ML13190A015

Oconee Nuclear Station, Units 1, 2, and 3, Aging Management Reviews for Newly Identified Systems, Structures and Components as of December 31, 2012

ML13190A015
Person / Time
Site:	Oconee
Issue date:	07/01/2013
From:	Batson S L Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13190A015 (15)

Text

DUKE Scoff L.BatsonENERGY, Oconee Nuclear StationDuke EnergyONO1VP I 7800 Rochester HwySeneca, SC 2967210 CFR 54.37(b) o: 864.873.3274

f. 864.873.

4208Scoft.Batson@duke-energy.com July 1, 2013U. S. Nuclear Regulatory Commission Attn: Document Control DeskWashington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC (Duke Energy)Oconee Nuclear Station, Units 1, 2, and 3Docket Nos. 50-269, 50-270, 50-287Aging Management Reviews for Newly Identified

Systems, Structures andComponents as of December 31, 2012Pursuant to 10 CFR 54.37(b),

attached are aging management reviews (AMR) for thoseOconee Nuclear Station systems, structures and components (SSC) that have been newlyidentified as of December 31, 2012. These AMRs support changes to the aging management program summaries provided in the 2012 revision of the Updated Final Safety Analysis Report(UFSAR) for Oconee Nuclear Station that will be submitted under separate cover on or beforeJuly 1, 2013.The following are the SSCs that have AMRs attached to this letter:1) Standby Shutdown Facility

-Auxiliary Service Water2) Fan and Damper Housings3) Keowee Turbine Guide Bearing Oil CoolersThis submittal document contains no regulatory commitments.

If there are any questions, please contact Susan Perry at (864) 873-4370.

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

Executed on the 1st dayof July, 2013.Sincerely, Scott L. BatsonAttachment www.duke-energy.com U. S. Nuclear Regulatory Commission July 1, 2013Page 2xc:Mr. Victor McCreeAdministrator, Region IIU.S. Nuclear Regulatory Commission Marquis One Tower245 Peachtree Center Ave., NE, Suite 1200Atlanta, GA 30303-1257 Mr. John BoskaProject ManagerU.S. Nuclear Regulatory Commission 11555 Rockville PikeMail Stop O-8G9ARockville, MD 20852-2746 Mr. Ed CroweSenior Resident Inspector Oconee Nuclear Station U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 1Aging Management ReviewsForNewly Identified Oconee Nuclear StationSystems, Structures and Components as of December 31, 2012 U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 2Introduction This summary report is in lieu of adding a level of detail to the Oconee Nuclear Station (ONS)Updated Final Safety Analysis Report (UFSAR) that is greater than the remainder of the UFSAR,including the License Renewal Supplement.

An entry on the NRC website, "Frequently AskedQuestions (FAQs) About License Renewal Inspection Procedure (IP) 71003, 'Post-Approval SiteInspection for License Renewal,"'

relates to the amount of detail required per 10CFR 54.37(b).

Itstates, "The NRC staff will consider it acceptable if the summary information included in theFSAR update is consistent with the requirements of 10 CFR 54.21(d),

and the guidance providedby Revision 1 of NUREG-1 800, 'Standard Review Plan for License Renewal Applications forNuclear Power Plants' (SRP-LR),

provided that the licensee has supplied the technical details (asdescribed in RIS 2007-16) in another documented submittal to the NRC." The information in thisreport is consistent with the technical information previously submitted to the NRC with theLicense Renewal Application (LRA) and subsequent requests for additional information (RAIs).In July 1998, ONS submitted a LRA to the NRC to renew the operating licenses for ONSUnits 1, 2, and 3 for an additional 20 years beyond the original license expiration dates ofFebruary 6, 2013, October 6, 2013, and July 19, 2014, respectively.

Within the LRA, systemdescriptions were provided to define the component types, intended functions, and the AgingManagement Programs (AMPs) that applied.

Lists of individual components within the scope oflicense renewal were not required to be provided.

The renewed operating licenses were issuedin May 2000 to extend the operating licenses for ONS Units 1, 2, and 3 for an additional 20 years.For holders of a renewed operating

license, 10 CFR 54.37(b) requires that newly-identified

systems, structures, or components (SSCs) be included in the UFSAR update required by10 CFR 50.71(e) describing how the effects of aging will be managed.

Newly-identified SSCs arethose SSCs that were installed in the plant at the time of the LRA submittal but were notevaluated as part of the LRA.A review of engineering

changes, newly generated License Renewal Boundary

Drawings, anditems identified using the Problem Investigation Program (PIP) were reviewed fromJanuary 1, 2012 through December 31, 2012. From this review, three Aging Management Reviews (AMRs) were performed for "newly identified" items. All newly identified components have been assigned to existing AMPs and appropriate actions to detect and manage agingeffects throughout the period of extended operation (PEO) have been taken.The components for which AMR results are already addressed within the LRA or are addressed by responses to NRC RAIs are not discussed here, since the results of the AMR have beenpreviously submitted and found acceptable.

Summaries of the completed AMRs included in this report are:1 -Standby Shutdown Facility

-Auxiliary Service Water (SSF-ASW)

System Changes2 -Fan and Damper Housings3 -Keowee Turbine Guide Bearing Oil Coolers U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 31.0 Standby Shutdown Facility

-Auxiliary Service Water (SSF-ASW)

System ChangesDuring the LRA, the SSF-ASW piping was classified as having external environments ofsheltered and yard pipe. Yard pipe was considered piping above ground piping. In addition, it was initially thought that the SSF-ASW had an internal environment of just service water.ONS had a leak in a section of underground SSF-ASW piping. During the Failure Investigation Process (FIP), it was identified that the LRA did not appropriately represent the SSF-ASWpiping. A portion of the SSF-ASW piping is buried piping (external environment

-Underground).

It was also identified that certain sections of SSF-ASW piping are filled with demineralized (treated) water. An EC was performed to replace a portion of the underground portion of piping.The existing material was carbon steel, and the new material used was stainless steel.Impact on ONS UFSAR Chapter 18No changes are required in Chapter 18 of the UFSAR for the Condenser Circulating WaterInternal Coating Inspection Program or the Service Water Piping Corrosion Program.Tables 1.1 and 1.2 contain the AMR review summary for internal and externalenvironments.

U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 4Table 1.1Aging Management Review Summary TableSSF-ASW System Internal Environments Component Intended Material Environment Aging Effect Requiring Aging Management Type Function Management Program/Activity Loss of Material Service Water PipingGalvanic Corrosion Corrosion ProgramPressure Carbon Steel Treated Water GeraCoosn Pie Pressure General Corrosion Pipe Boundary Pitting Corrosion Stainless Steel Treated Water Loss of Material Service Water PipingPitting Corrosion Corrosion ProgramTable 1.2Aging Management Review Summary TableSSF-ASW System External Environments Component Intended Material Environment Aging Effect Requiring Aging Management Type Function Management Program/Activity Loss of Material Condenser Circulating WaterGalvanic Corrosion Internal Coating Inspection Carbon Steel Underground General Corrosion ProgramPressure Pitting Corrosion Pipe Boundary MICLoss of Material Condenser Circulating WaterStainless Steel Underground Pitting Corrosion Internal Coating Inspection MIC Program U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 52.0 Fan and Damper HousingsIn accordance with RIS 2007-16, the NRC expects applicants to identify active mechanical component housings that require an AMR pursuant to 10 CFR 54.21. This determination considers whether failure of the housing would result in a failure of the associated activemechanical component to perform its intended

function, and whether the housing meets thelong-lived and passive criteria as defined in the Rule.Specifically, housings for fans and dampers that perform a pressure retention and/or structural integrity

function, which if not maintained, could prevent the associated active mechanical component from performing its intended function.

Housings that perform these functions andmeet the long-lived and passive criteria are subject to an AMR.ONS considered the non-active part of a component that performs a function within the scope ofPart 54 (e.g., Fan and Damper Housings).

These reviews considered not just the activemechanical component, but also the intended function of its associated housing.

The following Air Conditioning,

Heating, Cooling and Ventilation Systems within the scope of License Renewalwere evaluated as part of this process:" Standby Shutdown Facility HVAC* Reactor Building Cooling System" Auxiliary Building Ventilation System* Control Room Pressurization and Filtration System* Penetration Room Ventilation System" Reactor Building Purge SystemAlthough the Fan and Damper Housings were evaluated as an integral part of the "Ductwork" commodity in the original LRA since they also perform a pressure boundary component intended

function, these components were not explicitly identified as a commodity group suchas "Fan and Damper Housings" in the submittal.

Impact on ONS UFSAR Chapter 18New UFSAR sections have been generated and incorporated into Chapter 18, Section 3.17,Preventative Maintenance Activities.

Tables 2.1 and 2.2 contain the AMR review summary for internal and externalenvironments.

U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 6Table 2.1Aging Management Review Summary TableFan and Damper Housings Internal Environments Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring TypeFunction Management Program/Activity Aluminum Air None NoneFan Pressure Galvanized Air Loss of Material

-Preventative Maintenance Activities Steel General Corrosion Reactor Housings Boundary Stainless RatrSanesAir None NoneBuilding SteelPurge System Aluminum Air None NoneGalvanized Air Loss of Material

-Preventative Maintenance Activities Damper Pressure SteelAi GeeaCorso PrvnaieMntaceciiis Housings Boundary tlGeneral Corrosion Stainless Air None NoneSteelPenetration Aluminum Air None NonePntainGalvanized Loss of Material

-.Room Fan Pressure Stee Air L orrion Preventative Maintenance Activities Ventilation Housings Boundary Stainless ANneSystem Steel Air None NoneReactor Aluminum Air None NoneBuilding Fan Pressure Sted Air Loss of Material

-Preventative Maintenance Activities Cooling Housings Boundary StlGeneral Corrosion System Stainless Air None None___________

________

Steel __________________________________

Aluminum Air None NoneBuilding Fan Pressure Galvanized Air Loss of Material

-Preventative Maintenance Activities Ventilation Housings Boundary Stainless ANneSystem Steel Air None None U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 7Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring Program/Activity Management Aluminum Air None NoneBuilding Damper Pressure Galvanized Air Loss of Material

-Preventative Maintenance Activities Ventilation Housings Boundary Stainless ANneSystem Steel Air None NoneAluminum Air None NoneGalvanized Loss of Material

-Fan Pressure Steel Air General Corrosion Preventative Maintenance Activities Control Room Housings Boundary Stainless Air NonePressurization Steeland Filtration Aluminum Air None NoneSystem Galvanized Loss of Material

-Damper Pressure Steel Air General Corrosion Preventative Maintenance Activities Housings Boundary Stainless Air NoneSteelAluminum Air None NoneGalvanized Ar Loss of Material

-Fan Pressure Air Preventative Maintenance Activities Housings Boundary Steel General Corrosion Standby Stainless Air None NoneS h u td o w n A l m n mA rNnoSte e lFacility HVAC Aluminum Air None NoneDamper Pressure Galvanized Air Loss of Material

-Preventative Maintenance Activities Housings Boundary Steel General Corrosion Stainless Air None NoneSteel U. S, Nuclear Regulatory Commission July 1, 2013Attachment Page 8Table 2.2Aging Management Review Summary TableFan and Damper Housings External Environments Component ended Aging Effect Aging Management System Type Function Material Environment Requiring Type Function Management Program/Activity ReactorBuildinaLoss of Material

-Boric Acid WastaaeBoric Acid Corrosion ProgramAluminumI. -__________________________________

Sheltered Loss of Material

-Boric Acid WastageBoric Acid Corrosion ProgramFanHousingsPressureBoundaryLoss of Material

-Reato Borc Ad Wasteiage

-Boric Acid Corrosion ProgramBoric Acid WastageSheltered Loss of Material

-Inspection Program for CivilGeneral Corrosion Engineering Structures andGalvanizedComponents Steel Loss of Material

-Bori Aci Wasage Boric Acid Corrosion ProgramSheltered Loso aeil- Inspection Program for CivilLossra Cofratroian Engineering Structures andGeneal orroion Components ReactorBuildingPurge SystemStainless SteelReactorBuildinaNoneNone-, 4Sheltered NoneNoneAluminumSheltered Loss of Material

-Boric Acid WastageBoric Acid Corrosion ProgramDamperHousingsPressureBoundaryLoss of Material

-wBoric Ad Wasteiae

-Boric Acid Corrosion ProgramBoric Acid WastageGalvanized Sheltered Inspection Program for CivilSteel Loss of Material

-General Corrosion Engineering Structures andG Components Stainless SteelSheltered NoneNonei h I I i U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 9Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring Program/Activity

_________

________

_______________

__________

Management PormAtvtAluminum Sheltered None NonePenetration Inspection Program for CivilRoom Fan Pressure Steel ofeMterian Engineering Structures andVentilation Housings Boundary SteComponents SystemStils Stail Sheltered None NoneAluminum Reactor Loss of Material

-Aluminum__

Building Boric Acid Wastage Boric Acid Corrosion ProgramReactorLoss of Material

-Reactor Borc Ad Wasteiage

-Boric Acid Corrosion ProgramBuilding Fan Pressure Galvanized Boric Acid WastageCooling Housings Boundary Steel Sheltered Loss of Material

-Inspection Program for CivilSystem General Corrosion Engineering Structures andComponents Stainless Sheltered None NoneSteelLoss of Material

-Aluminum Sheltered Boric Acid Wastage Boric Acid Corrosion ProgramAuxiliary Loss of Material

-Boric Acid Corrosion ProgramBuilding Fan Pressure Galvanized Sheltered Loss of Mate Inspection Program for CivilVentilation Housings Boundary Steel Loss of Materiala-Systm GeeralCorrsion Engineering Structures andSystem General Corrosion Components Stainless Sheltered None NoneSteel I U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 10Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring TypeFunction Management Program/Activity Aluminum Sheltered Loss of Material

-Aluminum Shetere Boric Acid Wastage Boric Acid Corrosion ProgramAuxiliary Loss of Material

-Boric Acid Corrosion ProgramBuilding Damper Pressure Galvanized Sheltered Boric of Mate Inspection Program for CivilVentilation Housings Boundary Steel Loss of Material

-ineerin Progra ndSystem General Corrosion Engineering Structures and___________Components Stainless Sheltered None NoneSteelAluminum Sheltered None NoneGalvanized Loss of Material

-Inspection Program for CivilFan Pressure Steel Sheltered General Corrosion Engineering Structures andHousings Boundary Components Control Room Stainless Sheltered None NonePressurization Steeland Filtration Aluminum Sheltered None NoneSystem Galvanized Loss of Material

-Inspection Program for CivilDamper Pressure Steel Sheltered General Corrosion Engineering Structures andHousings Boundary Components Stainless Sheltered None NoneSteelAluminum Sheltered None NoneStandby Galvanized Loss of Material

-Inspection Program for CivilShutdown Fan Pressure Steel Sheltered General Corrosion Engineering Structures andFacility HVAC Housings Boundary Components Stainless Sheltered None NoneSteel U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 11Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring Type_____Function_______

Management Program/Activity Aluminum Sheltered None NoneStandby Galvanized Loss of Material

-Inspection Program for CivilShutdown Damper Pressure Steel vanid General Corrosion Engineering Structures and..... .Housinas Boundarv ComDonents U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 123.0 Keowee Turbine Guide Bearing Oil CoolersThe Turbine Guide Bearing Oil System includes the Turbine Guide Bearing Oil Coolers that arewithin the scope of License Renewal.

The Turbine Guide Bearing Oil Coolers provide thenecessary flow of lubricating oil to the Keowee turbine guide bearings.

Although the Turbine Guide Bearing Oil Coolers were originally included within the scope ofLicense Renewal in the original LRA, the heat transfer intended function for these heatexchangers was not identified at that time, only the pressure boundary intended function.

Heattransfer has since been identified as a License Renewal intended function for these components as part of the Problem Investigation Program (PIP).Impact on ONS UFSAR Chapter 18A new UFSAR section has been generated and incorporated into Chapter 18, Section 3.17,Preventative Maintenance Activities.

Tables 3.1 and 3.2 contain the AMR review summary for internal and externalenvironments.

U. S. Nuclear Regulatory Commission July 1, 2013Attachment Page 13Table 3.1Aging Management Review Summary TableKeowee Turbine Guide Bearing Oil Coolers Internal Environments Component Intended Material Environment Aging Effect Requiring Aging Management Type Function Management Program/Activity Heat 3.1.1 Heat TransferTubes Transfer Stainless Steel Raw Water Degradation

-3.1.2 Preventative

_Fouling Maintenance Activities Table 3.2Aging Management Review Summary TableKeowee Turbine Guide Bearing Oil Coolers External Environments Component Intended Material Environment Aging Effect Requiring Aging Management Type Function Management Program/Activity Heat HKeowee Oil Sampling ProgramTueHTasera tilesSeeti Heat TransferTubes Transfer Stainless Steel Oil Degradation

-Fouling Preventative Maintenance I I_ I I I Activities