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.Batson ENERGY, Oconee Nuclear Station Duke Energy ONO1VP I 7800 Rochester Hwy Seneca, SC 29672 10 CFR 54.37(b) o: 864.873.3274

f. 864.873. 4208 Scoft.Batson@duke-energy.com July 1, 2013 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC (Duke Energy)Oconee Nuclear Station, Units 1, 2, and 3 Docket Nos. 50-269, 50-270, 50-287 Aging Management Reviews for Newly Identified Systems, Structures and Components as of December 31, 2012 Pursuant to 10 CFR 54.37(b), attached are aging management reviews (AMR) for those Oconee Nuclear Station systems, structures and components (SSC) that have been newly identified 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 before July 1, 2013.The following are the SSCs that have AMRs attached to this letter: 1) Standby Shutdown Facility -Auxiliary Service Water 2) Fan and Damper Housings 3) Keowee Turbine Guide Bearing Oil Coolers This 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 day of July, 2013.Sincerely, Scott L. Batson Attachment www.duke-energy.com U. S. Nuclear Regulatory Commission July 1, 2013 Page 2 xc: Mr. Victor McCree Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. John Boska Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8G9A Rockville, MD 20852-2746 Mr. Ed Crowe Senior Resident Inspector Oconee Nuclear Station U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 1 Aging Management Reviews For Newly Identified Oconee Nuclear Station Systems, Structures and Components as of December 31, 2012 U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 2 Introduction 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 Asked Questions (FAQs) About License Renewal Inspection Procedure (IP) 71003, 'Post-Approval Site Inspection for License Renewal,"'

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

It states, "The NRC staff will consider it acceptable if the summary information included in the FSAR update is consistent with the requirements of 10 CFR 54.21(d), and the guidance provided by Revision 1 of NUREG-1 800, 'Standard Review Plan for License Renewal Applications for Nuclear Power Plants' (SRP-LR), provided that the licensee has supplied the technical details (as described in RIS 2007-16) in another documented submittal to the NRC." The information in this report is consistent with the technical information previously submitted to the NRC with the License 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 ONS Units 1, 2, and 3 for an additional 20 years beyond the original license expiration dates of February 6, 2013, October 6, 2013, and July 19, 2014, respectively.

Within the LRA, system descriptions were provided to define the component types, intended functions, and the Aging Management Programs (AMPs) that applied. Lists of individual components within the scope of license renewal were not required to be provided.

The renewed operating licenses were issued in 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 by 10 CFR 50.71(e) describing how the effects of aging will be managed. Newly-identified SSCs are those SSCs that were installed in the plant at the time of the LRA submittal but were not evaluated as part of the LRA.A review of engineering changes, newly generated License Renewal Boundary Drawings, and items identified using the Problem Investigation Program (PIP) were reviewed from January 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 aging effects 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 been previously submitted and found acceptable.

Summaries of the completed AMRs included in this report are: 1 -Standby Shutdown Facility -Auxiliary Service Water (SSF-ASW)

System Changes 2 -Fan and Damper Housings 3 -Keowee Turbine Guide Bearing Oil Coolers U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 3 1.0 Standby Shutdown Facility -Auxiliary Service Water (SSF-ASW)

System Changes During the LRA, the SSF-ASW piping was classified as having external environments of sheltered 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-ASW piping. 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 18 No changes are required in Chapter 18 of the UFSAR for the Condenser Circulating Water Internal Coating Inspection Program or the Service Water Piping Corrosion Program.Tables 1.1 and 1.2 contain the AMR review summary for internal and external environments.

U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 4 Table 1.1 Aging Management Review Summary Table SSF-ASW System Internal Environments Component Intended Material Environment Aging Effect Requiring Aging Management Type Function Management Program/Activity Loss of Material Service Water Piping Galvanic Corrosion Corrosion Program Pressure Carbon Steel Treated Water GeraCoosn Pie Pressure General Corrosion Pipe Boundary Pitting Corrosion Stainless Steel Treated Water Loss of Material Service Water Piping Pitting Corrosion Corrosion Program Table 1.2 Aging Management Review Summary Table SSF-ASW System External Environments Component Intended Material Environment Aging Effect Requiring Aging Management Type Function Management Program/Activity Loss of Material Condenser Circulating Water Galvanic Corrosion Internal Coating Inspection Carbon Steel Underground General Corrosion Program Pressure Pitting Corrosion Pipe Boundary MIC Loss of Material Condenser Circulating Water Stainless Steel Underground Pitting Corrosion Internal Coating Inspection MIC Program U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 5 2.0 Fan and Damper Housings In 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 active mechanical component to perform its intended function, and whether the housing meets the long-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 and meet 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 of Part 54 (e.g., Fan and Damper Housings).

These reviews considered not just the active mechanical component, but also the intended function of its associated housing. The following Air Conditioning, Heating, Cooling and Ventilation Systems within the scope of License Renewal were 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 System Although 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 such as "Fan and Damper Housings" in the submittal.

Impact on ONS UFSAR Chapter 18 New 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 external environments.

U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 6 Table 2.1 Aging Management Review Summary Table Fan and Damper Housings Internal Environments Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring TypeFunction Management Program/Activity Aluminum Air None None Fan Pressure Galvanized Air Loss of Material -Preventative Maintenance Activities Steel General Corrosion Reactor Housings Boundary Stainless RatrSanesAir None None Building Steel Purge System Aluminum Air None None Galvanized Air Loss of Material -Preventative Maintenance Activities Damper Pressure SteelAi GeeaCorso PrvnaieMntaceciiis Housings Boundary tlGeneral Corrosion Stainless Air None None Steel Penetration Aluminum Air None None PntainGalvanized Loss of Material -.Room Fan Pressure Stee Air L orrion Preventative Maintenance Activities Ventilation Housings Boundary Stainless ANne System Steel Air None None Reactor Aluminum Air None None Building Fan Pressure Sted Air Loss of Material -Preventative Maintenance Activities Cooling Housings Boundary StlGeneral Corrosion System Stainless Air None None___________

________ Steel __________________________________

Aluminum Air None None Building Fan Pressure Galvanized Air Loss of Material -Preventative Maintenance Activities Ventilation Housings Boundary Stainless ANne System Steel Air None None U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 7 Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring Program/Activity Management Aluminum Air None None Building Damper Pressure Galvanized Air Loss of Material -Preventative Maintenance Activities Ventilation Housings Boundary Stainless ANne System Steel Air None None Aluminum Air None None Galvanized Loss of Material -Fan Pressure Steel Air General Corrosion Preventative Maintenance Activities Control Room Housings Boundary Stainless Air None Pressurization Steel and Filtration Aluminum Air None None System Galvanized Loss of Material -Damper Pressure Steel Air General Corrosion Preventative Maintenance Activities Housings Boundary Stainless Air None Steel Aluminum Air None None Galvanized Ar Loss of Material -Fan Pressure Air Preventative Maintenance Activities Housings Boundary Steel General Corrosion Standby Stainless Air None None S h u td o w n A l m n mA rNnoSte e l Facility HVAC Aluminum Air None None Damper Pressure Galvanized Air Loss of Material -Preventative Maintenance Activities Housings Boundary Steel General Corrosion Stainless Air None None Steel U. S, Nuclear Regulatory Commission July 1, 2013 Attachment Page 8 Table 2.2 Aging Management Review Summary Table Fan and Damper Housings External Environments Component ended Aging Effect Aging Management System Type Function Material Environment Requiring Type Function Management Program/Activity Reactor Buildina Loss of Material -Boric Acid Wastaae Boric Acid Corrosion Program Aluminum I. -__________________________________

Sheltered Loss of Material -Boric Acid Wastage Boric Acid Corrosion Program Fan Housings Pressure Boundary Loss of Material -Reato Borc Ad Wasteiage

-Boric Acid Corrosion Program Boric Acid Wastage Sheltered Loss of Material -Inspection Program for Civil General Corrosion Engineering Structures and GalvanizedComponents Steel Loss of Material -Bori Aci Wasage Boric Acid Corrosion Program Sheltered Loso aeil- Inspection Program for Civil Lossra Cofratroian Engineering Structures and Geneal orroion Components Reactor Building Purge System Stainless Steel Reactor Buildina None None-, 4 Sheltered None None Aluminum Sheltered Loss of Material -Boric Acid Wastage Boric Acid Corrosion Program Damper Housings Pressure Boundary Loss of Material -w Boric Ad Wasteiae -Boric Acid Corrosion Program Boric Acid Wastage Galvanized Sheltered Inspection Program for Civil Steel Loss of Material -General Corrosion Engineering Structures and G Components Stainless Steel Sheltered None None i h I I i U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 9 Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring Program/Activity

_________

________ _______________

__________

Management PormAtvt Aluminum Sheltered None None Penetration Inspection Program for Civil Room Fan Pressure Steel ofeMterian Engineering Structures and Ventilation Housings Boundary SteComponents SystemStils Stail Sheltered None None Aluminum Reactor Loss of Material -Aluminum__

Building Boric Acid Wastage Boric Acid Corrosion Program ReactorLoss of Material -Reactor Borc Ad Wasteiage

-Boric Acid Corrosion Program Building Fan Pressure Galvanized Boric Acid Wastage Cooling Housings Boundary Steel Sheltered Loss of Material -Inspection Program for Civil System General Corrosion Engineering Structures and Components Stainless Sheltered None None Steel Loss of Material -Aluminum Sheltered Boric Acid Wastage Boric Acid Corrosion Program Auxiliary Loss of Material -Boric Acid Corrosion Program Building Fan Pressure Galvanized Sheltered Loss of Mate Inspection Program for Civil Ventilation Housings Boundary Steel Loss of Materiala-Systm GeeralCorrsion Engineering Structures and System General Corrosion Components Stainless Sheltered None None Steel I U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 10 Component 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 Program Auxiliary Loss of Material -Boric Acid Corrosion Program Building Damper Pressure Galvanized Sheltered Boric of Mate Inspection Program for Civil Ventilation Housings Boundary Steel Loss of Material -ineerin Progra nd System General Corrosion Engineering Structures and___________Components Stainless Sheltered None None Steel Aluminum Sheltered None None Galvanized Loss of Material -Inspection Program for Civil Fan Pressure Steel Sheltered General Corrosion Engineering Structures and Housings Boundary Components Control Room Stainless Sheltered None None Pressurization Steel and Filtration Aluminum Sheltered None None System Galvanized Loss of Material -Inspection Program for Civil Damper Pressure Steel Sheltered General Corrosion Engineering Structures and Housings Boundary Components Stainless Sheltered None None Steel Aluminum Sheltered None None Standby Galvanized Loss of Material -Inspection Program for Civil Shutdown Fan Pressure Steel Sheltered General Corrosion Engineering Structures and Facility HVAC Housings Boundary Components Stainless Sheltered None None Steel U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 11 Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring Type_____Function_______

Management Program/Activity Aluminum Sheltered None None Standby Galvanized Loss of Material -Inspection Program for Civil Shutdown Damper Pressure Steel vanid General Corrosion Engineering Structures and..... .Housinas Boundarv ComDonents U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 12 3.0 Keowee Turbine Guide Bearing Oil Coolers The Turbine Guide Bearing Oil System includes the Turbine Guide Bearing Oil Coolers that are within the scope of License Renewal. The Turbine Guide Bearing Oil Coolers provide the necessary flow of lubricating oil to the Keowee turbine guide bearings.Although the Turbine Guide Bearing Oil Coolers were originally included within the scope of License Renewal in the original LRA, the heat transfer intended function for these heat exchangers was not identified at that time, only the pressure boundary intended function.

Heat transfer 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 18 A 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 external environments.

U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 13 Table 3.1 Aging Management Review Summary Table Keowee 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 Transfer Tubes Transfer Stainless Steel Raw Water Degradation

-3.1.2 Preventative

_Fouling Maintenance Activities Table 3.2 Aging Management Review Summary Table Keowee 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 Program TueHTasera tilesSeeti Heat Transfer Tubes Transfer Stainless Steel Oil Degradation

-Fouling Preventative Maintenance I I_ I I I Activities