Structures Monitoring Program Structures Monitoring Program Fire Protection Program Fire Protection Program Structures Monitoring Program Structures Monitoring Program *1' Table:' ... 801'1 'I '"' " '"'1 , . , Note .... '"'l'i' ,. :1,jiP!X*l: i!*l'11."*', *,1:1 , 11,vo1:1211tepi ,* *,1 H ltenili' q:, 'P:Hii'' l:'il' *1:1 ':!:1111 1 ' , I ',, 111.A3-7 (T-02) lll.A6-7 (T-20) Vll.G-1 (A-19) Vll.G-1 (A-19) Vll.G-2 (A-20) Vll.G-2 (A-20) 3,5.1-32 I A 3.5.1-45 I E, 511 3.3.1-61 I A 3.3.1-61 I A 3.3.1-61 I E, 515 3.3.1-61 I E, 515 SBK-L-17155 I Enclosure 2/ Page 235 U.S. Nuclear Regulatory Commission Intended Component Type Function WCS -Penetration Sea/ -SERVICE WATER COOLING Shelter, TOWER Including Switchgear Protection Rooms in Air Outdoor WCS -Penetration Sea/ -SERVICE WATER Shelter, Protection PUMPHOUSE in Air Outdoor WCS -Fire Penetration Seal -SERVICE WATER COOLING Fire Barrier TWR including Swgr Rms in Air Indoor Uncontrolled WCS -Fire Seal -SERVICE WATER PUMPHOUSE in Air Fire Barrier Indoor Uncontrolled Material Elastomer Elastomer Elastomer Elastomer Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation . '" '. '"' ll' ,1,11 Aging Effect'Requiring Environment Management Air Outdoor Separation (External) Air Outdoor Separation (External} Air Indoor Uncontrolled Separation (External) Air Indoor Uncontrolled Separation (External) ., Aging :1:' 'I' 111Table J 1;1
+* NUREG 1801. I " Management Vol. 2 Item 3.X.1 Note Program Item Structures Monitoring Program, Building Vll.G-2 3.5.1-60 E,520 Deformation (A-20) Monitoring Program Structures Monitoring Program, Building Vll.G-2 3.5.1-60 E, Deformation (A-20) 520 Monitoring Program Structures Monitoring Program, Building Vll.G-1 3.5.1-60 E, 520 Deformation (A-19) Monitoring Program Structures Monitoring Program, Building Vll.G-1 3.5.1-60 E, 520 Deformation (A-19) Monitoring Program SBK-L-17155 I Enclosure 2/ Page 236 U.S. Nuclear Regulatory Commission Standard Notes Table 3.5.2-8 Water Control Structures Summary of Aging Management Evaluation 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&deg;C (<140&deg; 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-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 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 (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 components by the Structures Monitoring Program, Seabrook Station will age manage this condition through the Building Deformation Monitoring Program. to SBK-L-17155 Supplement 58 -NextEra Energy Seabrook's revised LRA Appendix A -Updated Final Safety Analysis Report Supplement Table A.3, License Renewal 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 LOCATION Provide confirmation and acceptability of the 1. PWR Vessel Internals implementation ofMRP-227-A by addressing the plant-A.2.1.7 specific Applicant/Licensee Action Items outlined in section 4.2 of the NRC SER. Enhance the program to include visual inspection for 2. Closed-Cycle Cooling Water cracking, loss of material and fouling when the in-scope A.2.1.12 systems are opened for maintenance. Inspection of Overhead Enhance the program to monitor general corrosion on the Heavy Load and Light Load crane and trolley structural components and the effects of A.2.1.13 3. (Related to Refueling) Handling Systems wear on the rails in the rail system. Inspection of Overhead 4. Heavy Load and Light Load Enhance the program to list additional cranes for A.2.1.13 (Related to Refueling) monitoring. Handling Systems Enhance the program to include an annual air quality test 5. Compressed Air Monitoring requirement for the Diesel Generator compressed air sub A.2.1.14 system. 6. Fire Protection Enhance the program to perform visual inspection of A.2.1.15 penetration seals by a fire protection qualified inspector. Enhance the program to add inspection requirements such 7. Fire Protection as spalling, and loss of material caused by freeze-thaw, A.2.1.15 chemical attack, and reaction with aggregates by qualified inspector. --------**---------SCHEDULE Complete Prior to the period of extended operation. Prior to the period of extended operation. Prior to the period of extended operation. Prior to the period of extended operation. Prior to the period of extended operation. Prior to the period of extended operation.
+U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 3 8. Fire Protection 9. Fire Water System 10. Fire Water System 11. Fire Water System Enhance the program to include the performance of visual inspection of fire-rated doors by a fire protection qualified inspector. Enhance the program to include NFPA 25 (2011 Edition) guidance for "where sprinklers have been in place for 50 years, they shall be replaced or representative samples 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 periodic flow testing of the fire water system in accordance 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 examinations are performed. These inspections will be 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 Prior to the period of extended A.2.1.15 operation. Prior to the period of extended A.2.1.16 operation. Prior to the period of extended A.2.1.16 operation. Within ten years prior to the A.2.1.16 period of extended operation.
+U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 4 12. Aboveground Steel Tanks 13. Fire Water System 14. Fuel Oil Chemistry 15. Fuel Oil Chemistry 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 managing the aging effects of loss of material and cracking, 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 internal bottom surface of the two Fire Protection Water 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 offloading to the Auxiliary Boiler fuel oil storage tank and 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 tank at least once per quarter and to remove water as necessary. A.2.1.17 Within 10 years prior to the period of extended operation. A.2.1.16 Within ten years prior to the period of extended operation. Prior to the period of extended A.2.1.18 operation. A.2.1.18 Prior to the period of extended operation.
+U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 5 16. Fuel Oil Chemistry 17. Fuel Oil Chemistry 18. Reactor Vessel Surveillance 19. Reactor Vessel Surveillance 20. Reactor Vessel Surveillance 21. Reactor Vessel Surveillance Enhance the program to require draining, cleaning and inspection of the diesel fire pump fuel oil day tanks on a 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 fuel oil storage tanks, Diesel Generator fuel oil day tanks, diesel fire pump fuel oil day tanks and auxiliary boiler fuel oil storage tank. Enhance the program to specify that all pulled and tested capsules, unless discarded before August 31, 2000, are 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 cold leg temperature or higher fluence, the impact of plant 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 meets the schedule requirements of 10 CFR 50 Appendix 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 maintains it in a condition which would permit its future use, including during the period of extended operation. Prior to the period of extended A.2.1.18 operation. A.2.1.18 Prior to the period of extended operation. Prior to the period of extended A.2.1.19 operation. Prior to the period of extended A.2.1.19 operation. Prior to the period of extended A.2.1.19 operation. A.2.1.19 Prior to the period of extended operation.
+U.S. Nuclear Regulatory Commission SBK-L-17 I 55 I Enclosure 3/ Page 6 22. One-Time Inspection 23. Selective Leaching of Materials 24. Buried Piping And Tanks Inspection One-Time Inspection of 25. ASME Code Class 1 Small Bore-Piping External Surfaces 26. Monitoring Inspection of Internal Surfaces in Miscellaneous 27. Piping and Ducting Components 28. Lubricating Oil Analysis 29. Lubricating Oil Analysis Implement the One Time Inspection Program. A.2.1.20 Within ten years prior to the period of extended operation. Implement the Selective Leaching of Materials Program. The program will include a one-time inspection of selected Within five years prior to the components where selective leaching has not been A.2.1.21 period of extended operation. identified and periodic inspections of selected components where selective leaching has been identified. Implement the Buried Piping And Tanks Inspection Within ten years prior to the Program. A.2.1.22 period of extended operation Implement the One-Time Inspection of ASME Code Class Within ten years prior to the A.2.1.23 1 Small Bore-Piping Program. period of extended operation. Enhance the program to specifically address the scope of the program, relevant degradation mechanisms and effects Prior to the period of extended of interest, the refueling outage inspection frequency, the A.2.1.24 operation. training requirements for inspectors and the required periodic reviews to determine program effectiveness. Implement the Inspection of Internal Surfaces in A.2.1.25 Prior to the period of extended Miscellaneous Piping and Ducting Components Program. operation. Enhance the program to add required equipment, lube oil Prior to the period of extended analysis required, sampling frequency, and periodic oil A.2.1.26 changes. operation. Enhance the program to sample the oil for the Reactor A.2.1.26 Prior to the period of extended Coolant pump oil collection tanks. operation.
+U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 7 30. Lubricating Oil Analysis ASME Section XI, 31. Subsection IWL Structures Monitoring 32. Program Structures Monitoring 33. Program Electrical Cables and Connections Not Subject to 34. 10 CFR 50.49 Environmental Qualification Requirements Electrical Cables and Connections Not Subject to 10 CFR 50.49 35. Environmental Qualification Requirements Used in Instrumentation Circuits Inaccessible Power Cables Not Subject to 10 CFR 50.49 36. Environmental Qualification Requirements 37. Metal Enclosed Bus Enhance the program to require the performance of a one-time ultrasonic thickness measurement of the lower portion A.2.1.26 Prior to the period of extended of the Reactor Coolant pump oil collection tanks prior to operation. the period of extended operation. Enhance procedure to include the definition of A.2.1.28 Prior to the period of extended "Responsible Engineer". operation. Enhance procedure to add the aging effects, additional Prior to the period of extended locations, inspection frequency and ultrasonic test A.2.1.31 operation. requirements. Enhance procedure to include inspection of opportunity Prior to the period of extended when planning excavation work that would expose A.2.1.31 operation. inaccessible concrete. Implement the Electrical Cables and Connections Not Prior to the period of extended Subject to 10 CFR 50.49 Environmental Qualification A.2.1.32 operation. Requirements program. Implement the Electrical Cables and Connections Not Prior to the period of extended Subject to 10 CFR 50.49 Environmental Qualification A.2.1.33 operation. Requirements Used in Instrumentation Circuits program. Implement the Inaccessible Power Cables Not Subject to Prior to the period of extended 10 CFR 50.49 Environmental Qualification Requirements A.2.1.34 operation. program. Implement the Metal Enclosed Bus program. A.2.1.35 Prior to the period of extended operation.
+U.S. Nuclear Regulatory Commission SBK-L-l 71SS I Enclosure 3/ Page 8 38. Fuse Holders Electrical Cable Connections Not Subject to 10 CFR S0.49 39. Environmental Qualification Requirements 40. 34S KV SF6 Bus Metal Fatigue of Reactor 41. Coolant Pressure Boundary Metal Fatigue of Reactor 42. Coolant Pressure Boundary Pressure -Temperature Limits, including Low 43. Temperature Overpressure Protection Limits Implement the Fuse Holders program. A.2.1.36 Prior to the period of extended operation. Implement the Electrical Cable Connections Not Subject to Prior to the period of extended 10 CFR S0.49 Environmental Qualification Requirements A.2.1.37 operation. program. Implement the 34S KV SF6 Bus program. A.2.2.1 Prior to the period of extended operation. Enhance the program to include additional transients Prior to the period of extended beyond those defined in the Technical Specifications and A.2.3. l operation. UFSAR. Enhance the program to implement a software program, to Prior to the period of extended count transients to monitor cumulative usage on selected A.2.3.1 operation. components. The updated analyses will be Seabrook Station will submit updates to the P-T curves and submitted at the appropriate time L TOP limits to the NRC at the appropriate time to comply A.2.4.1.4 to comply with l 0 CFR SO with 10 CFR SO Appendix G. Appendix G, Fracture Toughness Requirements.
+U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 9 44. Environmentally-Assisted Fatigue Analyses (TLAA) 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 At least two years prior to the Fen factors to valid CUFs determined from an existing A.2.4.2.3 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 Alkali-Silica Reaction 45. (ASR) Monitoring Program 46. Protective Coating Monitoring and Maintenance 47. Protective Coating Monitoring and Maintenance 48. Protective Coating Monitoring and Maintenance 49. Protective Coating Monitoring and Maintenance ASME Section XI, 50. Subsection IWE 51. Number Not Used 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 the change in through-thickness expansion since period of extended operation installation of the extensometers and compare it to change (initial study) and 10 years determined from extensometer readings. Consistency thereafter (follow-up study). between these results will provide additional corroboration of the methodology in MPR-4153. Enhance the program by designating and qualifying an A.2.1.38 Prior to the period of extended Inspector Coordinator and an Inspection Results Evaluator. operation. Enhance the program by including, "Instruments and Equipment needed for inspection may include, but not be limited to, flashlight, spotlights, marker pen, mirror, A.2.1.38 Prior to the period of extended measuring tape, magnifier, binoculars, camera with or operation. without wide angle lens, and self sealing polyethylene sample bags." Enhance the program to include a review of the previous A.2.1.38 Prior to the period of extended two monitoring reports. operation. Enhance the program to require that the inspection report is to be evaluated by the responsible evaluation personnel, A.2.1.38 Prior to the period of extended who is to prepare a summary of findings and operation. recommendations for future surveillance or repair. Baseline inspections were Perform UT of the accessible areas of the containment completed during OR16. Repeat liner plate in the vicinity of the moisture barrier for loss of A.2.1.27 containment liner UT thickness examinations at intervals of no material. Perform opportunistic UT of inaccessible areas. more than five (5) refueling outages.
+U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 11 ASME Section XI, 52. Subsection IWL 53. Reactor Head Closure Studs Implement measures to maintain the exterior surface of the Contairunent Structure, from elevation -30 feet to +20 feet, A.2.1.28 Complete in a dewatered state. Replace the spare reactor head closure stud(s) Prior to the period of extended manufactured from the bar that has a yield strength> 150 A.2.1.3 ksi with ones that do not exceed 150 ksi. operation.
+U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 12 Steam Generator Tube 54. Integrity 55. Number Not Used Closed-Cycle Cooling Water 56. System 57. Closed-Cycle Cooling Water System 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 weld inspections for the remaining life of the steam A.2.1.10 Complete 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. Revise the station program documents to reflect the EPRI Prior to the period of extended Guideline operating ranges and Action Level values for A.2.1.12 hydrazine and sulfates. operation. Revise the station program documents to reflect the EPRI Prior to the period of extended Guideline operating ranges and Action Level values for A.2.1.12 operation. Diesel Generator Cooling Water Jacket pH.
+U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 13 58. Fuel Oil Chemistry Nickel Alloy Nozzles and 59. Penetrations Buried Piping and Tanks 60. Inspection Compressed Air Monitoring 61. Program 62. Water Chemistry 63. Flow Induced Erosion 64. Buried Piping and Tanks Inspection Update Technical Requirement Program 5 .1, (Diesel Fuel Oil Testing Program) ASTM standards to ASTM D2709-A.2.1.18 Prior to the period of extended 96 and ASTM D4057-95 required by the GALL XI.M30 operation. Rev 1 The Nickel Alloy Aging Nozzles and Penetrations program Prior to the period of extended will implement applicable Bulletins, Generic Letters, and A.2.2.3 operation. staff accepted industry guidelines. Implement the design change replacing the buried Prior to the period of extended Auxiliary Boiler supply piping with a pipe-within-pipe A.2.1.22 operation. configuration with leak detection capability. Replace the flexible hoses associated with the Diesel Within ten years prior to the Generator air compressors on a frequency of every 10 A.2.1.14 period of extended operation. years. Enhance the program to include a statement that sampling Prior to the period of extended frequencies are increased when chemistry action levels are A.2.1.2 exceeded. operation. 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 A.2.1.2 Prior to the period of extended 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 A.2.1.22 Within ten years prior to the steel pipe within the scope of this program. If the initial period of extended operation. 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 65. Flux Thimble Tube Alkali-Silica Reaction 66. (ASR) Monitoring Program 67. Structures Monitoring Program Implement measures to ensure that the movable incore Prior to the period of extended detectors are not returned to service during the period of extended operation. NIA operation. -In Progress 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 thickness expansion of all monitored points by A.2.1.31.A of extended operation and every 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 degradation such as loss of material. The removed core A.2.1.31 Complete 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 68. Program Open-Cycle Cooling Water 69. System 70. Closed-Cycle Cooling Water System Alkali-Silica Reaction (ASR) Monitoring Program I 71. Building Deformation Monitoring Program 72. Flow-Accelerated Corrosion Inspection of Internal Surfaces in Miscellaneous 73. Piping and Ducting Components Perform sampling at the leak off collection points for A.2.1.31 Complete chlorides, sulfates, pH and iron once every three months. Replace the Diesel Generator Heat Exchanger Plastisol PVC lined Service Water piping with piping fabricated A.2.1.11 Complete from AL6XN material. Inspect the piping downstream of CC-V-444 and CC-V-446 to determine whether the loss of material due to Within ten years prior to the cavitation induced erosion has been eliminated or whether A.2.1.12 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 acceptance criteria used are appropriate to manage the effects of ASR. A.2.1.3 lA Prior to the period of extended NextEra !implement the Alkali-Silica Reaction (ASR) A.2.l.31B operation. 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 A.2.1.8 Prior to the period of extended thinning caused by mechanisms other than FAC. operation. Enhance the program to include performance of focused examinations to provide a representative sample of20%, or a maximum of25, of each identified material, A.2.1.25 Prior to the period of extended environment, and aging effect combinations during each operation. 10 year period in the period of extended operation.
+U.S. Nuclear Regulatory Commission SBK-L-17155 /Enclosure 3/Page 16 74. Fire Water System 75. Fire Water System 76. Fire Water System 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 and installed in the proper orientation (e.g., upright, 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 pipe or sprinklers is detected during pipe inspections, the 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).
+* main drain tests
+* deluge valve trip tests
+* fire water storage tank exterior surface inspections Prior to the period of extended A.2.1.16 operation. Prior to the period of extended A.2.1.16 operation. A.2.1.16 Prior to the period of extended operation.
+U.S. Nuclear Regulatory Commission SBK-L-17 I 55 I Enclosure 3/ Page 17 77. Fire Water System 78. External Surfaces Monitoring Open-Cycle Cooling Water 79. System 80. Fire Water System 81. Fuel Oil Chemistry 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 A.2.1.16 Prior to the period of extended 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 are insulated and a sample of indoor insulated components A.2.1.24 Prior to the period of extended 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 Within 10 years prior to the internal coatings/linings for loss of coating integrity. A.2.1.11 period of extended operation. Enhance the program to include visual inspection of Within 10 years prior to the internal coatings/linings for loss of coating integrity. A.2.1.16 period of extended operation. Enhance the program to include visual inspection of Within 10 years prior to the internal coatings/linings for loss of coating integrity. A.2.1.18 period of extended operation.
+U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 18 Inspection of Internal 82. Surfaces in Miscellaneous Piping and Ducting Components 83. Alkali-Silica Reaction Monitoring ASME Section XI, 84. Subsection IWL 85. Fire Water System 86. Fire Water System 87. Fire Water System Enhance the program to include visual inspection of internal coatings/linings for loss of coating integrity. A.2.1.25 Within 10 years prior to the period of extended operation. 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-of-plane direction. A.2.1.31A Complete 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 Prior to the period of extended structures within the scope of ASME Section XI, A.2.1.28 operation. Subsection IWL Program. Enhance the program to perform additional tests and inspections on the Fire Water Storage Tanks as specified in Section 9.2.7 ofNFPA 25 (2011 Edition) in the event that A.2.1.16 Prior to the period of extended 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." Enhance the program to include disassembly, inspection, A.2.1.16 Prior to the period of extended and cleaning of the mainline strainers every 5 years. operation. Increase the frequency of the Open Head Spray Nozzle Air Flow Test from every 3 years to every refueling outage to
+* A.2.1.16 Prior to the period of extended 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 88. Fire Water System Inspection of Internal Surfaces in Miscellaneous 89. Piping and Ducting Components PWR Vessel Internals 90. 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 Within five years prior to the piping are configured to completely drain the piping, and A.2.1.16 c) normally-dry piping that could have been wetted by period of extended operation. 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 RCP Motor Refurbishment Specification for the internal painting of the motor upper bearing coolers and motor air A.2.1.25 Prior to the period of extended coolers. All four RCP motors will be refurbished and operation. 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 227-A (Pressurized Water Reactor Internals Inspection and A.2.1.7 Evaluation Guidelines) and NEI 03-08 (Guideline for the operation Management of Materials Issues).
+U.S. Nuclear Regulatory Commission SBK-L-17155 I Enclosure 3/ Page 20 Building Deformation 91 Monitoring 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 additional parameters to be monitored based on the results A.2.l.31B March 15, 2020 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. to SBK-L-17155 NextEra Energy Seabrook, Application for Withholding Proprietary Information from Public Disclosure and Affidavit U.S. Nuclear Regulatory Commission SBK-L-17155 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. Nuclear Regulatory Commission 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. Subscribed and sworn to before me this 12 O day of October, 2017. Notary Public My commission expires 3/rt;/1,.,7__ Regional Vice President -Northern Region NextEra Energy Seabrook, LLC 626 Lafayette Road Seabrook, New Hampshire 03874
 }}

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
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