ML13311A054

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Nine Mile Point, Unit 2 - Pressure and Temperature Limits Report (PTLR) PTLR-2, Revision 0 (Draft B)
ML13311A054
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Site: Nine Mile Point Constellation icon.png
Issue date: 11/04/2013
From: Inch G B
Constellation Energy Nuclear Group, Nine Mile Point
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Office of Nuclear Reactor Regulation
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TAC MF0345 PTLR-2, Rev 0
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ATTACHMENT 2NINE MILE POINT UNIT 2PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) -REVISION 0 (DRAFT B)Nine Mile Point Nuclear Station, LLCNovember 4, 2013 CENGSMa joint venture ofConstellation neg"'eDFOEnerWy 10DFNINE MILE POINTNUCLEAR STATIONNine Mile Point Nuclear StationNine Mile Point Unit 2Pressure and Temperature Limits Report (PTLR)PTLR-2, Revision 0 (Draft B)Prepared by: Date:G. B. InchMechanical Design EngineeringReviewed by: Date:S. K. DharMechanical Design EngineeringApproved by: Date:P. E. Bartolini, SupervisorMechanical-Structural Design EngineeringApproved by: Date:M. N. Khan, General SupervisorDesign EngineeringThis Controlled Document provides reactor pressure vessel pressure and temperature limitsfor use in conjunction with the Nine Mile Point Unit 2 Technical Specifications. Documentpages may only be changed through the re-issue of a revision to the entire document.

NMP2 Pressure and Temperature Limits ReportTable of ContentsSection1.0 Purpose2.0 Applicability3.0 Methodology4.0 Operating Limits5.0 Discussion6.0 ReferencesFigure 1 Bottom Head and Composite P-T Curves for PressureTest [Curve A] for up to 32 EFPYFigure 2 Bottom Head and Composite P-T Curves for Core NotCritical [Curve B] for up to 32 EFPYFigure 3 Composite P-T Curves for Core Critical [Curve C] for upto 32 EFPYTable 1 Data Table for Composite P-T Curve for 32 EFPYppendix A Reactor Vessel Material Surveillance Programppendix B Supporting Informationppendix C ChecklistPage11123678910151625AAAiPTLR-2Revision 0 NMP2 Pressure and Temperature Limits Report1.0 PurposeThe purpose of the Nine Mile Point Nuclear Station Unit 2 (NMP2) Pressure andTemperature Limits Report (PTLR) is to present operating limits relating to:1. Reactor Coolant System (RCS) Pressure versus Temperature limits duringHeatup, Cooldown and Hydrostatic/Class 1 Leak Testing;2. RCS Heatup and Cooldown rates;3. Reactor Pressure Vessel (RPV) to RCS coolant AT requirements duringRecirculation Pump startups;4. RPV bottom head coolant temperature to RPV coolant temperature ATrequirements during Recirculation Pump startups;5. RPV head flange bolt-up temperature limits.This report has been prepared in accordance with the requirements of TechnicalSpecification (TS) 5.6.7, "Reactor Coolant System (RCS) PRESSURE ANDTEMPERATURE LIMITS REPORT (PTLR)."2.0 ApplicabilityThis report is applicable to the NMP2 RPV for up to the 32 Effective Full Power Years(EFPY).The following TS are affected by the information contained in this report:TS 3.4.11 RCS Pressure and Temperature (P/T) Limits;3.0 MethodologyThe limits in this report were derived from the NRC-approved methods listed in TS 5.6.7,using the specific revisions listed below:1. The appendix B Adjusted Reference Temperature (ART) is defined based onconservative extrapolation for up to 32 EFPY. The Neutron fluence used for theART was verified conservative per the NMP2 plant specific Reg. Guide 1.190methods documented in Reference 6.2, approved in reference 6.3. and 6.10.2. The pressure and temperature limits were calculated per GEH P-T Curve LicensingTopical Report, NEDC-33178P-A, Revision 1, "GE Hitachi Nuclear EnergyMethodology for Development of Reactor Pressure Vessel Pressure-TemperaturePage 1 of 27 PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportCurves," Report for BWR Owners' Group, Sunol, California, (GEH Proprietary),June 2009, approved in Reference 6.5.3. This revision of the pressure and temperature limits is to incorporate the followingchanges:Changes to the curves, limits, or parameters within this PTLR, based upon newirradiation fluence data of the Reactor Pressure Vessel (RPV), or other plant designassumptions in the Updated Final Safety Analysis Report (UFSAR), can be madepursuant to 10 CFR 50.59, provided the above methodologies are utilized. Therevised PTLR shall be submitted to the NRC upon issuance, in accordance with TSSection 5.6.7.Changes to the curves, limits, or parameters within this PTLR, based upon newsurveillance capsule data of the RPV, cannot be made without prior NRC approval.Such analysis and revisions shall be submitted to the NRC for review prior toincorporation into the PTLR. Since NMP2 surveillance capsule program is the ISPprogram, new surveillance data through the Integrated Surveillance Program (ISP)does not represent new data that requires NRC review prior to incorporation into thePTLR.4.0 Operating LimitsThe pressure-temperature (P-T) curves included in this report represent steam domepressure versus minimum vessel metal temperature and incorporate the appropriatenon-beltline limits and irradiation embrittlement effects in the beltline region.Complete P-T curves were developed for the estimated fluence based on 32 EFPYassuming 3988 MWth rating. A tabulation of the P-T curves is also included in Table 1.The previous evaluation for Pressure-Temperature limits for up to 22 EFPY is containedin Reference 6.6.The operating limits for pressure and temperature are required for three categories ofoperation: (a) hydrostatic pressure tests and leak tests, referred to as Curve A; (b) non-nuclear heatup/cooldown (core not critical), referred to as Curve B; and (c) core criticaloperation, referred to as Curve C.Heatup and Cooldown rate limit during Hydrostatic and Class 1 Leak Testing (Figure 1):Curve A): < 20 OF/hour.Page 2 of 27 PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportNormal Operating Heatup and Cooldown rate limit (Figures 2 and 3): Curve B -Non-Nuclear Heating and Curve C -Nuclear Heating): < 100 °F/hour.RPV bottom head coolant temperature to RPV coolant temperature AT limit duringRecirculation Pump startup: < 145 OF.Recirculation loop coolant temperature to RPV coolant temperature AT limit duringRecirculation Pump startup: < 50 OF.RPV flange and adjacent shell temperature limit: _> 70 OF.5.0 DiscussionNo new computer codes have been used in the development of Pressure-Temperaturecurves.The method for determining the initial RTNDT for all vessel materials is that defined inSection 4.1.2 of NEDC-33178P-A, Revision 1, approved for use in Reference 6.5. InitialRTNDT values for all vessel materials considered are presented in tables in this PTLR.Surveillance capsule material data to represent the NMP2 vessel is available from theIntegrated Surveillance Program (ISP). Since NMP2 is not a host plant in the ISPprogram, the ISP program representative materials are evaluated to confirm applicabilityof RG 1.99 position 1.1. The ISP data review is shown in Appendix B. The NMP2representative plate is not the same as the target plate material and is thereforeprovided for information only and is not considered in development of the PT curves.The NMP2 representative weld is not the same as the target weld material. However, asthe same heat is used in beltline axial welds, the ISP weld material is considered in thedevelopment of the PT curves. This material is not the limiting material with respect tothe PT curves; the NMP2 plant-specific plate heat C3147-1, has the limiting ART.For NMP2, there are three thickness discontinuities in the vessel. One discontinuity isbetween the bottom head torus and dollar plate. One discontinuity is between thebottom head torus and Shell #1. One discontinuity is between the transition in the upperShell (Shell #3 to Shell #4). The thickness discontinuities do not cause a change in theRTNDT.The adjusted reference temperature (ART) of the limiting beltline material is used toadjust the beltline P-T curves to account for irradiation effects. Regulatory Guide 1.99,Revision 2 (RG 1.99) provides the methods for determining the ART. The RG 1.99Page 3 of 27 PTLR-2Revision 0 NMP2 Pressure and Temperature Limits Reportmethods for determining the limiting material and adjusting the P-T curves using ARTare discussed in this section.The vessel beltline copper and nickel values (except for the N6 and N12 nozzles) wereobtained from Reference 6.6 PT curve limits report. Chemistries for the surveillancematerials evaluated in Appendix B of this report were obtained from the ISP. The LPCI(N6) Nozzle and the Water Level Instrumentation (N12) Nozzle are now included in theextended beltline region. For the N6 nozzle forging, CMTR's were located whichcontained Cu (0.07%) and Ni (0.86%) values. For the N6 nozzle welds, CMTRs werelocated that contained Cu and Ni values as shown in the ART table.For the Water Level Instrumentation (N12) Nozzle, the CMTR's do not contain the Cuand Ni content. Since plant-specific information regarding the Cu and Ni content for thismaterial is not available, the evaluation was performed based on a bounding estimate forforgings fabricated from SA508 Class 1 material. This was defined based on a search ofavailable BWR vessel purchase records for SA508 Class 1 materials. Representativevalues for Cu and Ni content were developed using Mean + 1 sigma.The P-T curves for the non-beltline region were conservatively developed for a Boiling-Water Reactor Product Line 6 (BWR/6) with nominal inside diameter of 251 inches. Theanalysis is considered appropriate for NMP2, since the plant specific geometric valuesare bounded by the generic analysis for a large BWRJ6. The generic value was adaptedto the conditions at NMP2 using plant-specific RTNDT values for the reactor pressurevessel. The value of R/t112 for NMP2 = 126.6875 / (7.19)1/2 = 47.3 inch112.The peak RPV ID fluence used in the P-T curve evaluation for 32 EFPY is calculatedusing methods that comply with the guidelines of RG 1.190, (References 6.2, 6.3 and6.4). Appendix B lists the peak fluence levels used for the PT curves.The P-T curves for the heatup and cooldown operating conditions at a given EFPY applyfor both the 1/4T and 3/4T locations. When combining pressure and thermal stresses, itis usually necessary to evaluate stresses at the 1/4T location (inside surface flaw) andthe 3/4T location (outside surface flaw). This is because the thermal gradient tensilestress of interest is in the inner wall during cooldown and the outer wall during heatup.However, as a conservative simplification, the thermal gradient stress at the 1/4Tlocation is assumed to be tensile for both heatup and cooldown. This results in theapproach of applying the maximum tensile stress at the 1/4T location. This approach isconservative because irradiation effects cause the allowable toughness, Kir, at 1/4T tobe less than that at 3/4T for a given metal temperature. This approach causes noPage 4 of 27 PTLR-2Revision 0 NMP2 Pressure and Temperature Limits Reportoperational difficulties, since the BWR is at steam saturation conditions during normaloperation, well above the heatup/cooldown curve limits.For the core not critical curve (Curve B) and the core critical curve (Curve C), the P-Tcurves specify a coolant heatup and cooldown temperature rate of _< 1OO0F/hr for whichthe curves are applicable. However, the core not critical and the core critical curveswere also developed to bound transients defined on the RPV thermal cycle diagram andthe nozzle thermal cycle diagrams. For the hydrostatic pressure and leak test curve(Curve A), a coolant heatup and cooldown temperature rate of _< 20°F/hr must bemaintained. The P/T limits and corresponding heatup/cooldown rates of either Curve Aor B may be applied while achieving or recovering from test conditions. Curve A appliesduring pressure testing and when the limits of Curve B cannot be maintained.For NMP2, the plate heat C3147-1 is the limiting material for the beltline region. Peakfluence values used in the development of the Pressure-Temperature curves areidentified in Appendix B. The limiting ART for the beltline LPCI N6 and Water LevelInstrumentation N12 nozzle forgings and welds are also considered in the developmentof the beltline PT curves.In order to ensure that the limiting vessel discontinuity has been considered in thedevelopment of the P-T curves, the methods in Sections 4.3.2.1 and 4.3.2.2 of NEDC-33178P-A, Revision 1, approved for use in Reference 6.5, for the non-beltline andbeltline regions, respectively, are applied.Page 5 of 27 PTLR-2Revision 0 NMP2 Pressure and Temperature Limits Report6.0 References6.1 GEH Report NEDC-33414P, Revision 1, "Pressure-Temperature Curves forConstellation Generation Group Nine Mile Point Nuclear Station Unit 2", October20126.2 Benchmarking of Nine Mile Point Unit 1 and Unit 2 Neutron Transport Calculations,MPM-402781 Revision 1, September 2003.6.3 NRC Letter to NMPNS dated October 27, 2003, "Nine Mile Point Nuclear Station,Unit No. 1 -Issuance of Amendment Re: Pressure-Temperature Limit Curves andTables (TAC No. MB6687)."6.4 Fluence Extrapolation in Support of NMP2 P-T Curve Update, MPM-913991,September, 20136.5 Letter from T. R. Bount, USNRC to D. Coleman, BWROG, "Final Safety Evaluationfor Boiling Water Reactors Owners' Group Licensing Topical Report NEDC-33178P, General Electric Methodology for Development of Reactor PressureVessel Pressure-Temperature Curves (TAC No. MD2693)," April 27, 20096.6 Pressure-Temperature Operating Curves for Nine Mile Point Unit 2, MPM-502840,dated July 2003.6.7 "BWRVIP-135, Revision 2: BWR Vessel and Internals Project IntegratedSurveillance Program (ISP) Data Source Book and Plant Evaluations", 1020231,EPRI, Palo Alto, CA, October 2009 (EPRI Proprietary Information)6.8 Letter from P. S. Tam (NRC) to J. A. Spina (NMPNS), dated November 8, 2004,"Nine Mile Point Nuclear Station Unit Nos. 1 and 2 -Issuance of Amendments Re:Implementation of the Reactor Pressure Vessel Integrated Surveillance Program(TAC Nos. MC1758 and MC1759)"6.9 Nine Mile Point Unit 2 3-Degree Surveillance Capsule Report, MPM-1200676,December, 2000.6.10 NRC Letter to NMPNS dated November 8, 2004 -Issuance of Amendments RE:Implementation of the Reactor Pressure Vessel Integrated Surveillance Program(TAC Nos. MC1 758 and MC1759)Page 6 of 27 PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportFigure 1 -Bottom Head and Composite P-T Curves for Pressure Test [Curve A] for up to 32 EFPY,aZ~0U)0)0I-wZwLU140013001200110010009008007006005004003002001000INITIAL RTndt VALUESARE0°F FOR BELTLINE,5°F FOR UPPERVESSEL,AND10°F FOR BOTTOM HEADBELTLINE CURVESADJUSTED AS SHOWN:EFPY SHIFT (°F)32 51HEATUP/COOLDOWNRATE OF COOLANT< 20°F/HR0 25 50 75 100 125 150 175 200MINIMUM REACTOR VESSEL METAL TEMPERATURE (-F)Page 7 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportFigure 2 -Bottom Head and Composite P-T Curves for Core Not Critical [Curve B]for up to 32 EFPY14001300120011000,.1000* 9000~I-w 800U)U)W 7000I--"W 600zI-a 500: 400c( 3oU)300HEATUPICOOLDOWNRATE OF COOLANT< 100°F/HR200100-UPPER VESSELAND BELTLINELIMITS00 25 50 75 100 125 150 175 200MINIMUM REACTOR VESSEL METAL TEMPERATURE (°F)Page 8 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportFigure 3 -Composite P-T Curves for Core Critical [Curve C] for up to 32 EFPYcn00U.1"I-wZ_.1I-JC-)I-wC,,uJ,nw0Z140013001200110010009008007006005004003002001000BELTLINE CURVEADJUSTED AS SHOWN:EFPY SHIFT (-F)32 51INITIAL RTndt VALUESARE0°F FOR BELTLINE,5°F FOR UPPERVESSEL,AND24.6°F FOR BOTTOMHEADHEATUP/COOLDOWNRATE OF COOLANT< 100°F/HRL.Minimum CriticalityTemperature 70'F-BELTLINE AND NON-BELTLINE LIMITS0 25 50 75 100 125 150 175 200 225 250MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)Page 9 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportTable 1 -NMP2 Tabulation of Composite P-T Curves for 32 EFPY -Required Metal Temperature with Required Coolant Temperature Rateat 100 °F/hr for Curves B & C and 20 °F/hr for Curve Afor Figures 1, 2 & 3BOTTOM UPPER RPV &BOTTOM UPPER RPV &PRESSURE(PSIG)0102030405o607080901001101201301401SO16017018019020021022023024025O260270280290HEADCURVE A(°F)68.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.0BELTLINECURVE A('F)70.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.0HEADCURVE B(°F)68.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.0BELTLINECURVE B(*F)70.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.070.071.372.8LIMITINGCURVE C(*F)70.070.070.070.070.070.070.070.070.070.070.071.975.779.282.485.287.990.592.995.297.399.3101.3103.1104.9106.6108.2109.8111.3112.8Page 10 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportTable 1 -NMP2 Tabulation of Composite P-T Curves for 32 EFPY -Required Metal Temperature with Required Coolant Temperature Rateat 100 °F/hr for Curves B & C and 20 °F/hr for Curve Afor Figures 1, 2 & 3BO'TOMHEADPRESSURE(PSIG)300310312.5312.5320330340350360370380390400410420430440450460470480490500510520530540550560570CURVE A(°F)68.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.0UPPER RPV &BELTLINECURVE A(*F)70.070.070.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0BOTTOMHEADCURVE B(°F)68.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.0UPPER RPV &BELTILINECURVE B(°F)74.275.575.9130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0LIMITINGCURVE C(°F)114.2115.5115.9170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0.170.0Page 11 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportTable 1 -NMP2 Tabulation of Composite P-T Curves for 32 EFPY -Required Metal Temperature with Required Coolant Temperature Rateat 100 *F/hr for Curves B & C and 20 °F/hr for Curve Afor Figures 1, 2 & 3BOTTOMHEADPRESSURE(PSIG)580590600610620630640650660670680690700710720730740750760770780790800810820830840850860870CURVE A('F)68.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.0UPPER RPV &BELTLINECURVE A(*F)100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0BOlTOMHEADCURVE B(°F)68.068.068.068.068.068.068.068.068.068.068.769.971.072.273.374.475.576.677.678.679.680.681.582.583.484.385.286.086.987.7UPPER RPV &BELTLINECURVE B('F)130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0LIMITINGCURVE C('F)170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0Page 12 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportTable 1 -NMP2 Tabulation of Composite P-T Curves for 32 EFPY -Required Metal Temperature with Required Coolant Temperature Rateat 100 °F/hr for Curves B & C and 20 °F/hr for Curve Afor Figures 1, 2 & 3BOTTOMHEADPRESSURE(PSIG)880890900910920930940950960970980990100010101020103010351040105010551060107010801090110011051110112011301140CURVE A(7F)68.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.068.669.269.669.970.671.271.9UPPER RPV &BELTLINECURVE A(°F)100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0100.0BOTTOMHEADCURVE B(*F)88.689.490.291.091.792.593.394.094.795.596.296.997.698.298.999.699.9100.2100.9101.2101.5102.1102.8103.4104.0104.3104.6105.2105.8106.3UPPER RPV &BELTILINECURVE B(°F)130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0LIMITINGCURVE C(°F)170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0Page 13 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportTable 1 -NMP2 Tabulation of Composite P-T Curves for 32 EFPY -Required Metal Temperature with Required Coolant Temperature Rateat 100 °F/hr for Curves B & C and 20 °F/hr for Curve Afor Figures 1, 2 & 3BOTTOM UPPER RPV &PRESSURE(PSIG)11501160117011801190120012101220123012401250126012701280129013001310132013301340135013601370138013901400HEADCURVE A(*F)72.573.173.874.475.075.676.276.877.377.978.579.079.680.180.781.281.782.382.883.383.884.384.885.385.886.3BELTLINECURVE A(*F)100.0100.0100.0100.0100.0100.4101.0101.7102.3102.9103.5104.1104.7105.2105.8106.4106.9107.5108.0108.6109.1109.7110.2110.7111.2111.7BOTTOMHEADCURVE B(*F)106.9107.5108.0108.6109.1109.7110.2110.8111.3111.8112.3112.8113.3113.8114.3114.8115.3115.8116.2116.7117.2117.6118.1118.5119.0119.4UPPER RPV &BELTLINECURVE B('F)130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.0130.3130.6130.8131.1131.4131.8132.2132.7133.1133.5134.0134.4134.8135.2135.7LIMITINGCURVE C(*F)170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.0170.3170.6170.8171.1171.4171.8172.2172.7173.1173.5174.0174.4174.8175.2175.7Page 14 of 27 PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportAppendix AReactor Vessel Material Surveillance ProgramIn accordance with 10 CFR 50, Appendix H, Reactor Vessel Material Surveillance ProgramRequirements, the first surveillance capsule was removed from the NMP2 reactor vessel afterCycle 7, in March 2000, and tested. The surveillance capsule contained flux wires for neutronfluence measurement, Charpy V-Notch impact test specimens and uniaxial tensile testspecimens fabricated using materials from the vessel materials within the core beltline region.The methods and results are presented in Reference 6.9, as required by 10 CFR 50,Appendices G and H.As described in the NMP2 Updated Safety Analysis Report (USAR) Section 5.3.1.6, MaterialSurveillance, the BWRVIP Integrated Surveillance Program (ISP) will determine the removalschedule for the remaining two (2) NMP2 surveillance capsules. Per the BWRVIP ISP, NMP2 isnot a host plant; all remaining surveillance capsules are classified as "Standby." The NMP2material surveillance program is administered in accordance with the BWRVIP ISP. The ISPcombines the US BWR surveillance programs into a single integrated program. This programuses similar heats of materials in the surveillance programs of BWRs to represent the limitingmaterials in other vessels. It also adds data from the BWR Supplemental Surveillance Program(SSP).NMP2 maintains a Reg. Guide 1.190 fluence monitoring program and reviews the actual fluenceon a routine basis, as discussed in USAR Section 4.1.4.5 and Appendix C, Section C.2.1.2.Page 15 of 27 PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportAppendix BNMP2 Reactor Pressure Vessel P-T CurveSupporting Plant-Specific InformationFigure of NMP2 Reactor Pressure VesselTOP HEADTOP HEAD FLANGESHELL FLANGE-SHELL #4-SHELL #3SHELL #2iter Leveltrumentation NozzleSHELL #1LPCI NOZZLETOP OFACTIVE FUEL(TAF)366.31'"BOTTOM OFACTIVE FUEL(BAF)21 6.31'"Page 16 of 27 PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportAppendix BNMP2 Initial RTNDT Values for RPV MaterialsPlate and Flange MaterialsTest DropComponent Heat or Heat I Flux I Lot Temp Charpy Energy'" (TO-r-60) Weight RTNDT(*F) (ft-lb) (*F) NDT ('F)(*F)Top Head & FlangeShell FlangeMark 27-1 48D 1072-1-1 /48B1121-1-1 40 67 131 110 10 -20 10Top Head FlangeMark 32-1 49B 168-1-1 /49D 161-1-1 30 94 98 77 0 -30 0Top Head DollarMark 36-2 A0678-1 40 53 62 53 -20 -20 -20Top Head Torus PlatesMarks 36-1-1 36-1-2, 36-1-3 C2325-2 60 55 55 52 0 -20 0Marks 36-1-4. 36-1-5, 36-1-6 C2480-2 30 62 50 66 -30 -40 -30Shell CoursesUpper Shell PlatesMark 24-1-1 C3193-1 60 59 56 58 0 -10 0Mark 24-1-2 C3192-2 70 61 54 63 10 -10 10Mark 24-1-3 C3192-1 70 58 51 72 10 -10 10Upper Intermediate PlatesMark 23-1-1 C3121-1 70 52 50 50 10 -20 10Mark 23-1-2 C3138-1 50 56 56 50 -10 -50 -10Mark 23-1-3 B6991-1 20 70 64 56 -40 -40 -40Lower-Intermediate PlatesMark 22-1-1 C3065-1 50 70 50 50 -10 -30 -10Mark 22-1-2 C3121-2 60 50 53 50 0 -30 0Mark 22-1-3 C3147-1 60 50 50 52 0 -20 0Lower Shell PlatesMark 21-1-1 C3147-2 60 52 50 50 0 -20 0Mark 21-1-2 C3066-2 40 55 52 51 -20 -30 -20Mark 21-1-3 C3065-2 70 51 53 51 10 -10 10Bottom HeadBottom Head DollarMark 13-1 B6803-2 50 55 58 52 -10 -10 -10Mark 13-2 C2944-2 40 62 58 60 -20 -20 -20Mark 13-3 B6803-1 70 68 56 54 10 -30 10Bottom Head Torus PlatesMarks 13-4, 13-5, 13-6 C3073-1 60 51 54 53 0 -20 0Marks 13-7, 13-8, 13-9 C3073-2 70 51 57 55 10 -10 10Skirt KnuckleMark 9-1-1, 9-1-2, 9-1-3, 9-1-4 C3957-3 30 55 54 60 -30 -20 -20(1) Minimum Charpy values are used in these calculations.Page 17 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportAppendix BNMP2 Initial RTNDT Values for RPV Materials, ContinuedNozzle MaterialsTest DropComponent Heat or Heat / Flux/.Lot Temp Charpy Energy[U (T50T-60) Weight RTNDT(CF) (ft-lb) (*F) NDT (°F)(*F)N1 Recirculation Outlet NozzleMark 49-1-1 Q2QL1W/63A-1 40 102 109 91 -20 -20 -20Mark 49-1-2 Q2QLlW/63A-2 40 95 106 82 -20 -20 -20N2 Recirculation Inlet NozzleMark 52-1-1 Q2QL2W I 62A-1 30 93 97 94 -30 -20 -20Mark 52-1-2 Q2Q67W / 62A-2 40 95 103 105 -20 -20 -20Mark 52-1-3 Q2Q67W / 62A-3 40 82 81 101 -20 -20 -20Mark 52-1-4 02Q67W / 62A-4 40 67 64 77 -20 -20 -20Mark 52-1-5 Q2Q67W / 62A-5 40 62 67 109 -20 -20 -20Mark 52-1-6 Q2QL2W / 62A-6 40 102 102 109 -20 -20 -20Mark 52-1-7 Q2QL2W / 62A-7 40 79 83 87 -20 -20 -20Mark 52-1-8 Q2Q65W / 62A-8 40 105 120 128 -20 -20 -20Mark 52-1-9 Q2Q65W / 62A-9 40 105 103 124 -20 -20 -20Mark 52-1-10 Q2QL2W / 62A-10 40 94 90 66 -20 -20 -20N3 Steam Outlet NozzleMark 56-1-1 Q2Q68W / 1828-1 40 78 99 52 -20 -20 -20Mark 56-1-2 Q2Q68W / 182B-2 40 76 87 75 -20 -20 -20Mark 56-1-3 Q2Q68W / 182B-3 40 69 107 97 -20 -20 -20Mark 56-1-4 Q2Q68W / 182B-4 40 121 120 116 -20 -20 -20N4 Feedwater NozzleMark 59-1-1 Q2QL2W / 315A-1 40 103 103 87 -20 -20 -20Mark 59-1-2 Q2QL2W / 315A-2 30 77 96 100 -30 -20 -20Mark 59-1-3 Q2QL2W / 315A-3 30 77 56 54 -30 -20 -20Mark 59-1-4 Q2QL2W / 315A-4 30 114 101 92 -30 -20 -20Mark 59-1-5 Q2QL2W / 315A-5 40 95 72 116 -20 -20 -20Mark 59-1-6 Q2QL2W / 315A-6 40 101 79 73 -20 -20 -20N5 Core Spray Nozzle (Low Pressure)Mark 63-1-1 Q2QL3W / 867B-1 20 82 81 66 -40 -20 -20N6 RHR-LPCI NozzleMark 67-1-1 Q2QL3W / 854A-1 40 53 101 84 -20 -20 -20Mark 67-1-2 Q2Q0L3W / 854A-2 40 64 74 70 -20 -20 -20Mark 67-1-3 Q2QL3W / 854A-3 40 65 70 60 -20 -20 -20N7 Top Head Spray NozzleMark 71-1-1 Q2Q60QT / 569F-1 30 98 114 131 -30 -20 -20Mark 72-1 Weld Neck Flange 720230 / 10618D / 3445-1 20 90 122 179 -40 -40 -40Mark 73-2-1 Blind Flange C4889-3 30 54 70 78 -30 -30 -30N8 Top Head Vent NozzleMark 74-1 211290 / L3156 40 50 54 51 -20 -20 -20Mark 75-1 Weld Neck Flange 720230 / 10618D / 3445-1 20 90 122 179 -40 -40 -40Mark 76-1A Blind Flange D1295-3 20 52 58 72 -40 -40 -40N9 Jet Pump Instrumentation NozzleMark 77-1-1 Q2QL4W / R64A-1 40 66 62 54 -20 -20 -20Mark 77-1-2 Q2QL4W / R64A-2 40 57 62 56 -20 -20 -20N10 CRD Hydraulic System ReturnMark 80-1 Q2QL4W / 868B 40 67 63 65 -20 -20 -20Page 18 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportAppendix BNMP2 Initial RTNDT Values for RPV Materials, ContinuedNozzle MaterialsTest DropComponent Heat or Heat I Flux I Lot Temp Charpy Energy[1' (T5oT-60) Weight RTNDT(OF) (ft-lb) (°F) NOT (°F)_(F)Nll Core AP & Liquid ControlMark 84-1 NX5001 / 1765 (Alloy 600) (Note 2)Mark 89-1 Weld Coupling 67993/1550 (Stainless) (Note 2)Mark 85-1-1 54318 / 1095 (Alloy 600) (Note 2)N12 Instrument NozzleMark 88-1-1 thru 88-1-4 717456 / L9295 / FE-1 40 64 58 57 -20 -20 -20N13 Instrument NozzleMark 88-1-5 thru 88-1-6 717456 / L9295 / FE-1 40 64 58 57 -20 -20 -20N14 Instrument NozzleMark 91-1-1 thru 91-1-4 717456 / L9295 / FE-1 40 64 58 57 -20 -20 -20N15 Drain NozzleMark 93-1 B19W (213099)/ R853A 40 85 86 93 -20 -20 -20N16 Core Spray (High Pressure)Mark 63-1-2 Q2QL3W / 867B-2 40 89 89 71 -20 -20 -20N17 Seal Leak Detector NozzleMark 104-1 NX4745 / 461 (Alloy 600) (Note 2)Mark 30-1 615146/3444 (Note 3)Mark 142-1 615146/3444 (Note 3)N18 Top Head Spare NozzleMark 71-1-2 Q2Q60QT / 569F-2 30 51 66 93 -30 -20 -20Mark 99-1 Weld Neck Flange 720230/ 10618D / 3445-1 20 90 122 179 -40 -40 -40Mark 73-2-2 Blind Flange B7492-2 40 62 50 55 -40 -40 -40CRD Stub TubeMark 14 NX4994 I M1753 (Alloy 600) (Note 2)Mark 14 NX5190 / M1769 (Alloy 600) (Note 2)Mark 14 NX6104 / M4728 (Alloy 600) (Note 2)Mark 14 NX7249G (Alloy 600) (Note 2)Mark 14 1NX5151 / M1758 (Alloy 600) (Note 2)Mark 14 2NX5291/M1789 (Alloy 600) (Note 2)Mark 14 4NX5190 / M1770 (Alloy 600) (Note 2)Mark 14 NX5159 (Alloy 600) (Note 2)Mark 14 NX4902 (Alloy 600) (Note 2)Nozzle WeldsN6 LPCI Nozzle 629865/A421A27AD -10 69 70 88 -70 -90 -70N6 LPCI Nozzle 04T931/A423B27AG 0 65 69 72 -60 -90 -60N6 LPCI Nozzle 402P3162/H426B27AE -10 60 54 68 -70 -70 -70N6 LPCI Nozzle 5P6771/Unde 124/0342 (Single) 30 78 53 68 -30 -30 -30N6 LPCI Nozzle 5P6771/Linde 124/0342 (Tandem) 40 77 81 83 -20 -20 -20N6 LPCI Nozzle 492L4871/A421B27AF 10 56 58 61 -50 -80 -50N6 LPCI Nozzle 05T776/L314A27AH -10 69 72 81 -70 -70 -70(1) Minimum Charpy values are used in these calculations.(2) Alloy 600 and Stainless Steel components do not require fracture toughness evaluation; see Appendix A of Reference 6.1 for additionalinformation.(3) Small diameter piping does not require fracture toughness evaluation; see Appendix A of Reference 6.1 for additional information.Page 19 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportAppendix BNMP2 Initial RTNDT Values for RPV Materials, ContinuedAppurtenance MaterialsTest DropComponent Heat or Heat I Flux I Lot Terp Charpy Energy'" (Tsor60) Weight RTNDT(CF) (ft-lb) ('F) NDT (*F)(*F)Support SkirtMark 10-1-1 C2762-1F 30 60 62 59 -30 -50 -30Mark 10-1-2 A0797-3 20 54 62 51 -40 -10 -10Support Skirt ExtensionMark 10-2-1 thru 10-2-6 R0530-1 70 112 110 90 10 10 10Shroud SupportMarks 20-1-1 thru 20-1-4 (Horizontal Support to BH) 3NX6945-1 I PC-9435 (Alloy 600) (Note 2)Marks 20-1-1 thru 20-1-4 (Horizontal Support to BH) 2NX7083-1 I PC-9729 (Alloy 600) (Note 2)Marks 20-2-1, 20-2-2 (Horizontal Support to BH) 2NX694&-1 / PC-9437 (Alloy 600) (Note 2)Marks 20-4-1 thru 20-4-6 (Vertical Supports from CP) 1 NX6897-1 I PC-9401 (Alloy 600) (Note 2)Marks 20-4-7 thru 20-4-14 (Vertical Supports from CP) 1 NX6897-7 / PC-9402 (Alloy 600) (Note 2)Marks 17-1-1 thru 17-1-14 (Vertical Supports to BH) 636478-4X (Alloy 600) (Note 2)Stabilizer BracketMark 101-1 A1322-2B 50 67 50 51 -10 -20 -10Refueling Bellows BarMark 29-1-1 thru 29-1-6 A2457-7 60 50 50 52 0 -20 0Mark 45-1-1 thru 45-1-6 R0503-1 60 53 46 60 0 0 0Guide Rod BracketMark 106-1-1 & 106-1-2 120867/ 333 (Stainless) (Note 2)Steam Dryer Support BracketMark 108-1-1 thru 108-1-4 120867 /333 (Stainless) (Note 2)Core Spray BracketMark 116-1-1 thru 116-1-8 120867 /333 (Stainless) (Note 2)Feedwater Sparger BracketMark 112-1-1 thru 112-1-12 633345 /333 (Stainless) (Note 2)Top Head Lifting LugMark 43-1-5 thru 43-1-8 C3916-2B 60 58 53 59 0 -40 0Thermocouple Pads and ClampsMark 47-1 and 47-2 C3427-13A 30 50 53 50 -30 -30 -30Dryer Hold Down BracketMarks 110-1-1 thin 110-1-4 C2325-2 60 55 55 52 0 -20 0Marks 110-1-1 thru 110-1-4 C2480-2 20 50 53 50 -40 -40 -40(1) Minimum Charpy values are used in these calculations.(2) Alloy 600 and Stainless Steel components do not require fracture toughness evaluation; see Appendix A of reference 6.1 for additional information. CP = CorePlate; BH = Bottom HeadPage 20 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportAppendix BNMP2 Initial RTNDT Values for RPV Materials, ContinuedBolting MaterialsTest C harpy Energy Mi Lat LSTComponent Heat Temp (ft-Ib) Exp (*F)(°F) (mils)STUDSClosureMark 38-1-1 thu 38-1-13 11949 10 54 56 56 32 10Mark 38-1-14 thu 38-1-26 11054 10 46 47 46 26 10Mark 38-1-27 thu 38-1-44 11949 10 54 56 56 32 10Mark 38-1-45 thu 38-1-56 84176 10 49 49 48 26 10Mark 38-1-57 thu 38-1-76 11949 10 54 56 56 32 10N7 & N18 NozzlesMark 73-4 82116 10 63 64 63 25 10N8 NozzleMark 76-3 82116 10 63 64 63 25 10NUTSClosureNMark 39-5-1 thu 39-5-48 43320 10 48 50 48 29 10Mark 39-5-49 thu 39-5-54 83706 10 50 51 54 26 10Mark 39-5-55 thu 39-5-76 84751 10 48 48 47 25 10N7 & N18 NozzlesMark 73-5 14886 10 69 72 76 30 10N8 NozzleMark 76-4 14886 10 69 72 76 30 10CLOSURE BUSHINGSMark 152-1-1 thru 152-1-76 52504 10 48 48 50 28 10CLOSURE WASHERSMark 39-6-1 thru 39-6-76 83706 10 50 51 54 26 10Page 21 of 27 PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportAppendix BNMP2 Adjusted Reference Temperatures for 32 EFPYLower Shell. Shell 1 to Sholl 2 Girth Weld and Lower Shell Axial Welds Note 10Thickoess in inches = 6.1875Lower-ontermediate Shell and Axial WeldsThickoess in inche- 6.1875N6 NozzleThickness in inchesN12 NozzleThickness in nches=Note 10Note 10Note 1054 EFPY Peak I D fluence 1.58E+18 n4cm'32 EFPY Peak I D. uence = 9.36E, 17 Ncm'32 EFPY Peak 114 T fluence = 6.46E+17 nlcm'54 EFPY Peak I. D. nuence 1 62E018 10cl'32 EFPY Peak I D fcuence = 9.60E+17 rwcm232 EFPY Peak 114 T fuence = 6.62E÷17 Nw'M254 EFPY Peak I.D. tluence = 5.34E+17 Now232 EFPY Peak I D. fluence = 3.16E+17 NVcm232 EFPY Peak 114 T fluence = 2.18E+17 n/cmz54 EFPY Peak I.D fIuence = 3.65E+17 r4cm'32 EFPY Peak I.D. Suence 2.16E+17 rscm'32 EFPY Peak 114 T fluence = 1 49E017 slcm26 187561875Adjusted Inital 114 T 32 EFPY 32 EFPY 32 EFPYCOMPONENT HEAT %Cu %Ni CF CF RTxaT Fluence a RTaeT Ot Oe Margin Shift ARTF sdcl' "F (Note 8) PF PF "FPLATES:Lowe rentermediate ShellC306,5-1 006 063 37 -10 6.62E+17 126 0 6 126 251 15C3121-2 009 0.65 58 0 662E+17 19.7 0 10 197 394 39C3147-1 011 063 74.5 0 662E÷17 25.3 0 13 253 50.6 51Lower ShellC3065-2 006 0.63 37 10 6.46E+17 124 0 6 124 24.8 35C3066-2 0.07 0.64 44 -20 6 46E+17 14.7 0 7 14.7 29.5 9C3147-2 0.11 063 745 0 6.46E017 25.0 0 12 25.0 49.9 50WELDS: (1)Ciumofenteneal4P7216(Sy0751 0.045 0.80 61 -50 6 46E+17 20.4 0 10 204 409 -94P7216(T50751 0035 0.82 475 -80 6 46E617 159 0 8 15.9 31.8 .484P7465(Sy0751 0.02 0.82 27 -60 6.46E017 90. 0 5 9.0 18.1 -414P7465(Ty0751 0.02 0.00 27 -60 6 46E017 9.0 0 5 90 181 41AxialLower Shell 5P621401Sy0331 0.02 082 27 -50 6.46E÷17 90 0 5 9.0 18.1 -31Lowe Shell 5P6214B(T)l0331 0.014 0.70 22.8 40 6.46E+17 7.6 0 4 76 153 -25Lcnr-feoennediate Shel 5PS657(S)Y0931 0.07 0.71 95 -60 662E+17 32.3 0 16 323 645 5Lnoer-lnternediate Shell 5P5657(Ty0931 004 089 54 -60 6 62E+17 183 0 9 103 36.7 -23NOZZLES:-orgingsN6 LPCI (2) Q2Q1L3W 0.07 o60. 44 -20 2.18E+17 6.0 0 4 8.0 10.0 -iN12 Water Level Ilstwmeroation (2.3) 717456 0.272 0214 136 0 1.49E+17 194 0 10 19.4 38.9 39Weida (1)N6 LPCI (2) 629865/A421A27AD 005 1.10 69 -70 218E+17 123 0 6 123 24.7 -45N6LPCI 2) 04T9311A423927AG 003 1.06 41 -60 2 18Ec17 7.4 0 4 7.4 149 45N6 LPCI (2) 402P3162JH426827AE 003 083 41 -70 2.10E+17 7.4 9 4 7.4 149 -55N6 LPCI (2) 5P6771(SY0342 0.03 088 41 -30 2 18E+17 7.4 0 4 7.4 149 -156 LPCI (2) 5P6771(Ty0342 0.04 0.95 54 -20 2 18E+17 9.8 0 5 9.8 196 0N6 LPCI (2) 492L487l/A421027AF 0.03 098 41 -50 2.18E+17 7.4 0 4 7.4 149 -35N6 LPCI (2) 05T7761L314A27AH 0.06 0.92 82 -70 2.18E+17 149 0 7 14.9 29.8 -40N12 Water Levi Instnamertation (9) InonnelINTEGRATED SURVEILLANCEPROGRAM (4):Plate (5) C2761-2 0.10 054 65 10 6.66E+17 20.1 0 11 221 441 54Weld (6,7) 5P6214B 0.027 0.94 36.8 53.7 A40 0662E317 182 0 9 182 36.5Noles:(1) This evoluation includes both Single (S) and Tandem IT) wire materials.(2) Chemistries and Initial RT-D for the nozzle forg0ngs were obtained from BWR fleet CMTR data. Copper content was based upon 14 data points and nickel was based upon 35 data points.(3) The N12 nozzle is claesified as a partial penetration in Shell Ring #2.(4) Repfesentatike materials as defined by the Integrated Surceillance Program (ISP).(5) The ISP plate material is not the same heat number as the target plate as defined in the ISP Therefore. the CF from RG1.99. Position 1.1 is wed to determine the ART. This information is not required per BWRVIP-135to dictate the ART owed for the NMP2 PT curves. and is proided for information only. Plate C3147-1 remains the limiting behline material for the purpose of developIng the PT curves(6) The ISP weld material is not the same heat numher ase terget weld (SP5657) as defined in the ISP. H er. the ISP weld material is the same heat as another beftine weld Therefore. the slroedllan'e datais considered and the CF is adjusted as defined in RG1.99 Postion 2.1.(7) The Adjusted CF was conneestisely calculated using the hinting parameters for this heat because there are two (2) sets of data Wovided by the ISP (from Perry and SSP materials that originated hrom Grand Gull).CF+,,,,, = (27r20)

  • 39 75 = 53.7"F(9) PorwoJ submimtal included a conser itrorw = 14.5'F. BWROG NRC-approved methodology has been applied. allowing reduction such that a, = 0-F(9) Non-feirtie matedils do not require ealuation for fracture toughness.(10) Fluence conseirtioly extrapolated for ART determination RG 1.190 Flcenee projections proided in reference 6.4Page 22 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportAppendix BNMP2 RPV Beltline P-T Curve Input ValuesAdjusted RTNDT = Initial RTNDT + Shift A = 0 + 51 = 51°F (Based on ART Table)Vessel Height H = 869.75 inchesBottom of Active Fuel Height B = 216.3 inchesVessel Radius (to base metal) R = 126.7 inchesMinimum Vessel Thickness (without clad) t = 6.1875 inchesPage 23 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportAppendix BNMP2 Definition of RPV Beltline Regionl1]ElevationComponent (inches fromRPV "0")Shell # 2 -Top of Active Fuel (TAF) 366.3"Shell # 1 -Bottom of Active Fuel (BAF) 216.3"Centerline of Recirculation Outlet Nozzle in Shell # 1 172.5"Top of Recirculation Outlet Nozzle N1 in Shell # 1 197.9"Centerline of Recirculation Inlet Nozzle N2 in Shell # 1 181.0"Top of Recirculation Inlet Nozzle N2 in Shell # 1 198.7"Centerline of LPCI Nozzle N6 in Shell #2 372.5"Bottom of LPCI Nozzle N6 in Shell #2 337.1"Centerline of Water Level Instrumentation Nozzle N12 in Shell # 2 366.0"Bottom of Water Level Instrumentation Nozzle N12 in Shell #2 364.4"[1] The beltline region is defined as any location where the peak neutron fluence isexpected to exceed or equal 1.0e17 n/cm2.[2] The dimensions identified above are specified as the distance (elevation) abovevessel "0"The review of the axial fluence edicated that the RPV fluence projected to 54 EFPYdrops to less than 1.0e17 n/cm2 at 12" e low the BAF and a~t--' above TAF. The beltlineregion considered in the develop n the P-T curves has b' conservatively adjusted toinclude the region from 204.6" to 378.4" above reactor vessel "0".Based on the above, it is concluded that none of the NMP2 reactor vessel plates, nozzles, orwelds, other than those included in the Adjusted Reference Temperature Table, are in thebeltline region.Page 24 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportAppendix CNMP2 Reactor Pressure Vessel P-T Curve ChecklistS... Parameter Completed Comments/Resolutions/ClarificationsInitial RTNDTInitial RTNDT has been determined The beltline LPCI N6 and Water Levelfor NMP2 for all vessel materials Instrumentation N12 nozzle forgingsincluding plates, flanges, forgings, and welds have been considered in thestuds, nuts, bolts, welds. development of the beltline PT curves.Include explanation (includingmethods/sources) of anyexceptions, resolution of discrepantdata (e.g., deviation from originallyreported values).Appendix B contains tables of allInitial RTNDT values for NMP2Has any non-NMP2 initial RTNDT The review performed indicated that theinformation (e.g., ISP, comparison NMP2 plant-specific weld material ARTto other plant) been used? values bound those determined for theISP representative weld material.If deviation from the LTR processoccurred, sufficient supporting No deviations from the LTR processinformation has been included (e.g.,Charpy V-Notch data used todetermine an Initial RTNDT).All previously published Initial RTNDT RVID was reviewed. All initial RTNDTvalues from sources such as the values agree. No further review wasGL88-01, RVID, FSAR, etc., have required.been reviewed.Adjusted Reference Temperature (ART)Sigma I (standard deviation for NMP2 has previously calculated theInitial RTNDT) is 00F unless the ART using a conservative of 14.50FRTNDT was obtained from a source for all materials. However, since theother than CMTRs. If ai is not equal GE/BWROG method of estimatingto 0, reference/basis has been RTNDT per NEDC-32399-P operates onprovided, the lowest Charpy energy value andprovides a conservative adjustment tothe 50 ft-lb level, the value of ai istaken to be 0°F for the vessel materialsin the evaluation.Sigma A (standard deviation forARTNDT) is determined per RG 1.99,Rev. 2Page 25 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportParameter Completed Comments/Resolutions/ClarificationsChemistry has been determined for Z The vessel chemistries are consistentall vessel beltline materials including with previously reported information.plates, forgings (if applicable), andwelds for NMP2. The LPCI (N6) Nozzle and the WaterInclude explanation (including Level Instrumentation (N12) Nozzle aremethods/sources) of any now included in the extended beltlineexceptions, resolution of discrepant region. For the N6 nozzle forging anddata (e.g., deviation from originally welds, CMITR's were located whichreported values), contained Cu and Ni values as shownin the ART table.Non-NMP2 chemistry information Z An adjusted CF was required for ISP(e.g., ISP, comparison to other Heat 5P6214B, and was determinedplant) used has been adequately per Paragraph 2.1 of RG 1.99.defined and described.For any deviation from the LTR Z No deviations from the LTR processprocess, sufficient information hasbeen included.All previously published chemistry [values from sources such as theGL88-01, RVID, FSAR, etc., havebeen reviewed.The fluence used for determination Zof ART and any extended beltlineregion was obtained using an NRC-approved methodology.The fluence calculation provides an Zaxial distribution to allowdetermination of the vesselelevations that experience fluenceof 1.0E17 n/cm2 both above andbelow active fuel.The fluence calculation provides an Zaxial distribution to allowdetermination of the fluence forintermediate locations such as thebeltline girth weld (if applicable) orfor any nozzles within the beltlineregion.All materials within the elevation [range where the vessel experiencesa fluence >1.0E17 n/cm2 have beenincluded in the ART calculation. Allinitial RTNDT and chemistryinformation is available orPage 26 of 27PTLR-2Revision 0 NMP2 Pressure and Temperature Limits ReportParameter-:- Completed Comments/ResolutionslClarificationsexplained.DiscontinuitiesThe discontinuity comparison has [been performed as described in No deviationsSection 4.3.2.1 of the LTR. Anydeviations have been explained.Discontinuities requiring additional [components (such as nozzles) to beconsidered part of the beltline havebeen adequately described. It isclear which curve is used to boundeach discontinuity.Appendix G of the LTR describes [the process for considering a The thickness discontinuity evaluationthickness discontinuity, both beltline demonstrated that no additionaland non-beltline. If there is a adjustment is required; the curvesdiscontinuity in the NMP2 vessel bound the discontinuity stresses.that requires such an evaluation, theevaluation was performed. Theaffected curve was adjusted tobound the discontinuity, if required.Appendix H of the LTR defines the Z An evaluation was performed to assurebasis for the CRD Penetration curve that the CRD discontinuity bounds thediscontinuity and the appropriate other discontinuities that are protectedtransient application. The NMP2 by the CRD curve with respect toevaluation bounds the requirements pressure stresses. For heatup/of Appendix H. cooldown conditions, the CRDpenetration provides bounding limits.Appendix J of the LTR defines the [basis for the Water LevelInstrumentation Nozzle curvediscontinuity and the appropriatetransient application. The NMP2evaluation bounds the requirementsof Appendix J.Page 27 of 27PTLR-2Revision 0
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