BVY 07-054, Vermont, License Renewal Application, Amendment 28 Response to Request for Additional Information

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Vermont, License Renewal Application, Amendment 28 Response to Request for Additional Information
ML072140847
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 07/30/2007
From: Ted Sullivan
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 07-054, TAC MC9668
Download: ML072140847 (69)
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Text

kP%'EnteW Entergy Nuclear Operations, Inc.Vermont Yankee P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500 Tel 802 257 5271 July 30, 2007 Docket No. 50-271 BVY 07-054 TAC No. MC 9668 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Reference:

Subject:

1. Letter, Entergy to USNRC, "Vermont Yankee Nuclear Power Station, License No. DPR-28, License Renewal Application," BVY 06-009, dated January 25, 2006.2. Letter, USNRC to Entergy, "Request for Additional Information for the Review of the Vermont Yankee Nuclear Power Station, License Renewal Application", NVY 07-093, dated July 24, 2007.3. Letter, USNRC to Entergy, "Safety Evaluation Report with Confirmatory Items Related to the License Renewal of Vermont Yankee Nuclear Power Station," NVY 07-036, dated March 30. 2007.Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)License Renewal Application, Amendment 28 On January 25, 2006, Entergy Nuclear Operations, Inc. and Entergy Nuclear Vermont Yankee, LLC (Entergy) submitted the License Renewal Application (LRA) for the Vermont Yankee Nuclear Power Station (VYNPS) as indicated by Reference
1. This letter contains two attachments as listed below to address an NRC Request for Additional Information (RAI) as indicated by Reference 2 and a Safety Evaluation Report (SER) Confirmatory Item as indicated by Reference 3.* Attachment 1: VYNPS License Renewal RAI 4.3.3-1 Response* Attachment 2: SER Confirmatory Item Response Clarification Should you have any questions concerning this letter, please contact Mr. Dave Mannai at (802)258-5422.I declare under penalty of perjury that the foregoing is true and correct, executed on July 30, 2007.Sincerely, Ved A. Srotivan Nl P SlsVieFIesiderýrJ Vermont Yankee Nuclear Power Station cc: See next page enc: Attachments 1 & 2 A 1 V-BVY 07-054 Docket No. 50-271 cc: Mr. James Dyer, Director U.S. Nuclear Regulatory Commission Office O5E7 Washington, DC 20555-00001 Mr. Samuel J. Collins, Regional Administrator U.S. Nuclear Regulatory Commission, Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Jack Strosnider, Director U.S. Nuclear Regulatory Commission Office T8A23 Washington, DC 20555-00001 Mr. Jonathan Rowley, Senior Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike MS-O-1 1 F1 Rockville, MD 20853 Mr. Mike Modes USNRC RI 475 Allendale Rd, King of Prussia, PA 19406 Mr. James S. Kim, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC P.O. Box 157 (for mail delivery)Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street -Drawer 20 Montpelier, Vermont 05620-2601 Diane Curran, Esq.Harmon, Curran, Spielberg

& Eisenberg, LLP 1726 M Street, N.W., Suite 600 Washington, D.C. 20036 BVY 07-054 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station License Renewal Application Amendment 28 VYNPS License Renewal RAI 4.3.3-1 Response VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION ATTACHMENT 1 RAI 4.3.3-1: The license renewal application (LRA) for the Vermont Yankee Nuclear Power Station listed several reactor coolant pressure boundary components that did not receive a plant-specific metal fatigue analysis and cumulative usage factor (CUF). The applicant generated LRA Commitment No. 27 to address this issue. In the commitment, the applicant committed to take one of the following options or a combination of options to ensure that the time-limited aging analysis (TLAA) on environmentally-assisted fatigue (EAF) of these components, and any other Class 1 components requiring reanalysis for EAF, will be acceptable under 10 CFR 54.21 (c)(1) for the period of extended operation:

Option (1): either refine the existing fatigue analyses or perform new fatigue analyses using at least one of four suboptions under this option.Option (2): manage aging by an aging management program (AMP) for the period of extended operation.

Option (3): repair or replace the impacted component prior to exceeding a CUF of 1.0.In order to make a determination on the acceptability of the applicant's TLAA on EAF under the requirements of 10 CFR 54.21 (c)(1), the staff requests that the applicant provide additional information on the option (or options) that will be used for LRA Commitment No. 27. The applicant is requested to describe the methodology that will be used for the chosen option(s) in sufficient detail for staff review. Specifically, the staff requests that: A. If Option (1) is chosen, describe the methodology and the process that will be used to ensure that assumptions, transients, cycles, external loadings, Fen values, and analysis methods are valid for the refined or new fatigue analyses.In the event the refined analyses performed under Option (1) result in CUFs greater than 1.0, describe the option(s) that may be used in addition to Option (1).B. If Option (2) is chosen, describe the AMP in sufficient detail with regard to inspection scope, inspection methods, inspection frequency, and inspection qualification techniques.

C. If Option (3) is chosen, describe how the repair or replacement activity will be implemented in accordance with applicable repair or replacement requirements of the ASME Code Section Xl.RAI 4.3.3-1 Response: Vermont Yankee (VY) intends to comply with Commitment 27 by demonstrating, through the implementation of Option 1, that the cumulative usage factors (CUF) of the most fatigue sensitive locations are less than 1.0 throughout the license renewal period, considering both mechanical and environmental effects. The processes that will be used to develop the calculations for Option 1 are established design and configuration management processes.

These processes are governed by Entergy's 10 CFR 50 Appendix B Quality Assurance (QA) program and include design input verification and independent reviews ensuring that valid assumptions, transients, cycles, external Page 1 of 2 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION ATTACHMENT 1 loadings, analysis methods, and environmental fatigue life correction factors will be used in the refined or new fatigue analyses.The analysis methods for determination of stresses and fatigue usage will be in accordance with an NRC endorsed Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III Rules for Construction of Nuclear Power Plant Components Division 1 Subsection NB, Class 1 Components, Subarticles NB-3200 or NB-3600 as applicable to the specific component.

VY will utilize design transients from VY Design Specifications as well as design transient information from typical BWR-4 references to bound all operational transients.

The numbers of cycles used for evaluation will be based on the design number of cycles and actual VY cycle counts projected out to the end of the license renewal period (60 years).Environmental effects on fatigue usage will be assessed using methodology consistent with the Generic Aging Lessons Learned Report, NUREG-1 801, Rev. 1, (GALL) that states; 'The sample of critical components can be evaluated by applying environmental life correction factors (Fen Methodology) to the existing ASME Code fatigue analyses.Formulae for calculating the environmental life correction factors are contained in NUREG/CR-6583 for carbon and low-alloy steels and in NUREG/CR-5704 for austenitic stainless steels." The Fatigue Monitoring Program currently tracks actual plant transients and evaluates these against the design transients.

Current cycle counts show no limits are approached or are expected to be approached for the current license term. VY has committed to modify the current fatigue monitoring program to require periodic updates of the cumulative usage factors and to include corrective actions if the numbers of analyzed transients are approached (LRA Commitments No. 5 and No.7). The Fatigue Monitoring Program will ensure that the numbers of transient cycles experienced by the plant remain within the analyzed numbers of cycles and hence, the component CUFs remain below the values calculated in the design basis fatigue evaluations.

If ongoing monitoring indicates the potential for a condition outside that analyzed above, Vermont Yankee may perform further reanalysis of the identified configuration using established configuration management processes as described above.If Option 2 of Commitment 27 becomes necessary, the inspection program submitted for approval by the NRC will be described in terms of the ten elements specified in Branch Technical Position RLSB-1 (NUREG-1800, Appendix A-i). Parameters monitored will be the presence and sizing of cracks. Frequency of inspection and acceptance criteria will be established such that detection of aging effects will occur before there is a loss of the component intended function(s).

The method of inspection will be a qualified volumetric technique based on plant-specific and industry-wide operating experience.

If Option 3 becomes necessary, repair or replacement of the affected component(s) will be in accordance with established plant procedures governing repair and replacement activities.

These established procedures are governed by Entergy's 10 CFR 50 Appendix B QA program and meet the applicable repair or replacement requirements of the ASME Code Section Xl.Page 2 of 2 BVY 07-054 Docket 50-271 BVY 07-054 Docket No. 50-271 Attachment 2 Vermont Yankee Nuclear Power Station License Renewal Application Supplement Amendment 28 SER Confirmatory Item Response Clarification VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 License Renewal Application Changes Page 1 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 The following information is provided as a supplement to the previously submitted License Renewal Application.

The need for this information was identified as a Safety Evaluation Report (SER) Confirmatory Item.Note: Insertions

= underlined, deletions

= strike-through Nonsafety-Related Components Affecting Safety-Related Systems Subject to Aging Management Review The following is provided to clarify the systems which are included in the scope of license renewal.Table 2.2-1a is revised to include the following new information:

Table 2.2-1 a Mechanical Systems within the Scope of License Renewal System Code System Code Name LRA Section Section 2.3.3.13, 103 HD & HV Instruments Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, AE Air Evacuation Miscellaneous Systems in Scope for (a)(2)LDBuilding (drainage system Section 2.3.3.13, BLID Buildne ( Miscellaneous Systems in components)

Scope for (a)(2)Section 2.3.3.13, CWP Circulating Water Priminq Miscellaneous Systems in Scope for a)(2)Section 2.3.3.13, ES Extraction Steam Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, HD Heater Drain Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, HV Heater Vent Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, HWC Hydrogen Water Chemistry Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, MUD Make-up Demineralizer Miscellaneous Systems in Scope for (a)(2)Page 2 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Section 2.3.3.13, SO Seal Oil Miscellaneous Systems in Scope for (a)(2)Turbine Building Closed Cooling Section 2.3.3.13, TBCCW Water Miscellaneous Systems in Scope for (a)(2 Section 2.3.3.13, TG Main Turbine Generator Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, TLO Turbine Lube Oil Miscellaneous Systems in Scope for (a)(2)The mechanical systems added to Table 2.2-1a (above) are hereby removed from Table 2.2-2 "Mechanical Systems Not within the Scope of License Renewal" Page 3 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 The following is provided to clarify the description of systems which are included in the scope of license renewal.> Table 2.3.3.13-A is revised to include the following new information:

Table 2.3.3.13-A Systems within the Scope of License Renewal based on the Potential for Physical Interaction with Safety-Related Components (10 CFR 54.4(a)(2))

System Code System Name Section with System Description Section 2.3.3.13, 103 HD & HV Instruments Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, AE Air Evacuation Miscellaneous Systems in Scope for (a)(2)AS Auxiliary Steam Section 2.3.4.1, Auxiliary Steam DBuildinq (drainagqe system Section 2.3.3.13, BLD Buildients) (Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, CWP Circulating Water Priming Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, ES Extraction Steam Miscellaneous Systems in Scope for (aS s2 Section 2.3.3.13, HVD Heater Drain Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, HV Heater Vent Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, HWC Hydrogqen Water Chemistr Miscellaneous Systems in Scope for (a)2 MS Main Steam Section 2.3.4.3, Main Steam Section 2.3.3.13, MUD Make-up Demineralizer Miscellaneous Systems in Scope for (a)(2)SA Service Air Section 2.3.3.7, Instrument Air Page 4 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Section 2.3.3.13, SO Seal Oil Miscellaneous Systems in Scope for (a)(2)Turbine Building Closed Cooling Section 2.3.3.13, TBCCW Waturb Miscellaneous Systems in Water Scope for (a)(2)Section 2.3.3.13, TG Main Turbine Generator Miscellaneous Systems in Scope for (a)(2)Section 2.3.3.13, TLO Turbine Lube Oil Miscellaneous Systems in Scope for (a)(2)> LRA Section 2.3.3.13.2 is revised to add descriptions of scope of license renewal as follows.systems newly added to the HD & HV Instruments The purpose of the 103 system is to provide indication, alarm, and control functions for associated systems (heater drains and heater vents).Air Evacuation The purpose of the AE system is to evacuate gqases from the main turbine and main condenser during startup and maintain the system free of noncondensible -gases during operation.

Buildinq (drainage system components)

The BLD system includes floor drains and the site sewers. This system classification also desiqnates buildings and structures which are evaluated in Section 2.4 of this LRA..Circulating Water Priming The purpose of the CWP system is to provide for evacuation of the discharae side of the main condenser.

Extraction Steam The purpose of the ES system is to supply steam to the shell side of various feedwater heaters for condensate and feedwater heatinq.Heater Drain Page 5 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 The purpose of the HD system is to provide proper level and control for the moisture separator and feedwater heaters by providing drain capability to the main condenser.

Heater Vent The purpose of the HV system is to provide for venting of non-condensable gases back to the main condenser.

Hvdrooen Water Chemistry The purpose of the HWC system is to mitiqate the chemical conditions in the reactor that allow IGSCC in the recirculation piping and reactor vessel internals.

The HWC system injects hydrogen into the reactor feedwater at the suction of the feedwater pumps.Make-up Demineralizer The purpose of the MUD system is to provide a supply of treated water to the DW system that may be used as makeup for the station and reactor cycles.Seal Oil The purpose of the SO system is to provide shaft sealing for the main generator.

Turbine Building Closed Cooling Water The purpose of the TBCCW system is to supply demineralized water to cool various nonsafety-related auxiliary equipment located in the turbine building in support of power generation Main Turbine Generator The purpose of the TG system is to convert the thermodynamic energy of steam into a reliable source of electrical energy for use on the transmission network and the station auxiliary busses.Turbine Lube Oil The purpose of the TLO system is to provide lube oil for lubrication of the main turbine.Page 6 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 The following is provided to clarify the description of components subject to aging management review which are to be included in aging management programs during the period of extended operation.

> Table 2.3.3.13-B is revised to include the following new information:

Table 2.3.3.13-B Description of Nonsafety-Related System Components Subject to Aging Management Review Based on 10 CFR 54.4(a)(2) for Physical Interactions

/System Code Nonsafety-Related Components Subject to AMR 103 Portion of the system in the turbine building AE Portion of the system in the turbine building Portion of the system inside associated with the plant stack !eep-sea'structure AS Portion of the system in the turbine building The portion of the system in the reactor building and the turbine building Portion of the system at the ECCS keep-full station in the turbine building, as well as the area on elevation 252 in the turbine building C where water pi'p. ru along the wall.Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.Portion of the system in the turbine building.

Components outside the CD safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.Portion of the system in the CST valve and instrument enclosure, the CST primary containment building, and the reactor building, and the turbine building.Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.Page 7 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Portion of the system in cooling tower #2 cell 1 and the turbine building.CWP Portion of the system in the turbine building Portion of the system in the diesel generator rooms in the turbine DG building Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.Portion of the system in the control building, the reactor building, and at the diesel g.nerator rooms in the turbine building and in the CST DW valve and instrument enclosure.

Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.ES Portion of the system in the turbine buildinq FDW Portion of the system in the reactor building and in primary containment and the turbine building Portion of the system in the fuel oil transfer pump house and the EQ turbine building.Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.Portion of the system in cooling tower #2 cell 1 and the reactor building, the turbine building, and the service water pump area of the FP intake structure.

Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.Portion of the system in the CST valve and instrument enclosure, the control building, the reactor building, and at the diesel geneFator HB reems in the turbine building Components outside the safety class pressure boundary yet relied upon to provide structural/seismic support for the pressure boundary.HD Portion of the system in the turbine building Page 8 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 HV Portion of the system in the turbine buildinq Portion of the system in the reactor building and the turbine building.HVAC Components outside the safety class pressure boundary yet relied upon to provide structural/seismic support for the pressure boundary.HWC Portion of the system in the turbine building The portion of the system in the reactor building and the turbine building that requires aging management review due to potential spatial interaction are tho ooling arnd lubrication S"ubc..p....t for the c..tainmc.

t air comprossor. (C 2 !A) and its p,"ocooe, andas well as the air dryer towers (tanks), drain piping, IA valves, and traps associated with the instrument air dryers (D-1-1A and D-1-1 B) and the containment air dryer (D-2-1A), as well as the drain piping, valves, and traps associated with the air receiver tank and knock-out drum (TK-55-1A and TK-154-lA).

Components outside the safety class pressure boundary yet relied upon to provide structural/seismic support for the pressure boundary.MS Portion of the system in the turbine building MUD Portion of the system in the turbine building Portion of the system in the reactor building and the turbine building PASS Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.Portion of the system in the "A" diesel gone.ratr room. in the turbine building Portion of the system in the CST valve and instrument enclosure, service water pump area of the intake structure, plant stack, primary RDW containment building, and reactor building and turbine building.Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.Portion of the system in the reactor building and the turbine building.Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.Page 9 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 The portion of the system in the turbine building that requires aging management review due to potential spatial interaction includes the SA drain piping, valves, and traps associated with the air receiver tanks (TK-5-1A and TK-5-1 B).Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.Portion of the system in the turbine building SC Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.SO Portion of the system in the turbine building Portion of the system in the reactor building, turbine building, and SPL plant stack.Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.Portion of the system in the service water pump area of the intake SW structure and the reactor building and the turbine building.Components outside the safety class pressure boundary, yet relied upon to provide structural/seismic support for the pressure boundary.TBCCW Portion of the system in the turbine building TG Portion of the system in the turbine building TLO Portion of the system in the turbine building Page 10 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 The following is provided to clarify the description of components subject to aging management review which are to be included in aging management programs during the period of extended operation.

LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-43, HD & HV Instruments (103) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Bolting Pressure boundary Piping Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For comoonent tvoes included under 10 CFR 54.4(a)(21-the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 11 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-44, Air Evacuation (AE)System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Bolting Pressure boundary Filter housing Pressure boundary Heat exchanger Pressure boundary nPressure boundary Pump casing Pressure boundary Rupture disk Pressure boundary Strainer housing Pressure boundary Trap Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs. -LRA Table 2.3.3-13-1, Augmented Offgas (AOG) System, Components Affecting Safety-Related Systems-Components Management Review, is revised adding the following line item.Component Type Intended Function 1 Steam trap Pressure boundary Nonsafety-Related Subject to Aging 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 12 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-45, Auxiliary Steam (AS)System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Bolting Pressure boundary Heat exchanger Pressure boundary (sh _IIQ PPressure boundary Stream trap Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.> LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-46, Building (drainage system components)

System (BLD), Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Bolting Pressure boundary Piping Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 13 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Table 2.3.3-13-2, Condensate (C) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line items.Component Type Intended Function 1 Heat exchanger (shell) Pressure boundar Orifice Pressure boundary Pump casing Pressure boundary Steam trap Pressure boundary Tank Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.LRA Table 2.3.3-13-4, Components Affecting Management Review, is Condensate Demineralizer (CD) System, Nonsafety-Related Safety-Related Systems-Components Subject to Aging revised adding the following line items.Component Type Intended Function 1 Boltinq Pressure boundary Filter housing Pressure boundary Pump casinq Pressure boundary Tank Pressure boundary Tubing Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 14 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Table 2.3.3-13-7, Condensate Storage and Transfer (CST) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line item.Component Type Intended Function 1 Filter housinq Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.> LRA Table 2.3.3-13-9, Circulating Water (CW) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line items.Component Type Intended Function'Expansion ioint Pressure boundary Tank Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 15 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-47, Circulating Water Priming (CWP) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Bolting Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tank Pressure boundary Trap Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes orovidina structural/seismic sunoort for comoonents that are included for nonsafetv-related SSCs directly connected to safety-related SSCs.LRA Table 2.3.3-13-10, Diesel Generator and Auxiliaries (DG) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised to delete the following line item.1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 16 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-48, Extraction Steam (ES)System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function'Bolting Pressure boundary Expansion joint Pressure boundary Orifice Pressure boundary Piping Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2).

the intended function of Pressure boundary includes orovidino struictujrl/seismic sunnort for comoonents that are inrcluded for nonn'fe~tv-rmkldtd RC~s dirpcoily, providinn structural/seismic support for components that are included for nonsafetv-related SSCs directlv connected to safety-related SSCs.LRA Table 2.3.3-13-13, Feedwater (FDW) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line items.Component Type Intended Function'Heat exchanger Pressure boundary kgshellI Orifice Pressure boundary Pump casing Pressure boundary Strainer housing Pressure boundary A1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 17 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Table 2.3.3-13-14, Fuel Oil (FO) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line item.Component Type Intended Function 1 Strainer housinq Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.> LRA Table 2.3.3-13-15, Fire Protection (FP) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line items.Component Type Intended Function 1 Orifice Pressure boundary Strainer housinq Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.LRA Table 2.3.3-13-18, House Heating Boiler (HB) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line items.Component Type Intended Function 1 Heat exchanger Pressure boundary Strainer housingq Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 18 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-49, Heater Drain (HD) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Bolting Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-50, Heater Vent (HV) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function'Bolting Pressure boundary Orifice Pressure boundary PPressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 19 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 LRA Table 2.3.3-13-21, Heating, Ventilation, and Air Conditioning (HVAC) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line items and deleting one line item.Component Type Intended Function 1 Duct Pressure boundary Fan housinq Pressure boundary Heat exchanger Pressure boundary (shell)H~atX~hag9FPressuro boundary Pump casing Pressure boundary Strainer housing Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-51, Hydrogen Water Chemistry (HWC) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function'Bolting Pressure boundary Pipinq Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providino structural/seismic SUDoort for components that are included for nonsafetv-related SSCs directly connected to safety-related SSCs.Page 20 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Table 2.3.3-13-22, Instrument Air (IA) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised to delete the following line item.1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.;> LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-52, Main Steam (MS) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Bolting Pressure boundary Heat exchanger Pressure boundary (shelll Orifice Pressure boundary Piig Pressure boundary Strainer housing Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For component tVpes included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 21 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-53, Make-up Demineralizer (MUD) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function'Bolting Pressure boundary Filter housing Pressure boundary Piig Pressure boundary Pump casing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For comDonent tvnes included under 10 CFR 54.4(a)(2).

the intended function of Dressure boundary includes providingq structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.> LRA Table 2.3.3-13-29, Potable Water (PW) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line items.Component Type Intended Function'Filter housinq Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 22 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-54, Service Air (SA) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Bolting Pressure boundary P!i Pressure boundary Tank Pressure boundary Trap Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.LRA Table 2.3.3-13-39, Stator Cooling (SC) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line items.Component Type Intended Function'Boltinq Pressure boundary Filter housing Pressure boundary Heat exchanger Pressure boundary Pump casing Pressure boundary Strainer housing Pressure boundary Tank Pressure boundary Tubing Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 23 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT

2) LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-55, Seal Oil (SO) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Bolting Pressure boundary Filter housinq Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Sight glass Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.LRA Table 2.3.3-13-41, Sampling (SPL) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line item.Component Type Intended Function 1 Strainer housing Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 24 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Table 2.3.3-13-42, Service Water (SW) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, is revised adding the following line item.Component Type Intended Function 1 Heat exchanger Pressure boundary (she ll 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.> LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-56, Turbine Building Closed Cooling Water (TBCCW) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Bolting Pressure boundary Heat exchanger Pressure boundary (shell)aging Pressure boundary Pump casing Pressure boundary Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For comoonent tvnes included under 10 CFR 54.4(a(2Y.

the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.Page 25 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-57, Main Turbine Generator (TG) System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Bolting Pressure boundary Filter housing Pressure boundary Piping Pressure boundary Pump casing Pressure boundary Turbine casing Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes orovidino structujral/seismic sunnort for comoonents that ar included for nonsafetv-related SSCsh direc~tly nrovidina structural/seismic sunnort for cornnonents that are included for nonsaf etv- related SSCs directly connected to safety-related SSCs.Page 26 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 LRA Section 2.3.3 is revised to add a new Table 2.3.3-13-58, Turbine Lube Oil (TLO)System, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function 1 Boltinq Pressure boundary Filter housing Pressure boundary Heat exchanger Pressure boundar (shellP Piin Pressure boundary Pump casing Pressure boundary Strainer housing Pressure boundary, Tank Pressure boundary Tubing Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs, Page 27 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-43, HD & HV Instruments (103) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.NUREG Component Intended Aging Effect Aging -1801, Table 1 Notes Type Function Material Environment Requiring Management Vol.2 Item Management Programs Item Pressure Carbon Air- indoor Loss of System VII.l-4 3.3.1-43 E Bolting boundary steel (ext) material Walkdown (AP-27)Pressure Stainless Air-indoor VII.J-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-1 7)Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A Piping boundary steel (ext) material Walkdown (A-77)Water VII.E3- 3.3.1-17 C Pressure Carbon Treated water Loss of Cher 18 Piping boundary steel (int) material Chemistry 18 Control -BWR (A-35)Pressure Copper Air -indoor V.F-3 3.2.1-53 C Tubing boundary alloy (ext) None None (EP-10)* 15% Zn Pressure Copper Treated water Loss of Water VII.E3-9 3.3.1-31 C Tubing boundary alloy (int) material Chemistry (AP-64)* 15% Zn Control -BWR Valve Pressure Carbon Air- indoor Loss of System V11.1-8 3.3.1-58 A body boundary steel (ext) material Walkdown (A-77)Water VIII.E- 3.4.1-4 A Valve Pressure Carbon Treated water Loss of Cher 33 body boundary steel (int) material Control -BWR (S-09)Page 28 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-44, System, Nonsafety-Related Components Affecting Safety-Related of Aging Management Evaluation, as follows.Air Evacuation (AE)Systems -Summary Aging Effect Aging NUREG Componen Intended Material Environment Requiring Management

-1801, Table 1 Notes Type Function Management Programs Vol.2 Item Item Bolting Pressure Carbon Air -indoor Loss of System VII.l-4 3.3.1-43 E boundary steel (ext) material Walkdown (AP-27)Pressure Stainless Air- indoor VII.J-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-1 7)Filter Pressure Carbon Air -indoor Loss of System VII.1-8 3.3.1-58 A housing boundary steel (ext) material Walkdown (A-77)Water VII.E3- 3.3.1-17 C Filter Pressure Carbon Treated water Loss of Cher 18 housing boundary steel (int) material Control -BWR (A-35)Heat Pressure Carbon Air- indoor Loss of System V1101- 3.3.1-59 C exchanger boundary steel (ext) material Walkdown (AP-41)(shell) _________

_________________

Heat Pressure Carbon Treated water Loss of Water VIIE3- 3.3.1-17 C exchanger boundary steel (int) material Chemistry 18 (shell) Control -BWR (A-35)Pressure Carbon Air -indoor Loss of System VII.l-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Water VII.E3- 3.3.1-17 C Piping Pressure Carbon Treated water Loss of Chemistry 18 boundary steel (int) material Control -BWR (A-35)Pump Pressure Carbon Air- indoor Loss of System VII.I-8 3.3.1-58 A casing boundary steel (ext) material Walkdown (A-77)Water VII.E3- 3.3.1-17 C Pump Pressure Carbon Treated water Loss of Cher 18 casing boundary steel (int) material Contro B 8 Control -BWR (A-35)Rupture Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-57 A disk boundary steel (ext) material Walkdown (A-77)Rupture Pressure Carbon Treated water Loss of Water VIllA- 3.4.1-4 C disk boundary steel (int) material Chemistry 15__________Control

-BWR (S-04) ____Strainer Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A housing boundary steel (ext) material Walkdown (S-29)Strainer Pressure Carbon Treated water Loss of Water Vill.& 3.4.1-4 A housing boundary steel (int) material Chemistry 33 hui bodr se (int)_material Control -BWR (S-09)Pressure Carbon Air -indoor Loss of System VIII.H-7 3.4.1-28 A Trap boundary steel (ext) material Walkdown (S-29)Water VIII.E- 3.4.1-4 A Pressure Carbon Treated water Loss of Cher 33 Trap boundary steel (int) material Chemistry 33 1 Control -BWR (S-09)Pressure Copper Air -indoor V.F-3 3.2.1-53 C Tubing alloy (ext) None None (EP-1 0)boundary < 15% Zn I Pressure Copper Treated water Loss of Water VII.E3-9 3.3.1-31 C Tubing boundary alloy (int) material Chemistry (AP-64)< 15% Zn Control -BWR Page 29 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Page 30 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 LRA Section 3.3.2, Table 3.3.2-13-1, Augmented Offgas (AOG) System, Related Components Affecting Safety-Related Systems -Summary Management Evaluation, is revised adding the following line items.Nonsafety-of Aging Aging Effect Aging NUREG Componen Intended Material Environment Requiring Management

-1801, Table 1 Notes Type Function Management Programs Vol.2 Item Item Flow VIll.A- 3.4.1-29 C Pressure Carbon Steam > 220'F Loss of a le d 17 boundary steel (int) material corrosion (S-15)Water VIII.A- 3.4.1-2 C Pressure Carbon Steam > 220'F Loss of Watr V3 Piping boundary steel (int) material Chemistry 15____________Control

-BWR (S-04)Pressure Carbon Steam > 220'F Cracking -TLAA -metal V111.12- 3.4.1-1 C Piping boundary steel (int) fatigue fatigue (S08)Pressure Carbon Treated water Cracking -TLAA -metal V5II.B2- 3.4.1-1 C Piping boundary steel > 220'F (int) fatigue fatigue (S-08)Steam Pressure Carbon Air- indoor Loss of System V.E-7 3.2.1-31 A trap boundary steel (ext) material Walkdown (E-44)Water VIll.A- 3.4.1-2 C Steam Pressure Carbon Steam > 220'F Loss of Cher 15 trap boundary steel (int) material Chemistry 15 Control -BWR (S-04)Steam Pressure Carbon Steam > 220'F Cracking -TLAA -metal V111.12- 3.4.1-1 C trap boundary steel (int) fatigue fatigue 5 Steam Pressure Carbon Treated water Cracking -TLAA -metal trap boundary steel > 220'F (int) fatigue fatigue 5S-08)Valve Pressure Carbon Air -indoor Loss of System V.E-7 3.2.1-31 A body boundary steel (ext) material Walkdown (E-44)Flow VIll.A- 3.4.1-29 C Valve Pressure Carbon Steam > 220'F Loss of a le d 17 body boundary steel (int) material corroio 17 corrosion (S-15)Valve Pressure Carbon Steam > 220°F Loss of Water VIII.A- 3.4.1-2 C steel (int) material Chemistry 15 body boundary steel(inControl

-BWR (S-04)Valve Pressure Carbon Steam > 220'F Cracking -TLAA- metal V.D2-32 3.2.1-1 A body boundary steel (int) fatigue fatigue (E-10)Water VIII.E- 3.4.1-4 A Valve Pressure Carbon Treated water Loss of Cher 33 body boundary steel (int) material Chemistry 33 Control -BWR (S-09)Valve Pressure Carbon Treated water Cracking -TLAA -metal Vill.12- .4.1-1 C 5 body boundary steel > 220'F (int) fatigue fatigue (S-08)Page 31 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-45, Auxiliary Steam (AS)System, Nonsafety-Related Components Affecting Safety-Related of Aging Management Evaluation, as follows.Systems -Summary dAging Effect Aging NUREG Component neddAigEfc gn -1801, Table 1 Typoen Incten Material Environment Requiring Management Vol.2 Te Notes Type Function Mngm t Prras Vol.2 Item Management Programs Item Pressure Carbon Air- indoor Loss of System VII.1-4 3.3.1-43 E Bolting boundary steel (ext) material Walkdown (AP-27)Pressure Stainless Air- indoor VIIJ-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-1 7)Heat VII.F1- 3.3.1-59 C exchanger Pressure Carbon Air -indoor Loss of System 10 eshellr boundary steel (ext) material Walkdown AP-41)Heat H eat Pressure Carbon Treated water Cracking -One-Time exchanger boundary steel > 220'F (int) fatigue Inspection (shell) I_____Heat Water Vii.E3- 3.3.1-17 C Hexanger Pressure Carbon Treated water Loss of Cher 18 exchanger budr ste itmaral Chemistry 18 (shell) boundary steel (int) material Control -BWR (A-35)Piping Pressure Carbon Air -indoor Loss of System VII.I-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Flow VIll.A- 3.4.1-29 C Pressure Carbon Steam > 220'F Loss of a le d 17 Piping boundary steel (int) material accelerated 17 corrosion

_(S-15)Pressure Carbon Steam > 220'F Loss of Water VIllA- 3.4.1-2 C Piping boundary steel (int) material Chemistry 15 Control -BWR (S-04)Pressure Carbon Steam > 220'F Cracking -TLAA -metal VIII.52- 3.4.1-1 C Piping boundary steel (int) fatigue fatigue (S08)Pressure Carbon Treated water Cracking -TLAA -metal VIII.B2- 3.4.1-1 C Piping boundary steel > 220'F (int) fatigue fatigue 5 (S-08)Pressure Carbon Treated water Loss of Water VII.E3- 3.3.1-17 C Piping boury steel Trete water Chemistry 18 boundary steel (int) material Control -BWR (A-35)Steam Pressure Carbon Air- indoor Loss of System V.E-7 3.2.1-31 A trap boundary steel (ext) material Walkdown (E-44)Flow VIll.A- 3.4.1-29 C Steam Pressure Carbon Steam > 220'F Loss of a le d 17 accelerated 17 trap boundary steel (int) material corrosion (S-15)Steam Pressure Carbon Steam > 220'F Loss of Water VIII.A- 3.4.1-2 C trap boundary steel (int) material Chemistry 15 Control -BWR (S-04)Steam Pressure Carbon Steam > 220'F Cracking -TLAA -metal VI11.12- 3.4.1-1 C 5 trap boundary steel (int) fatigue fatigue 5 Steam Pressure Carbon Treated water Cracking -TLAA -metal VIII.B2- 3.4.1-1 C 5 trap boundary steel > 220'F (int) fatigue fatigue (S08)Water VII.E3- 3.3.1-17 C Steam Pressure Carbon Treated water Loss of Chemistry 18 trap boundary steel (int) material Control -BWR (A-35)Tubing Pressure Carbon Air- indoor Loss of System V.E-7 3.2.1-31 A boundary steel (ext) material Walkdown (E-44) _ I_ I Page 32 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Flow V.D2-31 3.2.1-19 A Pressure Carbon Steam > 220'F Loss of a le d (E- 3. -Tubing boundary steel (int) material accelerated (E-07)corrosion Pressure Carbon Treated water Loss of Water VIIE3- 3.3.1-17 C Tubing boundary steel (int) material Chemistry 18 Control -BWR (A-35)Valve Pressure Carbon Air -indoor Loss of System Vl1.l-8 3.3.1-58 A body boundary steel (ext) material Walkdown (A-77)Valve Pressure Carbon Steam > 220'F Loss of Flow VllA- 3.4.1-29 C body boundary steel (int) material corroio 17 corrosion (S-15)Valve Pressure Carbon Steam > 220°F Loss of Water VIII.A- 3.4.1-2 C body boundary steel (int) material Chemistry 15 Control -BWR (S-04)Valve Pressure Carbon Steam > 220'F Cracking -TLAA -metal V.D2-32 3.2.1-1 A body boundary steel (int) fatigue fatigue (E-10)Valve Pressure Carbon Treated water Cracking -TLAA -metal V111.12- 3.4.1-1 C 5 body boundary steel > 220'F (int) fatigue fatigue (S-08)Water VIII.E- 3.4.1-4 A Valve Pressure Carbon Treated water Loss of Cher 33 body boundary steel (int) material Control -BWR (S-09)LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-46, Buildings (drainage system components)

System (BLD), Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.Aging Effect Aging NUREG Componen Intended Material Environment Requiring Management

-1801, Table 1 Notes Type Function Management Programs Vol.2 Item Bolting Pressure Carbon Air -indoor Loss of System VII.l-4 3.3.1-43 E boundary steel (ext) material Walkdown (AP-27)Pressure Stainless Air- indoor VII.J-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-1 7)Piping Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Periodic VII.G-24 3.3.1-68 E Pressure Carbon Untreated Loss of Surveillance (A-33)Piping boundary steel water (int) material and Preventive I_ Maintenance Page 33 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2, Table 3.3.2-13-2, Condensate (C) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, is revised adding the following line items.NUREG Component Intended Material Environment Aging Efc Aging -1801, Table 1 Notes Typ Fncio Mteral Enirnmnt Requiring Management Vol.2 Item Noe Type Function Management Programs Item Heat Pressure Carbon Air -indoor Loss of System V(Sl.H-7 3.4.1-28 A exchanger boundary steel (ext) material Walkdown (S-29)(shell)eat Pressure Carbon Treated water Cracking -One-Time exchanger boundary steel > 220'F (int) fatigue Inspection (shell)Heat Water VIII.E-7 3.4.1-5 A Hexanger Pressure Carbon Treated water Loss of Cher (S- 3.-(shell) boundary steel (int) material Controly-BWR Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A boundary steel (ext) material Walkdown (S-29)Pressure Carbon Treated water Loss of Water VIIIE- 3.4.1-4 A Orifice boundary steel (int) material Chemistry 33 Control -BWR (S-09)Pressure Carbon Steam > 220'F Loss of Water VIllA- 3.4.1-2 A Piping boundary steel (int) material Chemistry 15 Control -BWR (S-04)Flow VIII.B2- 3.4.1-29 C Pressure Carbon Steam > 220'F Loss of ale d 4 Piping boundary steel (int) material accelerated 4 corrosion (S-15)Pressure Carbon Steam > 220'F Cracking -TLAA -metal VIII.52- 3.4.1-1 C Piping boundary steel (int) fatigue fatigue (S-08)Pressure Carbon Treated water Cracking -TLAA -metal VIII.B2- 3.4.1-1 C Piping boundary steel > 220°F (int) fatigue fatigue 5 (S-08)Pump Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A casing boundary steel (ext) material Walkdown (S-29)Water VIII.E- 3.4.1-4 A Pump Pressure Carbon Treated water Loss of Chemistry 33 casing boundary steel (int) material Control -BWR (S-09)Steam Pressure Carbon Air -indoor Loss of System VIII.H-7 3.4.1-28 A trap boundary steel (ext) material Walkdown (S-29)Steam Pressure Carbon Steam > 220°F Loss of Flow VIII.B2- 3.4.1-29 C trap boundary steel (int) material accelerated 4 corrosion (S-15)Steam Pressure Carbon Steam > 220°F Loss of Water VIllA- 3.4.1-2 A trap boundary steel (int) material Chemistry 15 Control -BWR (S-04)Steam Pressure Carbon Steam > 220'F Cracking -TLAA -metal VIII.B2- 3.4.1-1 C 5 trap boundary steel (int) fatigue fatigue (S08)Water VIII.E- 3.4.1-4 A Steam Pressure Carbon Treated water Loss of Cher 33 trap boundary steel (int) material Chemistry 33 Control -BWR (S-09)Steam Pressure Carbon Treated water Cracking -TLAA -metal VIII.B2- 3.4.1-1 C 5 trap boundary steel > 220°F (int) fatigue fatigue (S-08)_____

Page 34 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Page 35 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2, Table 3.3.2-13-4, Condensate Demineralizer (CD) System, Nonsafety-Related Components Affecting Safety-Related Systems Management Evaluation, is revised adding the following line items.-Summary of Aging Component Intended Type Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-1801, Vol.2 Item Table 1 Item Notes Bolting Pressure Carbon Air -indoor Loss of System VIII.H-4 3.4.1-22 E Bolting boundary steel (ext) material Walkdown (S-34)Bolting Pressure Stainless Air -indoor VIIi.1-10 3.4.1-41 C Bolting boundary steel (ext) None None (SP-12)Filter Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A housing boundary steel (ext) material Walkdown (S-29)Water VIII.E- 3.4.1-4 A Filter Pressure Carbon Treated water Loss of Cher 33 housing boundary steel (int) material Chemistry 33 Control -BWR (S-09)Pump Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A casing boundary steel (ext) material Walkdown (S-29)Water VIII.E- 3.4.1-4 A Pump Pressure Carbon Treated water Loss of Cher 33 casing boundary steel (int) material Chemistry 33 Control -BWR (S-09)Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A boundary steel (ext) material Walkdown (S-29)Pressure Carbon Treated water Loss of Water V1IIE- 3.4.1-4 A Tank boundary steel (int) material Chemistry 33 bounaryControl

-BWR (S-09)Pressure Copper VIII.1-2 3.4.1-41 A T rsueAir -indoor Nn oe (P6 Tubing boundary alloy < (ext) None None (SP-6)15% Zn Pressure Copper Treated water Loss of Water VILA-5 3.4.1-15 C Tubing Peure alloy < (int) material Chemistry (SP-61)boundary 15% Zn Control -BWR Page 36 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2, Table 3.3.2-13-7, Condensate Storage and Transfer (CST) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, is revised adding the following line items.Aging Effect Aging NUREG Componen Intended Material Environment Requiring Management

-1801, Table 1 Notes Management Programs Vol.2 Item Item Filter Pressure Carbon Air -outdoor Loss of System VIII.H-7 3.4.1-28 A housing boundary steel (ext) material Walkdown (S-29)Water VIII.E- 3.4.1-4 A Filter Pressure Carbon Treated water Loss of Cher 33 housing boundary steel (int) material Control- BWR (S-09)LRA Section 3.3.2, Table 3.3.2-13-9, Circulating Water (CW) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, is revised adding the following line items.Page 37 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-47, Circulating Water Priming (CWP) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.Aging Effect Aging NUREG Component Intended Aging Magint -1801, Table 1 Notes Type Function Material Environment Requiring Management Vol.2 Item Management Programs Item Pressure Carbon Air- indoor Loss of System VII.l-4 3.3.1-43 E Bolting boundary steel (ext) material Walkdown (AP-27)Pressure Carbon Air- outdoor Loss of System VII.I-1 3.3.1-43 E Bolting boundary steel (ext) material Walkdown (AP-28)Bolting Pressure Stainless Air -indoor VII.J-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-17)Bolting Pressure Stainless Air -outdoor None None G Bolting boundary steel (ext)Pressure Carbon Condensation Loss of System V110.1- 3.4.1-28 A Piping boundary steel (ext) material walkdown 10 (S-42)Periodic VIII.E-6 3.4.1-31 E Pressure Carbon Raw water (int) Loss of Surveillance (S-24)Piping boundary steel material and Preventive Maintenance Pump Pressure Carbon Condensation Loss of System V10I.H- 3.4.1-28 A casing boundary steel (ext) material walkdown 10 (S-42)Periodic VIIIE-6 3.4.1-31 E Pump Pressure Carbon Raw water (int) Loss of Surveillance (S-24)casing boundary steel material and Preventive Maintenance Pressure Carbon Condensation Loss of System V10I.1- 3.4.1-28 A Tank boundary steel (ext) material walkdown 10 (S-42)Periodic VIII.E-6 3.4.1-31 E Tank Pressure Carbon Raw water (int) Loss of Surveillance (S-24)boundary steel material and Preventive Maintenance Pressure Carbon Condensation Loss of System VIII.H- 3.4.1-28 A Trap boundary steel (ext) material walkdown 10 (S-42)Periodic VIII.E-6 3.4.1-31 E Trap Pressure Carbon Raw water (int) Loss of Surveillance (S-24)boundary steel material and Preventive Maintenance Pressure Copper Condensation Loss of System VI.F16 -3.3.1-25 E Tubing alloy < (ext) material walkdown 16 boundary 15% Zn (A-46)Periodic VIIIE- 3.4.1-32 E Pressure Copper Loss of Surveillance 18 boundary alloy Raw water (int) material and Preventive (SP-31)Tubing boundary 15% Zn Maintenance Valve Pressure Carbon Condensation Loss of System VIII.H- 3.4.1-28 A body boundary steel (ext) material walkdown 10 (S-42)Page 38 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Periodic VIII.E-6 3.4.1-31 E Valve Pressure Carbon Raw water (int) Loss of Surveillance (S-24)body boundary steel material and Preventive Maintenance Page 39 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2, Table 3.3.2-13-10, Diesel Generator

& Auxiliaries (DG) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, is revised to delete the following line items.Page 40 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-48, Extraction Steam (ES)System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.Aging Effect Aging NUREG Componen!

Intended Agn fet Aig -1801, Table 1 Noe Typonent Fnctiond Material Environment Requiring Management Vol.2 Tem Notes Type Function Mngmt Prras Vol.2 Item Management Programs Item Bolting Pressure Carbon Air -indoor Loss of System VIIIH-4 3.4.1-22 E boundary steel (ext) material Walkdown (S-34)Pressure Stainless Air -indoor VIII1.-10 3.4.1-41 C Bolting boundary steel (ext) None None (SP-12)Expansion Pressure Stainless Air- indoor None None VIII.I-10 3.4.1-41 A joint boundary steel (ext) (SP-12)Water VIII.A- 3.4.1-37 C Expansion Pressure Stainless Steam > 270°f Loss of Chemistry 13 joint boundary steel (int) material Control -BWR (SP-46)Expansion Pressure Stainless Steam > 270'f Cracking -TLAA -metal H joint boundary steel (int) fatigue fatigue Steam > 270'f Cracking Water VIII.B2- 3.4.1-13 A Expansion Pressure Stainless (int) Chemistry 1 joint boundary steel itChmsr 1 Control -BWR (SP-45)Expansion Pressure Stainless Treated water Cracking Water VIII.A- 3.4.1-13 C joint boundary steel > 270'f (int) Chemistry 11 Control -BWR (SP-45)Expansion Pressure Stainless Treated water Cracking -TLAA -metal H joint boundary steel > 270°f (int) fatigue fatigue Expansion Pressure Stainless Treated water Loss of Water VIII.C-1 3.4.1-16 A joint boundary steel > 270'f (int) material Chemistry (SP-1 6)Control -BWR Pressure Carbon Air -indoor Loss of System VIII.H-7 3.4.1-28 A boundary steel (ext) material Walkdown (S-29)Pressure Carbon Steam > 220'F Loss of Flow VIII.C-5 3.4.1-29 A Orifice boundary steel (int) material accelerated (S-15)corrosion Pressure Carbon Steam > 220'f Cracking -TLAA -metal V111.12- 3.4.1-1 C Orifice boundary steel (int) fatigue fatigue (S0)Water VIII.C-3 3.4.1-2 A Pressure Carbon Steam > 220'f Loss of Cher (S- 3.-Orifice boundary steel (int) material Chemistry (S-04)Control -BWR Pressure Carbon Treated water Cracking -TLAA -metal VIII.B2- 3.4.1-1 C Orifice boundary steel > 220'F (int) fatigue fatigue 5-(S-08)Pressure Carbon Treated water Loss of Water VIII.C-6 3.4.1-4 A Orifice boundary steel (int) material Chemistry (S-09)Control -BWR Piig Pressure Carbon Air -indoor Loss of System VIII.1--7 3.4.1-28 A Piping boundary steel (ext) material Walkdown (S-29)Pressure Carbon Steam > 220'F Loss of Flow VIII.C-5 3.4.1-29 A Piping boundary steel (int) material accelerated (S-15)corrosion Water VIII.C-3 3.4.1-2 A Pressure Carbon Steam > 220'F Loss of Chemistry (S-04)Piping boundary steel (int) material Control -BWR (S0 Page 41 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Pressure Carbon Steam > 220'F Cracking -TLAA -metal V5II.B2- 3.4.1-1 C Piping boundary steel (int) fatigue fatigue (S-08)Pressure Carbon Treated water Cracking -TLAA -metal V111.12 3.4.1-1 C Piping boundary steel > 220'F (int) fatigue fatigue 5 (S-08)Water VIII.C-6 3.4.1-4 A Pressure Carbon Treated water Loss of Che r (S3. -Piping boundary steel (int) material Control -BWR Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A Tubing boundary steel (ext) material Walkdown (S-29)Pressure Carbon Treated water Loss of Water VIII.C-6 3.4.1-4 A Tubing boundary steel (int) material Chemistry (S-09)Control -BWR Valve Pressure Carbon Air -indoor Loss of System VIII.H-7 3.4.1-28 A body boundary steel (ext) material Walkdown (S-29)Valve Pressure Carbon Steam > 220oF Loss of Flow VIII.C-5 3.4.1-29 A accelerated (S-15)body boundary steel (int) material corrosion Water VIII.C-3 3.4.1-2 A Valve Pressure Carbon Steam > 220'F Loss of Cher (S-34-body boundary steel (int) material Control -BWR Valve Pressure Carbon Steam > 220'F Cracking -TLAA -metal VIII.B2- 3.4.1-1 C 5 body boundary steel (int) fatigue fatigue (S0)VIII.B2- 3.4.1-1 C Valve Pressure Carbon Treated water Cracking -TLAA -metal V 5 body boundary steel > 220'F (int) fatigue fatigue (S-08)Water VIII.C-6 3.4.1-4 A Valve Pressure Carbon Treated water Loss of Cher (3-09)body boundary steel (int) material Control -BWR (09 LRA Section Components Evaluation, is 3.3.2, Table 3.3.2-13-13, Feedwater Affecting Safety-Related Systems -revised adding the following line items.(FDW) System, Nonsafety-Related Summary of Aging Management Page 42 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Orifice Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A boundary steel (ext) material Walkdown (S-29)Pressure Carbon Treated water Cracking -TLAA -metal V111.12- 3.4.1-1 A boundary steel > 220'F (int) fatigue fatigue (S-li)Water VIII.D2- 3.4.1-4 A Pressure Carbon Treated water Loss of Chemistry 7 Orifice boundary steel > 220'F (int) material Control -BWR (S-09)Piping Pressure Carbon .o Loss of O VII.G-22 3.3.1-14 D boundary steel Lube oil (int) material Oil analysis (AP-30)Pressure Carbon Steam > 220oF Loss of Flow VIII.C-5 3.4.1-29 A Piping boundary steel (int) material accelerated (S-15)VII.2-3.Ccorrosion Pressure Carbon Steam > 220'F Cracking -TLAA -metal V151.12- 3.4.1-1 C Piping boundary steel (int) fatigue fatigue (S-08)Water VIII.C-3 3.4.1-2 A Pressure Carbon Steam > 220'F Loss of Cher (S-34-Piping boundary steel (int) material Controly-BWR Pump Pressure Carbon Air- indoor Loss of System, VIII.H-7 3.4.1-28 A casing boundary steel (ext) material Walkdown (S-29)Pump Pressure Carbon Lube oil (int) Loss of Oil analysis VII.G-22 3.3.1-14 D casing boundary steel material (AP-30)Pump Pressure Carbon Treated water Cracking -One-time H casing boundary steel > 220°f (int) fatigue inspection Treated water Water VIII.D2- 3.4.1-4 A Pump Pressure Carbon Loss of Chmsr 7 casing boundary steel > 220 0 f (int) material Contro 7 Control -BWR (S-09)Strainer Pressure Carbon Air -indoor Loss of System VIII.H-7 3.4.1-28 A housing boundary steel (ext) material Walkdown (S-29)Strainer Pressure Carbon Treated water Cracking -One-time H housing boundary steel > 220'f (int) fatigue inspection Strainer Pressure Carbon Treated water Loss of Water VIII.D2- 3.4.1-4 A housing boundary steel > 2201f (int) material Chemistry 7 Control -BWR (S-09)Pressure Copper Loss of VII.G-22 3.3.1-14 D Tubing Peure alloy < Lube oil (int) Oil analysis (AP-30)T g boundary 15% Zn material Pressure Copper Treated water Loss of Water VII.E3- 3.3.1-17 C Tubing boundary alloy < > 2204f (int) Lossrofl Chemistry 18 15% Zn material Control -BWR (A-35)Pressure Stainless Air- indoor VII.J-15 3.3.1-94 A Tubing boundary steel (ext) None None (AP-1 7)Tubing Pressure Stainless Loss of VII.C1-8 3.3.1-26 D Tubing boundary steel Lube oil (int) material Oil analysis (AP-47)Tubing Pressure Stainless Treated water Cracking -TLAA -metal H boundary steel > 2701f (int) fatigue fatigue Pressure Stainless Treated water Loss of Water VIII.D2- 3.4.1-16 A Tubing boundary steel > 270°f (int) material chemistry 4 control -BWR (SP-16)Pressure Stainless Treated water Cracking Water VIll.A- 3.4.1-13 C Tubing boundary steel > 270°f (int) Chemistry 11 Control -BWR (SP-45)Valve Pressure Carbon Loss of VII.C1- 3.3.1-14 D body boundary steel Lube oil (int) material Oil analysis 17 (AP-30)Flow VIII.C-5 3.4.1-29 A Valve Pressure Carbon Steam > 220'F Loss of a le d (S-i4)body boundary steel (int) material corroio (S_15)corrosionI Page 43 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Valve Pressure Carbon Steam > 220'F Cracking -TLAA -metal VIII.B2- 3.4.1-1 A 5 body boundary steel (int) fatigue fatigue (508)Water VIII.C-3 3.4.1-2 A Valve Pressure Carbon Steam > 220'F Loss of Cher (5-04)body boundary steel (int) material Control -BWR (S0 LRA Section 3.3.2, Table 3.3.2-13-14, Fuel Oil (FO) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, is revised adding the following line items.NUREG Componen!

Intended Aging Effect Aging -1801 Table 1 N Typonent Fnctiond Material Environment Requiring Management Vo8.2 Tem Notes Type Function Mngmt Prras Vol.2 Item Management Programs Item Strainer Pressure Carbon Air -indoor Loss of System VIII.H-7 3.4.1-28 A housing boundary steel (ext) material Walkdown (S-29)Strainer Pressure Carbon Loss of Diesel fuel VI.H1- 3.3.1-200 housing boundary steel Fuel oil (int) material monitoring 10 housing boundar steel(A-30)

____Strainer Pressure Stainless Air- indoor VII.J-15 3.3.1-94 A housing boundary steel (ext) None None (AP-1 7)Strainer Pressure Stainless Loss of Diesel fuel VII.H1-6 3.3.1-32 E housing boundary steel Fuel oil (int) material monitoring (AP-54) I_ I Page 44 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2# LRA Section 3.3.2, Table 3.3.2-13-15, Fire Protection (FP) System, Nonsafety-Related Components Affecting Safety-Related Systems -Evaluation, is revised adding the following line items.Summary of Aging Management ltded Aging Effect Aging NUREG Componen netn Material Environment Requiring Management

-1801, Tem Notes Management Programs Item Orifice Pressure Carbon Air- indoor Loss of System VII.l-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Pressure Carbon Loss of Fire water VII.G-24 3.3.1-68 B Orifice boundary steel Raw water (int) material system (A-33)Strainer Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A housing boundary steel (ext) material Walkdown (S-29)Strainer Pressure Carbon Raw water (int) Loss of Fire Water VII.G-24 3.3.1-68 B housing boundary steel material System (A-33)Strainer Pressure Gray cast Air -indoor Loss of System VII.1-8 3.3.1-58 A housing boundary iron (ext) material Walkdown (A-77)Strainer Pressure Gray cast Raw water (int) Loss of Fire Water VII.G-24 3.3.1-68 B housing boundary iron material System (A-33)Strainer Pressure Gray cast Raw water (int) Loss of Selective VII.G-14 3.3.1-85 A housing boundary iron material leaching (A-51)Page 45 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 LRA Section 3.3.2, Table 3.3.2-13-18, House Heating Boiler (HB) System, Related Components Affecting Safety-Related Systems -Summary Management Evaluation, is revised adding the following line items.Nonsafety-of Aging Aging Effect Aging NUREG Corponen Intended Material Environment Requiring Management

-1801 Table 1 Notes Type Function Mngmt Prras Vol.2 Item Management Programs Item Heat Pressure Carbon Air -indoor Loss of System V1101- 33.1-59 C exchanger boundary steel (ext) material Walkdown (AP-41)(shell) ________Heat VI1.1-11 3.3.1-58 A exchanger Pressure Carbon Condensation Loss of System (A-81)eshellr boundary steel (ext) material walkdown Water VII.C2- 3.3.1-47 E, 305 Heat Pressure Carbon Steam> 2200 F Loss of chemistry 14 exchanger budr ste itmaral control -(A-25)(shell) boundary steel (int) material auxiliary systems Heat *H eat Pressure Carbon Steam> 220' F Cracking -One-time exchanger boundary steel (int) fatigue inspection (shell)Water VII.C2- 3.3.1-47 E, 305 Heat Pressure Carbon Treated water Loss of chemistry 14 exchanger Peure Carbo Trete water control -(A-25)(shell) boundary steel (int) material auxiliary systems Strainer Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A housing boundary steel (ext) material Walkdown (S-29)Strainer Pressure Carbon Condensation Loss of System VI1.1-11 3.3.1-58 A housing boundary steel (ext) material walkdown (A-81)Water VII.C2- 3.3.1-47 E, 305 Strainer Pressure Carbon Treated water Loss of chemistry 14 housing boundary steel (int) material control -(A-25)auxiliary systems Page 46 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-49, Heater Drain (HD) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.Componen Intended Aging Effect Aging NUREG Type Inten Material Environment Requiring Management

-1801, Table 1 Notes Type Function Mngmt Prras Vol.2 Item Management Programs Item Bolting Pressure Carbon Air -indoor Loss of System VIII.H-4 3.4.1-22 E I boundary steel (ext) material Walkdown (S-34)Pressure Stainless Air- indoor VIII.I-10 3.4.1-41 C Bolting boundary steel (ext) None None (SP-12)Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A Piping boundary steel (ext) material Walkdown (S-29)Water VIII.D2- 3.4.1-4 A Pressure Carbon Treated water Loss of Chemistry 7 Piping boundary steel (int) material Control -BWR (S-09)Pump Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A casing boundary steel (ext) material Walkdown (S-29)Water VIII.D2- 3.4.1-4 A Pump Pressure Carbon Treated water Loss of Chemistry 7 casing boundary steel (int) material Control -BWR (S-09)Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A boundary steel (ext) material Walkdown (S-29)Pressure Carbon Treated water Loss of Water Vmis2- 3.4.1-4 A Tank boundary steel (int) material Control -BWR (S-09)Pressure Copper Air -indoor VIII.1-2 3.4.1-41 A Tubing boundary alloy (ext) None None (SP-6)Tuin bunar <15% Zn Pressure Copper Treated water Loss of Water VIllA-5 3.4.1-15 C Tubing boundary alloy (int) material Chemistry (SP-61)S<15% Zn Control -BWR Valve Pressure Carbon Air -indoor Loss of System VIII.H-7 3.4.1-28 A body boundary steel (ext) material Walkdown (S-29)Water VIII.D2- 3.4.1-4 A Valve Pressure Carbon Treated water Loss of Watr 3 Chemistry 7 body boundary steel (int) material Control -BWR (S-09) _________Page 47 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2-LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-50, Heater Vents (HV)System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.Aging Effect Aging NUREG Component Intended Material Environment Requiring Management

-1801, Table 1 Notes Type Function Manvim tent Manams Vol.2 Item Management Programs Item Bolting Pressure Carbon Air- indoor Loss of System VIII.H-4 3.41-22 E boundary steel (ext) material Walkdown (S-34)Pressure Stainless Air -indoor VIII.1-10 3.4.1-41 C Bolting boundary steel (ext) None None (SP-12)Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A boundary steel (ext) material Walkdown (S-29)Water VIII.D2- 3.4.1-4 A Pressure Carbon Treated water Loss of Chemistry 7 Orifice boundary steel (int) material Control -BWR (S-09)Piping Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A boundary steel (ext) material Walkdown (S-29)Pressure Carbon Treated water Loss of Water VIII.D2- 3.4.1-4 A Piping boundary steel (int) material Chemistry 7_______Control

-BWR (S-09)Pressure Carbon Air -indoor Loss of System VIII.H-7 3.4.1-28 A boundary steel (ext) material Walkdown (S-29)Water VIII.D2- 3.4.1-4 A Pressure Carbon Treated water Loss of Chemistry 7 Tank boundary steel (int) material Control -BWR 7S-09_Pressure Copper Air -indoor VII1.I-2 3.4.1-41 A Tubing boundary alloy (ext) None None (SP-6)< 15% Zn Pressure Copper Treated water Loss of Water VIII.A-5 3.4.1-15 C aubnyboundary al5 (int) material Chemistry (SP-61)*y 15% Zn Control -BWR Valve Pressure Carbon Air -indoor Loss of System VIII.H-7 3.4.1-28 A body boundary steel (ext) material Walkdown (S-29)Valve Pressure Carbon Treated water Loss of Water VIII.D2- 3.4.1-4 A body boundary steel (int) material Chemistry 7_______ _________________________

__________Control BWR (S-09)Page 48 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 LRA Section 3.3.2, Table 3.3.2-13-21, Heating, Ventilation, and Air Conditioning (HVAC)System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, is revised adding the following line items.Aging Effect Aging NUREG Componen Intended material Environment Requiring Management

-1801, Table 1 Type Function Malagenent Programs Vol.2 Item Notes Management rItem Pressure Carbon Air- indoor Loss of System VII.l-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Pressure Carbon Air- indoor Loss of System V.B-1 3.2.1-32 E boundary steel (int) material Walkdown (E-25)Fan Pressure Carbon Air- indoor Loss of System VII.l-8 3.3.1-58 A housing boundary steel (ext) material Walkdown (A-77)Fan Pressure Carbon Air -indoor Loss of System V.B-1 3.2.1-32 E housing boundary steel (int) material Walkdown (E-25)Heat VI1.1-11 3.3.1-58 A Heat Pressure Carbon Condensation Loss of System (A-1)exchanger boundary steel (ext) material Walkdown (A-81)(shell) VII.C1- 3.3.-I6 Heat Pressure Carbon Loss of Service water VII- 3.3.1-76 D exchanger Raw water (int) 19 esxhang boundary steel material integrity Pump Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A casing boundary steel (ext) material Walkdown (A-77)VII.C1- 3.3.1-76 D Pump Pressure Carbon Raw water (int) Loss of Service water 19 casing boundary steel material integrity

_ (A-38)Strainer Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A housing boundary steel (ext) material Walkdown (A-77)VII.C1- 3.3.1-76 D Strainer Pressure Carbon Loss of Service water 19 housing boundary steel Raw water (int) material integrity (A-38)Page 49 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-51, Hydrogen Water Chemistry (HWC) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.Aging Effect Aging NUREG Componen Intended Material Environment Requiring Management

-1801, Table 1 Notes Type Function Programs Vol.2 Item Item Bolting Pressure Carbon Air- indoor Loss of System VII.1-4 3.3.1-43 E boundary steel (ext) material Walkdown (AP-27)Pressure Stainless Air- indoor VII.J-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-1 7)Piping Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Water VII.E3- 3.3.1-17 C Piping Pressure Carbon Treated water Loss of Chemistry 18 boundary steel (int) material Control -BWR (A-35)Pressure Copper Air -indoor V.F-3 3.2.1-53 C Tubingalloy Pr r None None (EP-10)Tuig boundary alloy< 15% Zn Pressure Copper Treated water Loss of Water VII.E3-9 3.3.1-31 C Tubingalloy (int) material Chemistry (AP-64)Tuig bony < 15% Zn Control -BWR Valve Pressure Carbon Air- indoor Loss of System VII.I-8 3.3.1-58 A body boundary steel (ext) material Walkdown (A-77)Water VIII.E- 3.4.1-4 A Valve Pressure Carbon Treated water Loss of Cher 33 body boundary steel (int) material Control -BWR (S-09)LRA Section 3.3.2, Table 3.3.2-13-22, Instrument Air (IA) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, is revised to delete the following line items.Page 50 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-52, Main Steam (MS) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.Aging Effect Aging NUREG Component Intended Agn fet Aig -1801, Table 1 Noe Typonent Fnctiond Material Environment Requiring Management Vol.2 Tem Notes Type Function Mngmt Prras Vol.2 Item Management Programs Item Pressure Carbon Air- indoor Loss of System VIII.H-4 3.4.1-22 E Rotting boundary steel (ext) material Walkdown (S-34)Pressure Stainless Air- indoor VIII.I-10 3.4.1-41 C Bolting boundary steel (ext) None None (SP-12)Heat VII.F1- 3.3.1-59 C exchanger Pressure Carbon Air -indoor Loss of System 10 (shell) boundary steel (ext) material Walkdown (AP-41)Heat Pressure Carbon Steam > 270'F Cracking -One-Time H exchanger boundary steel (int) fatigue Inspection (shell)Heat Pressure Carbon Steam > 270'F Loss of Water VIIE3- 3.3.1-17 C exchanger boundary steel (int) material Chemistry 18 (shell) boundary steel (int)_material Control -BWR (A-35)Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A boundary steel (ext) material Walkdown (S-29)Pressure Carbon Steam > 2701f Cracking -TLAA -metal VIII.52- 3.4.1-1 A Orifice boundary steel (int) fatigue fatigue (S0)Flow VIII.B2- 3.4.1-29 A Pressure Carbon Steam > 270'f Loss of ale d 4 boundary steel (int) material corroio (corrosion

_(S-15)Water VIII.B2- 3.4.1-37 A Pressure Carbon Steam > 270*f Loss of Chery 3 Orifice boundary steel (int) material Chemistry 3 Control -BWR (S-05)Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A Piping boundary steel (ext) material Walkdown (S-29)Pressure Carbon Steam > 270°f Cracking -TLAA -metal VIII.B2- 3.4.1-1 A Piping boundary steel (int) fatigue fatigue 5 (S-08)Flow VIII.B2- 3.4.1-29 A Pressure Carbon Steam > 270'f Loss of ale d 4 boundary steel (int) material corrosion (S-15)Pressure Carbon Steam > 270'F Loss of Water VIII.B2- 3.4.1-37 A Piping boundary steel (int) material Chemistry 3 Control -BWR (S-05)Water VIII.D2- 3.4.1-4 C Pressure Carbon Treated water Loss of Cher 7 Piping boundary steel (int) material Chemistry 7 Control -BWR (S-09)Strainer Pressure Carbon Air -indoor Loss of System VIII.H-7 3.4.1-28 A housing boundary steel (ext) material Walkdown (S-29)Strainer Pressure Carbon Treated water Loss of Water VIII.D2- 3.4.1-4 C housing boundary steel (int) material Chemistry 7 I__I__IControl

-BWR I(S-09)Pressure Copper Air- indoor V.F-3 3.2.1-53 C Tubingalloy (ext) None None (EP-10)< 15% Zn Page 51 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Pressure Copper Steam > 270'F Loss of Water VII.E3-9 3.3.1-31 C Tubing Peure alloy (int) material Chemistry (AP-64)boundary < 15% Zn Control -BWR Pressure Copper Treated water Loss of Water VII.E3-9 3.3.1-31 C alloyboundary

<1 (int) material Chemistry (AP-64)y < 15% Zn Control -BWR Pressure Stainless Air- indoor VIII.I-10 3.4.1-41 A Tubing boundary steel (ext) None None (SP-12)Pressure Stainless Steam > 270'F Cracking -TLAA -metal H Tubing boundary steel (int) fatigue fatigue Steam > 270'F Loss of Water VIII.B2- 3.4.1-37 A Tubing boundary steel (int) material chemistry 2 control -BWR (SP-46)Steam > 270*f Cracking Water VIII.B2- 3.4.1-13 A Tubing boundary steel (int) Chemistry 1 Control -BWR (SP-45)Valve Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A body boundary steel (ext) material Walkdown (S-29)Steam > 270°F VIII.B2- 3.4.1-1 A Valve Pressure Carbon (int) Cracking -TLAA -metal body boundary steel fatigue fatigue 5 (S-08)Flow VIII.B2- 3.4.1-29 A Valve Pressure Carbon Steam > 270'F Loss of a le d 4 body boundary steel (int) material corroio 4 corrosion (S-t15)Water VIII.B2- 3.4.1-37 A Valve Pressure Carbon Steam > 270'F Loss of Chery 3 body boundary steel (int) material Control -BWR (3-05)Contero VII.2 3.41- (S05 Valve Pressure Carbon Treated water Loss of Water V1I1.12- 3.4.1-4 C body boundary steel (int) material Chemistry 7 Control -BWR (S-09)Page 52 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 , LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-53, Make-up Demineralizer (MUD) System, Nonsafety-Related Components Affecting Safety-Related Summary of Aging Management Evaluation, as follows.Systems -Aging Effect Aging NUREG Component Intended Aging Magint -1801 Table 1 Notes Type Function Material Environment Requiring Management Vol.2 Item Management Programs Item Bolting Pressure Carbon Air -indoor. Loss of System VII.1-4 3.3.1-43 E boundary steel (ext) material Walkdown (AP-27)Bot Pressure Stainless Air -indoor VII.J-15 3.3.1-94 C oing boundary steel (ext) None None (AP-17)Filter Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A housing boundary steel (ext) material Walkdown (A-77)Filter Pressure Carbon Treated water Loss of Water VIIE3- 3.3.1-17 C steel (Int) material Chemistry 18 housing boundary Control -BWR (A-35)Piping Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Water VII.E3- 3.3.1-17 C Piping Pressure Carbon Treated water Loss of Chemistry 18 boundary steel (int) material Control -BWR (A-35)Pump Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A casing boundary steel (ext) material Walkdown (A-77)Pump Pressure Carbon Treated water Loss of Water VIrE3- 3.3.1-17 C casing boundary steel (int) material Chmtry 18 rControl -BWR (A-35)Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Water VII.E3- 3.3.1-17 C Tank Pressure Carbon Treated water Loss of Chemistry 18 boundary steel (int) material Control -BWR (A-35)Pressure Copper Air -indoor V.F-3 3.2.1-53 C boundary alloy < (ext) None None (EP-10)Tubin boudary 15% Zn Pressure Copper Treated water Loss of Water VII.E3-9 3.3.1-31 C Tubing Peureary alloy < (int) material Chemistry AP-64)Tubing5boundary 1 Zn Control -BWR Valve Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A body boundary steel (ext) material Walkdown (A-77)Valve Pressure Carbon Treated water Loss of Water VIIIE- 3.4.1-4 A body boundary steel (int) material Chemistry 33 Control -BWR (S-09)Page 53 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2-LRA Section 3.3.2, Table 3.3.2-13-29, Potable Water (PW) System, Nonsafety-Related Components Evaluation, is Affecting Safety-Related Systems -revised adding the following line items.Summary of Aging Management NUREG Component Intended Aging Effect Aging -1801 Table 1 N Type Function Material Environment Requiring Management Vol.2 Item Notes Management Programs Item Filter Pressure Carbon Air- indoor Loss of System VII.l-8 3.3.1-58 A housing boundary steel (ext) material Walkdown (A-77)Periodic VII.G-24 3.3.1-68 E Filter Pressure Carbon Untreated Loss of Surveillance (A-33)housing boundary steel water (int) material and Preventive Maintenance Strainer Pressure Carbon Air-indoor Loss of System VII.l-8 3.3.1-58 A housing boundary steel (ext) material Walkdown (A-77)Periodic VII.G-24 3.3.1-68 E Strainer Pressure Carbon Untreated Loss of Surveillance (A-33)housing boundary steel water (int) material and Preventive Maintenance Pressure Carbon Air- indoor Loss of System V11.1-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Periodic VII.G-24 3.3.1-68 E Pressure Carbon Untreated Loss of Surveillance (A-33)boundary steel water (int) material and Preventive Maintenance Valve Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A body boundary steel (ext) material Walkdown (A-77)Periodic VII.G-24 3.3.1-68 E Valve Pressure Carbon Untreated Loss of Surveillance (A-33)body boundary steel water (int) material and Preventive Maintenance Page 54 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2-LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-54, Service Air (SA) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.Aging Effect Aging NUREG Component Intended Aging Magint -1801 Table 1 Notes Type Function Material Environment Requiring Management Vol.2 Item Management Programs Item Bolting Pressure Carbon Air -indoor Loss of System VII.1-4 3.3.1-43 E boundary steel (ext) material Walkdown (AP-27)Pressure Stainless Air- indoor VII.J-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-17)Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A Piping boundary steel (ext) material Walkdown (A-77)Pressure Carbon Air -indoor Loss of System V.B-1 3.2.1-32 E Piping boundary steel (int) material Walkdown (E-25)Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Periodic VII.G-24 3.3.1-68 E Pressure Carbon Untreated Loss of Surveillance (A-33)boundary steel water (int) material and Preventive Maintenance Pressure Carbon Air-indoor Loss of System VII.l-8 3.3.1-58 A Trap boundary steel (ext) material Walkdown (A-77)Periodic VII.G-24 3.3.1-68 E Pressure Carbon Untreated Loss of Surveillance (A-33)Trap boundary steel water (int) material and Preventive Maintenance Valve Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A body boundary steel (ext) material Walkdown (A-77)Valve Pressure Carbon Air- indoor Loss of System V.B-1 3.2.1-32 E body boundary steel (int) material Walkdown (E-25)Periodic VII.G-24 3.3.1-68 E Valve Pressure Carbon Untreated Loss of Surveillance (A-33)body boundary steel water (int) material and Preventive Maintenance Page 55 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2-LRA Section 3.3.2, Table 3.3.2-13-39, Stator Cooling (SC) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, is revised adding the following line items.Aging Effect Aging NUREG Componen Intended Material Environment Requiring Management

-1801, Table 1 Notes Management Programs Vol.2 Item Item Pressure Carbon Air -indoor Loss of System VII.1-4 3.3.1-43 E Bolting boundary steel (ext) material Walkdown (AP-27)Pressure Stainless Air- indoor VII.J-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-1 7)Filter Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A housing boundary steel (ext) material Walkdown (A-77)Water VII.C2- 3.3.1-47 E Filter Pressure Carbon Treated water Loss of Chemistry 14 housing boundary steel (int) material Control -(A-25)Auxiliary Systems Heat Pressure Carbon Air -indoor Loss of System V1051- 3.3.1-59 C exchanger boundary steel (ext) material Walkdown 10 (shell) bonay(AP-41)____

Water VII.C2- 3.3.1-47 E Heat Pressure Carbon Treated water Loss of Chemistry 14 exchanger steel (int) material Control -(A-25)(shell) boundary Auxiliary Systems Pump Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A casing boundary steel (ext) material Walkdown (A-77)Water VII.C2- 3.3.1-47 E Pump Pressure Carbon Treated water Loss of Chemistry 14 steel (int) material Control -(A-25)casing boundary sAuxiliary Systems Strainer Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A housing boundary steel (ext) material Walkdown (A-77)Water VII.C2- 3.3.1-47 E Strainer Pressure Carbon Treated water Loss of Chemistry 14 housing boundary steel (int) material Control -(A-25)Auxiliary Systems Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Water Vll.C2- 3.3.1-47 E Pressure Carbon Treated water Loss of Chemistry 14 Tank boundary steel (int) material Control -(A-25)Auxiliary Systems Pressure Copper Air- indoor V.F-3 3.2.1-53 C Tubing alloy (ext) None None (EP-1 0)Tug boundary < 15% Zn Water VII.C2- 3.3.1-47 E Pressure Copper Treated water Loss of Chemistry 14 Tubing boundary alloy (int) material- (A-25)* 15% Zn Auxiliary Systems Page 56 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-55, Seal Oil (SO) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.Aging Effect Aging NUREG Component Intended Aging Magint -1801, Table 1 Notes Type Function Material Environment Requiring Management Vol.2 Item Management Programs Item Bolting Pressure Carbon Air- indoor Loss of System VII.1-4 3.3.1-43 E boundary steel (ext) material Walkdown (AP-27)Pressure Stainless Air- indoor VII.J-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-1 7)Filter Pressure Carbon Air- indoor Loss of System VII.l-8 3.3.1-58 A housing boundary steel (ext) material Walkdown (A-77)Filter Pressure Carbon Lube oil (int) Loss of VII.G-22 3.3.1-14 D housing boundary steel material Oil analysis (AP-30)Piping Pressure Carbon Air -indoor Loss of System VII.I-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Piping Pressure Carbon Loss of VIL.G-22 3.3.1-14 D boundary steel Lube oil (int) material Oil analysis (AP-30)Pump Pressure Carbon Air -indoor Loss of System VII.1-8 3.3.1-58 A casing boundary steel (ext) material Walkdown (A-77)Pump Pressure Carbon Lube oil (int) Loss of VII.G-22 3.3.1-14 D casing boundary steel material Oil analysis (AP-30)Sight Pressure Carbon Air -indoor Loss of System VII.1-8 3.3.1-58 A glass boundary steel (ext) material Walkdown (A-77)Sight Pressure Carbon Lube oil (int) Loss of Oil analysis VII.G-22 3.3.1-14 D glass boundary steel material (AP-30)Sight Pressure Glass Air- indoor None None VII.J-8 3.3.1-93 A glass boundary (ext) (AP-14)Sight Pressure VII.J-10 3.3.1-93 A glass boundary Glass Lube oil (int) None None (AP-15)Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Pressure Carbon .o Loss of O a VII.G-22 3.3.1-14 D Tank boundary steel Lube oil (int) material Oil analysis (AP-30)Pressure Copper Air-indoor V.F-3 3.2.1-53 C Tubing boundary alloy (ext) None None (EP-1 0)< 15% Zn Pressure Copper Loss of VII.G-22 3.3.1-14 D Tubing boundary alloy < Lube oil (int) material Oil analysis (AP-30)15% Zn Valve Pressure Carbon Air- indoor Loss of System VII.I-8 3.3.1-58 A body boundary steel (ext) material Walkdown (A-77)Valve Pressure Carbon Loss of VII.G-22 3.3.1-14 D body boundary steel Lube oil (int) material Oil analysis (AP-30)Page 57 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 LRA Section Components Evaluation, is 3.3.2, Table 3.3.2-13-41, Sampling Affecting Safety-Related Systems -revised adding the following line items.(SPL) System, Nonsafety-Related Summary of Aging Management NUREG Aging Effect Aging -1801 Table 1 N Componen Intended Material Environment Requiring Management Vol.2' Item Notes Type Function Management Programs Item Strainer Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A housing boundary steel (ext) material Walkdown (S-29)Strainer Pressure Carbon Treated water Loss of Water V1IIE- 3.4.1-4 A housing boundary steel (int) material Chemistry 33 housing_ bControl -BWR (S-09)Strainer Pressure Stainless Air- indoor VII.J-15 3.3.1-94 A housing boundary steel (ext) None None (AP-17)Strainer Pressure Stainless Treated water Loss of Water VIIIE- 3.4.1-4 A housing boundary steel (int) material Chemistry 33 Control -BWR (S-09)> LRA Section 3.3.2, Table 3.3.2-13-42, Service Water (SW) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, is revised adding the following line items.Aging Effect Aging NUREG Componen Intended Material Environment Requiring Management

-1801, Table 1 Notes Management Programs Item Heat Pressure Carbon Air -indoor Loss of System V1I51- 3.3.1-59 C exchanger boundary steel (ext) material Walkdown (AP-41)(shell) ___________________

Heat Pressure Carbon Condensation Loss of System VI1.1-11 3.3.1-58 A exchanger boundary steel (ext) material walkdown (A-81)(shell)_____

___Heat VI1.C1-5 3.3.1-77 B exchanger essure Carbon t) Loss of Service water (A-64)(shell) boundary steel material integrity Heat VII.J-15 3.3.1-94 A Hexanger Pressure Stainless Air -indoor None None.3A1-947) exchanger bonay sel(x)None None (AP-17)(shell) boundary steel (ext)Heat Vll.F1-1 3.3.1-27 E Hean Pressure Stainless Condensation Loss of System (A-09)exchanger boundary steel (ext) material walkdown (A09)(shell)Heat Pressure Stainless Loss of Service water VIICi- 3.3.1-79 D exchanger stail Raw water (int) material integrity 15 (shell) (A-54)Pump Pressure Carbon Condensation Loss of System VII.l-1 1 3.3.1-58 A casing boundary steel (ext) material walkdown (A-81)Pump Pressure Stainless Air -indoor None None VII.J-15 3.3.1-94 A casing boundary steel (ext) (AP-17)Pump Pressure Stainless Condensation Loss of System VII.F1-1 3.3.1-27 E casing boundary steel (ext) material walkdown (A-09)VII.C1- 3.3.1-79 D Pump Pressure Stainless Raw water (int) matria i negrvicty casing boundary steel Raw water___material integrity (A-54)Page 58 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-56, Turbine Building Closed Cooling Water (TBCCW) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.Aging Effect Aging NUREG Componen Intended Material Environment Requiring Management

-1801, Table 1 Notes Management Programs Item Pressure Carbon Air -indoor Loss of System VII.1-4 3.3.1-43 E Bolting boundary steel (ext) material Walkdown (AP-27)Pressure Stainless Air- indoor VII.J-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-1 7)Heat Pressure Carbon Air -indoor Loss of System VF10- 3.3.1-59 C exchanger boundary steel (ext) material Walkdown (AP-41)(shell) ________________

_____Water VII.C2- 3.3.1-47 B Heat Pressure Carbon Treated water Loss of Chemistry 14 exchanger Peure Carbo Trete water Control -(A-25)(shell) boundary .steel (int) material Closed Cooling Water Pressure Carbon Air -indoor Loss of System VII.I-8 3.3.1-58 A Piping boundary steel (ext) material Walkdown (A-77)Water VII.C2- 3.3.1-47 B Pressure Carbon Treated water Loss of Chemistry 14 Piping boundary steel (int) material Control -(A-25)Closed Cooling Water Pump Pressure Carbon Air- indoor Loss of System VII.I-8 3.3.1-58 A casing boundary steel (ext) material Walkdown (A-77)Water VII.C2- 3.3.1-47 B Pump Pressure Carbon Treated water Loss of Chemistry 14 casing boundary steel (int) material Control -(A-25)Closed Cooling Water Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Water VII.C2- 3.3.1-47 B Pressure Carbon Treated water Loss of Chemistry 14 Tank boundary steel (int) material Control -(A-25)Closed Cooling Water Pressure Copper Air -indoor V.F-3 3.2.1-53 C Tubing boundary alloy (ext) None None (EP-10)< 15% Zn Water VII.C2- 3.3.1-47 B Pressure Copper Treated water Loss of Chemistry 14 Tubing boundary alloy (int) material Control -(A-25)< 15% Zn Closed Cooling Water Valve Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A body boundary steel (ext) material Walkdown (A-77)Water VII.C2- 3.3.1-47 B Valve Pressure Carbon Treated water Loss of Chemistry 14 body boundary steel (int) material Control -(A-25)Closed Cooling Water Page 59 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-57, Main Turbine Generator (TG) System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.Aging Effect Aging NUREG Componen Intended Material Environment Requiring Management

-1801, Table 1 Notes Management Programs Item Pressure Carbon Air -indoor Loss of System VII.1-4 3.3.1-43 E Bolting boundary steel (ext) material Walkdown (AP-27)Pressure Stainless Air- indoor VII.J-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-17)Filter Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A housing boundary steel (ext) material Walkdown (A-77)Steam > 270'f Cracking -TLAA -metal VIII.B2- 3.4.1-1 C Filter Pressure Carbon(ntfaiuftge 5 housing boundary steel (int) fatigue fatigue 5 (S-08)Filter Pressure Carbon Steam > 270'f Loss of Water VllA- 3.4.1-2 C housing boundary steel (int) material Chemistry 15 Control -BWR (S-04)Piping Pressure Carbon Air -indoor Loss of System VII.I-8 3.3.1-58 A boundary steel (ext) material Walkdown (A-77)Pressure Carbon Steam > 270'f Cracking -TLAA -metal VIII.B2- 3.4.1-1 C Piping boundary steel (int) fatigue fatigue 5 (S-08)Pressure Carbon Steam> 270'f Loss of Flow VIII.A- 3.4.1-29 C Piping boundary steel (int) material Accelerated 17 Corrosion (S-15)Loss of Water VIII.A- 3.4.1-2 C Piping boundary steel (int) material Chemistry 15 Control -BWR (S-04)Pump Pressure Carbon Air -indoor Loss of System VII.1-8 3.3.1-58 A casing boundary steel (ext) material Walkdown (A-77)Pump Pressure Carbon Treated water Cracking -One-time H casing boundary steel > 270'f (int) fatigue inspection Pump Pressure Carbon Treated water Loss of Water VII.E3- 3.3.1-17 C casing boundary steel > 270'f (int) material Chemistry 18 Control -BWR (A-35)Turbine Pressure Carbon Air -indoor Loss of System VII.I-8 3.3.1-58 A casing boundary steel (ext) material Walkdown (A-77)Turbine Pressure Carbon Steam > 270'f Cracking -One-time H casing boundary steel (int) fatigue inspection Turbine Pressure Carbon Steam > 270'f Loss of Water VII.E3- 3.3.1-17 C casing boundary steel (int) material Chemistry 18 Control -BWR (A-35)Treated water Water VII.E3- 3.3.1-17 C Turbine Pressure Carbon Tr nte Loss of Cher 18 casing boundary steel (int) material Chemistry 18 Control -BWR (A-35)Pressure Copper Air -indoor V.F-3 3.2.1-53 C ssure alloy (ext) None None (EP-1 0)Tubing boundary < 15% Zn Pressure Copper Steam > 270'f Loss of Water VII.E3-9 3.3.1-31 C Tubing boundary alloy (int) material Chemistry (AP-64)< 15% Zn Control -BWR Page 60 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2 Pressure Copper Treated water Loss of Water VII.E3-9 3.3.1-31 C Tubing alloy (int) material Chemistry (AP-64)y < 15% Zn Control -BWR Valve Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A body boundary steel (ext) material Walkdown (A-77)Valve Pressure Carbon Steam > 270'f Cracking -TLAA -metal VIII.B2- 3.4.1-1 C body boundary steel (int) fatigue fatigue 5 (S-08)Steam > 270'f Flow VIII.A- 3.4.1-29 C Valve Pressure Carbon Loss of body boundary steel (int) material accelerated 17 corrosion (S-15)Steam > 270°f Water VIII.A- 3.4.1-2 C Valve Pressure Carbon (n)Loss of Chemistry 15 body boundary steel (int) material Control -BWR (S-04)Water VIII.E- 3.4.1-4 A Valve Pressure Carbon Treated water Loss of Cher 33 body boundary steel (int) material Control -BWR (S-09)Page 61 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section 3.3.2 is revised to add a new Table 3.3.2-13-58, Turbine Lube Oil (TLO)System, Nonsafety-Related Components Affecting Safety-Related Systems -Summary of Aging Management Evaluation, as follows.NUREG Component Intended Material Environment Aging Efc Aging -1801, Table 1 Notes Type Function Malagenent Manams Vol.2 Item Management Programs Item Pressure Carbon Air -indoor Loss of System VII.l-4 3.3.1-43 E Bolting boundary steel (ext) material Walkdown (AP-27)Pressure Stainless Air- indoor VII.J-15 3.3.1-94 C Bolting boundary steel (ext) None None (AP-17)Filter Pressure Carbon Air- indoor Loss of System VII.l-8 3.3.1-58 A housing boundary steel (ext) material Walkdown (A-77)Filter Pressure Carbon Loss of VII.G-22 3.3.1-14 D housing boundary steel Lube oil (int) material Oil analysis (AP-30)Heat Pressure Carbon Air -indoor Loss of System VF10 -3.3.1-59 C exchanger boundary steel (ext) material Walkdown (AP-41)(shell) VI.-2 .-Heat Pressure Carbon Loss of VII.G-22 3.3.1-14 D exchanger Lube oil (int) material Oil analysis (AP-30)(shell) boundary steel Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A Piping boundary steel (ext) material Walkdown (A-77)Pressure Carbon Loss of VII.G-22 3.3.1-14 D Piping boundary steel Lube oil (int) material Oil analysis (AP-30)Pump Pressure Carbon Air- indoor Loss of System VII.1-8 3.3.1-58 A casing boundary steel (ext) material Walkdown (A-77)Pump Pressure Carbon Lube oil (int) Loss of Oil analysis VII.G-22 3.3.1-14 D casing boundary steel material (AP-30)Strainer Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A housing boundary steel (ext) material Walkdown (S-29)Strainer Pressure Carbon Lube oil (int) Loss of VII.G-22 3.3.1-14 D housing boundary steel material Oil analysis (AP-30)Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A boundary steel (ext) material Walkdown (S-29)Pressure Carbon Loss of VII.G-22 3.3.1-14 D Tank boundary steel Lube oil (int) material Oil analysis (AP-30)Pressure Copper Air- indoor V.F-3 3.2.1-53 C Tubing boundary alloy (ext) None None (EP-10)< 15% Zn I Pressure Copper Loss of VII.G-22 3.3.1-14 D Tubing boundary alloy < Lube oil (int) material Oil analysis (AP-30)15% Zn Valve Pressure Carbon Air- indoor Loss of System VIII.H-7 3.4.1-28 A body boundary steel (ext) material Walkdown (S-29)Valve Pressure Carbon Lube oil (int) Loss of VII.G-22 3.3.1-14 D body boundary steel I L material Oil analysis (AP-30)Page 62 of 63 BVY 07-054 Docket 50-271 VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SUPPLEMENT ATTACHMENT 2> LRA Section B.1.21 is revised to add the following systems to the list of nonsafety-related systems affecting safety-related components managed by the One-Time Inspection Program.o Auxiliary Steam (AS)o Condensate (C)o Feedwater (FDW)o House Heating Boiler (HB)o Main Steam (MS)o Main Turbine Generator (TG)> LRA Section B.1.22 is revised to add the following systems to the list of nonsafety-related systems affecting safety-related components managed by the Periodic Surveillance and Preventive Maintenance Program.o Buildings (drainage system components) (BLD)o Circulating Water Priming (CWP)o Service Air (SA)Page 63 of 63 BVY 07-054 Docket 50-271

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