View source for NL-14-0639, Revision 5 Pressure and Temperature Limits Report and Unit 2 Revision 5 Pressure and Temperature Limits Report

{{Adams
| number = ML14112A519
| issue date = 04/22/2014
| title = Revision 5 Pressure and Temperature Limits Report and Unit 2 Revision 5 Pressure and Temperature Limits Report
| author name = Pierce C
| author affiliation = Southern Co, Southern Nuclear Operating Co, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000424, 05000425
| license number = 
| contact person = 
| case reference number = NL-14-0639
| document type = Letter type:NL, Report, Technical
| page count = 50
}}

=Text=
{{#Wiki_filter:Charles R.Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.40 Inverness Center Parkway PostOfficeBox 1295 Birnningham, Alabama 35201 Tel 205,992.7872 Fax 205.992.7601 APR22 2014 SOUTHERN COMPANY Docket Nos.: 50-424 NL-14-0639 50-425U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington,D.C.20555-0001 Vogtle Electric Generating PlantUnit1 Revision 5 Pressure and Temperature Limits Report Unit 2 Revision 5 Pressure and Temperature Limits Report Ladies and Gentlemen:
In accordance with Technical Specification 5.6.6.d, Southern Nuclear Operating Company submits the enclosed Reactor Coolant System (RCS)Pressure and Temperature Limits Report (PTLR)Revision5forUnit 1, and Revision5forUnit2.
This letter containsnoNRC commitments.Ifyou have any questions, please contact Ken McElroy at (205)992-7369.Respectfully submitted, C.R.Pierce Regulatory Affairs Director CRP/RMJ/lac

==Enclosures:==

1.Unit 1 PTLR, Revision 5 2.Unit 2 PTLR, Revision 5 U.S.Nuclear Regulatory Commission NL-14-0639 Page 2 cc: Southern Nuclear Operating CompanyMr.S.E.Kuczynski, Chairman, President&CEOMr.D.G.Bost, Executive Vice President&Chief Nuclear OfficerMr.T.E.Tynan, Vice President-Vogtle1&2Mr.B.L.Ivey, Vice President-Regulatory AffairsMr.D.R.Madison, Vice President-Fleet OperationsMr.B.J.Adams, Vice President-Engineering RType: CVC7000 U.S.Nuclear Regulatory CommissionMr.V.M.McCree, Regional Administrator Mr.R.E.Martin,NRR Senior Project Manager-Vogtle1&2 Mr.L.M.Cain, Senior Resident Inspector-Vogtle1&2 Vogtle Electric Generating PlantUnit1 Revision 5 Pressure and Temperature Limits ReportUnit2 Revision 5 Pressure and Temperature Limits Report Enclosure 1 Unit 1 PTLR, Revision 5 Southern Nuclear Operating Company Vogtle Unit 1 Pressure Temperature Limits Report Revision 5, iVIarch 2014 Vogtle Unit1-Pressure Temperature Limits Report Southern Nuclear Table of Contents List of Tables liiListof Figures iv 1.0 RCS Pressure Temperature LimitsReport(PTLR) 1 2.0 Operating Limits 12.1RCS PressureandTemperature(P/T)
Limits (LCO 3.4.3)13.0Cold Overpressure Protection Systems (LCO 3.4.12)1 3.1 Pressurizer PORV Setpoints 23.2Arming Temperature 24.0ReactorVessel MaterialSurveillanceProgram 2 5.0 Supplemental Data Tables 3 6.0 References 19 Revision 5 VogtleUnit1-Pressure Temperature Limits Report Soutliern Nuclear List of TablesTable2-1VogtleUnit1 HeatupLimitsat36EFPY(WithoutUncertaintiesforInstrumentationErrors) 6Table2-2VogtleUnit1 CooldownLimitsat36EFPY (Without UncertaintiesforInstrumentationErrors) 7Table3-1 Vogtle Unit1DataPointsforCOPSPORVSetpoints 8Table5-1 Comparison of theVogtleUnit1 SurveillanceMaterial30 ft-lb Transition TemperatureShiftsandUpper Shelf Energy DecreaseswithRegulatoryGuide 1.99, Revision 2, Predictions 10Table5-2CalculationofChemistryFactorsusingVogtle Unit1Surveillance Capsule Data 11Table5-3ReactorVessel Beltline Material UnirradiatedToughnessPropertiesforVogtleUnit1 12Table5-4 PeakNeutronFluenceProjectionsatKey AzimuthalLocationsontheReactorVessel Clad/Base Metal InterfaceforVogtleUnit1 (10^n/cm^E>1.0MeV) 13Table5-5 Vogtle Unit 1 Calculationofthe AdjustedReferenceTemperature (ART)Values for the1/4TLocation@36EFPY 14Table5-6VogtleUnit1 Calculation of theARTValuesforthe3/4TLocation@36EFPY 15Table5-7Summaryofthe LimitingARTValuesUsedintheGenerationoftheVogtleUnit1 Heatup/Cooldown Curves 16Table5-8 RTpjsCalculationsforVogtle Unit 1 BeltlineRegionMaterialsat 36 EFPY 17Table5-9 RTpjsCalculationsfor Vogtle Unit 1 BeltlineRegionMaterialsat 57 EFPY 18 Revision 5 Vogtle Unit1-Pressure Temperature Limits Report Southern Nuclear List of FiguresFigure2-1VogtleUnit1 Reactor Coolant System Heatup Limitations (Heatup Rate of 100&deg;F/hr)Applicable for theFirst36EFPY (Without Margins for Instrumentation Errors)4Figure2-2VogtleUnit1 Reactor Coolant SystemCooldownLimitations (Cooldown Ratesupto 100&deg;F/hr)ApplicablefortheFirst36EFPY(WithoutMarginsfor Instrumentation Errors)5Figure3-1VogtleUnit1MaximumAllowableNominalPORV Setpoints for COPS 9 iv Revision 5 Vogtle Unit1-Pressure Temperature Limits Report Southern Nuclear 1.0 RCS Pressure Temperature Limits Report (PTLR)ThisPTLRforVogtleUnit1 has been prepared in accordancewiththe requirements ofTechnicalSpecification(TS)5.6.6.TheTS addressedinthisreport arelistedbelow:LCO3.4.3RCS Pressure and Temperature (P/T)LimitsLCO3.4.12Cold Overpressure Protection Systems (COPS)Revisions to thePTLRshallbeprovidedto the NRC after issuance.2.0RCS Pressure and Temperature(P/T)Limits The limitsforTS3.4.3arepresentedinthesubsections which followandweredeveloped using the NRC approved methodology in WCAP-14040, Revision 4'^'with exception of WCAP-16142-P, Revision (EliminationoftheFlange Requirement).
The operability requirements associated withCOPSare specified in LCO 3.4.12andwere determined to adequately protecttheRCSagainst brittle fracture intheeventofacold overpressuretransientin accordance with the methodology specifiedinTS 5.6.6.2.1RCSP/T Limits(LCO3.4.3)2.1.1Theminimumboltup temperatureis60&deg;F.2.1.2TheRCS temperature rate-of-change limits are:a.Amaximum heatup rateof100&deg;Fin any 1-hour period.b.Amaximumcooldownrateof 100&deg;Finany1-hourperiod.c.Amaximum temperature change of lessthanorequalto 10&deg;Finany1-hourperiodduring inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.2.1.3TheRCSP/T limitsforheatup, cooldown,inservicehydrostaticandleaktesting, and criticality are specified by Figures 2-1 and 2-2.3.0Cold Overpressure Protection Systems (LCO 3.4.12)ThesetpointsforthepressurizerPowerOperatedRelief Valves (PORVs)andarming temperature are presentedinthe subsections which follow.These setpointsandarming temperature have been developed using the NRC-approved methodology specified in TS 5.6.6.Revision 5 Vogtle Unit1-Pressure Temperature Limits Report Southern Nuclear 3.1 Pressurizer PORV Setpoints The pressurizer PORV setpoints are specifiedinFigure3-1 and Table 3-1.The limitsforthe COPS setpoints are containedinthe36EFPY steady-state curves(Table2-2),which arebeltlineconditionsand are not compensated for pressuredifferencesbetweenthe pressurizertransmitterandthereactormidplane/beltlineorforinstrument inaccuracies.
The pressuredifferencebetweenthe pressurizer transmitter and the reactor vessel midplane/beltlinewithfour reactor coolant pumps in operationis74psi.Note: These setpointsincludeanallowanceforthe 50&deg;Fthermaltransporteffectfor heat injection transients.
A calculation has been performedtoconfirm that the setpoints will maintain the system pressure within the established limits when the pressure difference between the pressure transmitter and reactor midplane and maximum temperature/pressure instrument uncertainties are applied to the setpoints.3.2Arming Temperature COPSshallbe armedwhenanyRCScoldleg temperature is&#xa3;220&deg;F.4.0 Reactor Vessel Material Surveillance ProgramThereactor vessel material irradiation surveillance specimensshallberemovedandexaminedtodetermine changes in material properties.
The removalscheduleis provided in UFSAR Table5.3.1-8.Theresultsof theseexaminationsshallbeusedtoupdateFigures 2-1, 2-2, and 3-1.Thepressurevesselsteel surveillance program (WCAP-11011'''')
is in compliance withAppendixto 10CFR50,"ReactorVessel MaterialSurveillanceProgramRequirements."Thematerialtestrequirementsandthe acceptance standard utilizethereference nil-ductility temperature RTndt, which is determined in accordance with ASTM E23''.The empirical relationship between RTndtandthefracture toughnessofthe reactor vessel steel is developed in accordance with Code Case N-640''of Section XIoftheASMEBoilerand PressureVesselCode,Appendix G,"FractureToughnessCriteriaforProtectionAgainst Failure"'^'.
The surveillance capsule removal schedulemeetsthe requirements of ASTM E185-82''.
The removal schedule is provided in UFSAR Table 5.3.1-8.Removalof these specimen capsules was completedforUnit1atrefueling outage 1R14.Referto UFSAR paragraph 5.3.1.6.1.4foradescriptionoftheexternalneutron monitoring system also known as ex-vessel neutron dosimetry (EVND)system.Revision 5 Vogtle Unit1-Pressure Temperature Limits Report Southern Nuclear 5.0 Supplemental Data Tables Table 5-1 contains a comparison of measured surveillance material 30 ft-lb transition temperature shifts and upper shelf energy decreases with Regulatory Guide 1.99, Revision 2'', predictions.Table5-2 showscalculationsofthesurveillancematerialchemistryfactorsusingsurveillance capsuledata.Notethatinthecalculationofthesurveillanceweldchemistryfactor,theratio procedurefromRegulatoryGuide 1.99,Revision2was followed.Theratioinquestionis equal to 1.02.Table5-3providestherequired Vogtle Unit1reactor vessel toughness data.Table5-4providesasummaryofthefluencevaluesusedinthe generationofthe heatup and cooldown limit curves and the PTS evaluation.Table5-5and5-6showthecalculationofthe1/4Tand3/4T adjusted reference temperature at36EFPYfor eachbeltlinematerialinthe Vogtle Unit1reactor vessel.The limiting beltline material was the intermediate shell plate B8805-2.Table5-7providesasummaryoftheadjustedreference temperature (ART)valuesofthe VogtleUnit1 reactor vessel beltline materials at the 1/4T and 3/4T locations for 36 EFPY.Table5-8 provides RTpts valuesforVogtleUnit1at36EFPY.Table5-9 provides RTpjs valuesforVogtleUnit1at57EFPY.
Revision 5 VogtleUnit1-Pressure Temperature Limits Report l\/laterial Property Basis Limiting Material: Intermediate Shell Plate B8805-2LimitingART Values at 36EFPY:1/4T.
110&deg;F 3/4T, 95&deg;F 2500 2250 Leal<Test Limit 2000 Southern Nuclear 1750--Unacceptable Operation Acceptable Operation 0^1500 (0 1250 1000 750 500 250 Heatup Rate 60Deg.F/Hr Heatup Rate lOODeg.F/Hr Boltup Temp.60'F Critical Limit 60Deg.F/Hr Critical Limit 100Deg.F/HrCriticalityLimit based on inservlce hydrostatic testtemperature (1 TO'F)forthe service period upto36 EFPY The lower limit for RCS pressureis-14.7psig 0 50 100 150200250 300 350 400 450 500 550 Moderator Temperature(Deg.F)Figure2-1VogtleUnit1 Reactor Coolant System Heatup Limitations (Heatup Rate of 100&deg;F/hr)Applicable for the First36EFPY (Without Margins for Instrumentation Errors)(Plotted Data provided on Table 2-1)Revision 5 VogtleUnit1-Pressure Temperature Limits Report Southern Nuclear Material Property Basis Limiting Material: Intermediate Shell Plate B8805-2LimitingART Values at36EFPY:1/4T, 110&deg;F 3/4T, 95T 12 (0&#xa5;3 (0 0)&#xa3;Q.<<3 O (0 O 2500 2250 2000 1750 1500 1250 1000 750 500 250 0 Una iccept able wp^iaiiuii Acceptable Operation Cooldown Rates, T/Hi steady-stat 40-60-100 e B(If 1 1>ltup imneratun i, 60&deg;F The lower limit for RCS pressureis-14.7psig 0 50100150 200 250 300 350 400 450500550 Moderator Temperature(Deg.F)Figure 2-2 VogtleUnit1 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100&deg;F/hr)Applicable for the First 36 EFPY (Without Margins for Instrumentation Error)(Plotted Data provided on Table 2-2)Revision 5 VogtleUnit1-Pressure Temperature Limits Report Table 2-1 VogtleUnit1 Heatup Limits at 36 EFPY (Without Uncertainties for Instrumentation Errors)Southern Nuclear 60T/hr Heatup 100F/hr Heatup 60&deg;F/hr Heatup Criticality Limit 100F/hr Heatup Criticality Limit Leak Test Limit T P T P T P T P T P 60-14.7 170-14.7 60-14.7 170-14.7 153 2000 60 747 170 760 60 730 170 730 170 2485 65 760 170 760 65 730 170 730 70 760 170 760 70 730 170 730 75 760 170 760 75 730 170 730 80 760 170 763 80 730 170 730 85 763 170 770 85 730 170 730 90 770 170 782 90 730 170 730 95 782 170 796 95 730 170 733 100 796 170 815 100 733 170 739 105 815 170 836 105 739 170 747 110 836 170 862 110 747 170 759 115 862 170 891 115 759 170 774 120 891 170 925 120 774 170 791 125 925 170 962 125 791 170 812 130 962 175 1005 130 812 175 837 135 1005 180 1052 135 837 180 865 140 1052 185 1105 140 865 185 897 145 1105 190 1163 145 897 190 933 150 1163 195 1228 150 933 195 974 155 1228 200 1300 155 974 200 1020 160 1300 205 1380 160 1020 205 1071 165 1380 210 1468 165 1071 210 1128 170 1468 215 1566 170 1128 215 1191 175 1566 220 1674 175 1191 220 1261 180 1674 225 1793 180 1261 225 1339 185 1793 230 1925 185 1339 230 1426 190 1925 235 2070 190 1426 235 1521 195 2070 240 2231 195 1521 240 1627 200 2231 245 2408 200 1627 245 1743 205 2408 205 1743 250 1872 210 1872 255 2014 215 2014 260 2171 220 2171 265 2344 225 2344 Revision 5 VogtleUnit1-Pressure TemperatureLimitsReport Table 2-2 VogtleUnit1 Cooldown Limits at 36 EFPY (Without Uncertainties for Instrumentation Errors)Southern Nuclear Steady State 20F/hr 40&deg;F/hr 60F/hr 100&deg;F/hr T 1 P T 1 P T 1 P T 1 P T 1 P 60-14.7 60-14.7 60-14.7 60-14.7 60-14.7 60 747 60 709 60 670 60 633 60 559 65 762 65 725 65 688 65 652 65 582 70 778 70 742 70 707 70 673 70 608 75 796 75 762 75 728 75 696 75 637 80 816 80 783 80 752 80 722 80 668 85 838 85 807 85 778 85 751 85 704 90 862 90 834 90 807 90 783 90 743 95 889 95 863 95 840 95 819 95 787 100 918 100 895 100 875 100 858 100 835 105 951 105 931 105 915 105 902 105 889 110 987 110 971 110 959 110 950 110 948 115 1027 115 1015 115 1007 115 1004 120 1071 120 1063 120 1061 125 1120 125 1117 130 1173 135 1233 140 1299 145 1371 150 1452 155 1541 160 1639 165 1747 170 1867 175 2000 180 2146 185 2308 Revision 5 VogtleUnit1-Pressure Temperature Limits Report Southern Nuclear Table 3-1 Vogtle Unit1DataPointsforthe Maximum Allowable NominalCOPSPORV Setpoints Temperature (Deg.F)PORV Setpoint (psig)70 612 90 612 140 642 201 760 202 760 350 760 Revision 5 VogtleUnit1-Pressure Temperature Limits Report Southern Nuclear 900 O CL s m O CL y CO 800 750 700 660 600 660 600<?460 o 400 j (201,760)/y/(70.612)^0 50 100 IdD200250300360 AUCTIONEERED LOW MEASURED ROS TEMPERATURE (DEOF)Figure 3-1: VogtleUnit1 Maximum Allowable Nominal PORV Setpoints for COPS Revision 5 VogtleUnit1-Pressure Temperature Limits Report Southern Nuclear Table 5-1 Comparison of theVogtleUnit1 SurveillanceMaterial30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide1.99,Revision2, Predictions 30 ft-lb Transition Upper Shelf Energy Fluence^^^
Temperature Shift Decrease (x10^n/cm^Predicted Measured Predicted Measured Material Capsule E>1.0 MeV)(op)(a)(OF)(i>)(%){%r Intermediate Shell U 0.334 26.80 13.56 14.5 0 Plate B8805-3^^^
Y 1.16 39.97 31.94 19.5 0 (Longitudinal)
V 1.97 45.50 42.66 22 3 X 3.53 51.03 96.50 26 11 Intermediate Shell u 0.334 26.80 0.00^^14.5 0 Plate 88805-3*"'
Y 1.16 39.97 15.19 19.5 0 (Transverse)
V 1.97 45.50 33.79 22 2 X 3.53 51.03 60.80 26 3 Surveillance U 0.334 23.52 24.98 14.5 0 Program Y 1.16 35.08 7.70 19.5 0 Weld Metal^'^V 1.97 39.93 0.00^'^22 2 X 3.53 44.79 53.40 26 3 Heat Affected u 0.334 o d o-5 Zone Y 1.16-20.78-9 Material V 1.97-42.08-11 X 3.53...10.60-7 Notes:a.Basedon Regulatory Guide 1.99, Revision 2, methodology usingthemean weightpercentvaluesofcopperand nickel of the surveillance material.b.Calculated using measured Charpy data plotted using CVGRAPH, Version 5.0.2''''''.
c.Valuesarebasedonthe definitionofuppershelf energy given in ASTM E185-82''.d.Thefluence values presented here arethecalculatedvalues,notthe best estimate values.e.Theactualvalueis-9.28.This physicallyshouldnotoccur,therefore0.00 will be conservatively assumed.f.Theactualvalueis
-1.34.This physically should not occur, therefore 0.00 will be conservatively assumed.g.Theactualvalueis
-19.35.This physically should not occur, therefore 0.00 will be conservatively assumed.h.Theheat numberforlowershellplateB8805-3is C-0623-1.i.TheSurveillanceweldwasfabricated from Wire Heat No.83653, Flux Type Linde 0091, Flux Lot No.3536.10 Revision 5 VogtleUnit1-Pressure Temperature Limits Report Southern Nuclear Table 5-2 Calculation of Chemistry FactorsUsingVogtleUnit1 Surveillance Capsule Data Material Capsule Capsule ff^>>>>ARTndt^^^FF*ARTndt FF^Intennediate Shell Plate B8805-3<''(Longitudinal)
U 0.334 0.698 13.56 9.5 0.487 Y 1.16 1.041 31.94 33.3 1.084 V 1.97 1.185 42.66 50.6 1.404 X 3.53 1.329 96.50 128.2 1.766 Intermediate Shell Plate B8805-3<''(Transverse)
U 0.334 0.698 0(e)0.0 0.487 Y 1.16 1.041 15.19 15.8 1.084 V 1.97 1.185 33.79 40.0 1.404 X 3.53 1.329 60.80 80.8 1.766 SUM: 358.2 9.482 CFb8805.3=KFF*RTndt)+Z(FF')=(358.2)-j-(9.482)=37.8>>F Surveillance Weld Material^^^
U 0.334 0.698 25.48 (24.98)^&deg;^
17.8 0.487 Y 1.16 1.041 7.85 (7.70)^&deg;'8.2 1.084 V 1.97 1.185 O^ej 0.0 1.404 X 3.53 1.329 54.47 (53.40)72.4 1.766 SUM: 98.4 4.741 CF surv.weid=Z(FF*RTndt)^Z(FF^)=(98.4)+(4.741)=20.8T Notes:a.f=Calculated fluence from capsule X dosimetry analysis results (x 10^n/cm^,E>1.0 MeV).b.FF=fluence factor c.ARTndt valuesarethe measured 30 ft-lb shift valuestakenfromApp.CofRef.
12.d.Thesurveillanceweldmetal ARTndtvalueshavebeenadjustedbyaratiofactorof 1.02.e.Actual values for ARTndtare-9.28(Plate)and
-1.34(Weld).Thisphysicallyshouldnotoccur, therefore for conservatism a value of zero will be used for this calculation.f.The heat numberforlowershellplateB8805-3is C-0623-1.g.SurveillanceWeldwasfabricatedfromWireHeat No.83653,FluxTypeLinde 0091,FluxLotNo.3536.
11 Revision 5 VogtleUnit1-Pressure Temperature Limits Report Southern Nuclear Table 5-3 Reactor VesselBeltlineMaterial Unirradiated Toughness PropertiesforVogtleUnit1 Material Description Cu (%)Ni(%)Initial RTndt^^Closure Head Flange B8801-1{Heat#123J173VA1)
--0.70 20&deg;F Vessel Flange B8802-1 (Heat#123H402VA1) 0.71 0&deg;F Intermediate Shell Plate B8805-1 (Heat#C-0613-1) 0.083 0.597 0&deg;F Intermediate Shell Plate B8805-2 (Heat#C-0613-2) 0.083 0.61 20&deg;F Intermediate Shell Plate B8805-3 (Heat#0-0623-1) 0.062 0.598 30&deg;F Lower Shell Plate B8606-1 (Heat#C-2146-1)0.053 0.593 20&deg;F Lower Shell Plate B8606-2 (Heat#0-2146-2) 0.057 0.60 20&deg;F Lower Shell Plate B8606-3 (Heat#0-2085-2) 0.067 0.623 10&deg;F IntermediateShellLongitudinalWelds, 101-124A, B&C'"'0.042 0.102-80TLowerShellLongitudinalWelds, 101-142A, B&C'"'0.042 0.102-80&deg;F Circumferential Weld 101-171'&deg;'
0.042 0.102-80&deg;F SurveillanceProgramWeld Metal*"'0.040 0.102 Notes:a.The initial RTndt valuesforthe platesandwelds are based on measured data.b.Allwelds,includingthe surveillance weld, were fabricatedwithweldwire heat number 83653,Linde0091Flux,LotNo.3536.PerRegulatoryGuide1.99,Revision2,"weight percentcopper"and"weight percent nickel" are the best-estimate valuesforthematerial,which willnonnallybethemeanofthe measured valuesforaplateorforgingorforweld samples madewiththeweldwire heat number that matchesthecritical vessel weld.12 Revision 5 VogtleUnit1-Pressure Temperature Limits Report Southern Nuclear Table 5-4 Peak Calculated Neutron Fluence ProjectionsatKeyAzimuthal Locations on the Reactor Vessel Clad/Base MetalInterfacefor Vogtle Unit 1 (n/cm^,E>1.0 MeV)Azimuthal Location EFPY 0&deg;16304514.33^^4.35E+18 6.55E+18 8.11E+18 8.38E+18 20.00 6.13E+18 9.16E+18 1.12E+19 1.15E+19 24.00 7.38E+18 1.10E+19 1.33E+19 1.37E+19 32.00 9.89E+18 1.47E+19 1.77E+19 1.81E+19 40.00 1.24E+19 1.83E+19 2.20E+19 2.25E+19 48.00 1.49E+19 2.20E+19 2.63E+19 2.70E+19 54.00 1.68E+19 2.48E+19 2.95E+19 3.03E+19(a)Theendofcycle 11(Actual)when Capsule X was withdrawn.
13 Revision 5 VogtleUnit1-Pressure Temperature Limits Report Southern Nuclear Table 5-5VogtleUnit1 CalculationoftheARTValuesfor the1/4TLocation@36 Material RG1.99 R2 Method CF m FF IRTndV"'ARTnd/^Margin^"^ARf^Intermediate Shell Plate B8805-1 Position 1.1 53.1 1.06 0 56.3 34 90 Intermediate Shell Plate B8805-2 Position 1.1 53.1 1.06 20 56.3 34 110 Intemiediate Shell Plate B8805-3 Position 1.1 38.4 1.06 30 40.7 34 105 Position 2.1 24.4 1.06 30 26.0 17lt)73 Lower Shell Plate B8606-1 Position 1.1 32.8 1.06 20 34.8 34 89 Lower Shell Plate B8606-2 Position 1.1 35.2 1.06 20 37.3 34 91 Lower Shell Plate B8606-3 Position 1.1 41.9 1.06 10 44.4 34 88 Inter.Shell Longitudinal Weld Seam 101-124A (0Azimuth)Position 1.1 34.5 0.899-80 31.0 31-18 Position 2.1 8.6 0.899-80 7.7-65 Inter.Shell Long.Weld Seams 101-124B.C (120\240"" Azimuth)Position 1.1 34.5 1.06-80 36.6 36.6-7 Position 2.1 8.6 1.06-80 9.1 9.1^^^-62 Intermediate to Lower Shell Girth Weld Seam 101-171 Position 1.1 34.5 1.06-80 36.6 36.6-7 Position 2.1 8.6 1.06-80 9.1 9.1^^^-62 Lower ShellLong.Weld Seams 101-142A,C (60&deg;, 300''Azimuth)
Position 1.1 34.5 1.06-80 36.6 36.6-7 Position 2.1 8.6 1.06-80 9.1 9.1^^^-62LowerShellLong.Weld Seam 101-142B (^80Mz/>77w^/7)
Position 1.1 34.5 0.899-80 31.0 31-18 Position 2.1 8.6 0.899-80 7.7 7.7^^^-65 Notes: a.b.c.d.e.f.g.CalculationofARTvalueswas basedoncalculatedfluenceprojectionsandnneasureddatafromtheprevious capsuleanalysisresults(CapsuleV,Ref.
10).Itshouldbenotedthatthefluenceprojectionsfrom CapsuleV(Ref.10)werehigherthan those from CapsuleX(Ref.12).However,thechemistryfactors determined from surveillance data(Table5-2)arenowhigherbutstilllowerthanthe correspondingPosition1.1chemistryfactor.Therefore,the limiting ART valuesfromPlateB8805-2couldnotbe exceededbyanupdatedplateB8805-3ARTvalueorupdatedweldARTvalues.Thus,theoriginal limitingARTvalueisstillvalid.Note,the surveillanceplatedataisnow deemed"Non-Credible,"butthishasnoimpact basedontheprecedingdiscussion.
Initial RTndt values are measured values.ARTndt=CF*FFM=2*(Oi^+ART=InitialRTndt+ARTndt+Margin{&deg;F);(RoundedperASTME29,usingthe"RoundingMethod").
Weld data deemed credible per References 10 and 12.Plate dataisnow deemed"Non-Credible." SeeNote"a." Neutron Fluence value usedforail materialisthe highestvaluefrom Reference 10for36EFPYwith exception to intermediate shell longitudinal weld 101-124A andlowershell longitudinal weld 101-142B which used the fluenceat0&deg;from Table5-4for36EFPY.Itshouldbenotedthatthefluence projections from Reference 10 arehigherthanthe updated fluence analysis in Reference 12.SeeNote"a." 14 Revision 5 VogtleUnit1-Pressure Temperature Limits Report Soutiiern Nuclear Table 5-6VogtleUnit1 Calculation of theARTValuesfor the3/4TLocation@36 Material RG1.99 R2 Method OF m FF IRTndt^'^ARTndt^'^Margin^^^Intermediate Shell Plate B8805-1 Position 1.1 53.1 0.773 0 41.0 34 75 Intermediate Shell Plate B8805-2 Position 1.1 53.1 0.773 20 41.0 34 95 Intermediate Shell Plate B8805-3 Position 1.1 38.4 0.773 30 29.7 29.7 89 Position 2.1 24.4 0.773 30 18.9 17^r;66 Lower Shell Plate B8606-1 Position 1.1 32.8 0.773 20 25.4 25.4 71 Lower Shell Plate B8606-2 Position 1.1 35.2 0.773 20 27.2 27.2 74 Lower Shell Plate B8606-3 Position 1.1 41.9 0.773 10 32.4 32.4 75 Inter.Shell Longitudinal Weld Seam 101-124A{0''Azimuth)
Position 1.1 34.5 0.622-80 21.5 21.5-37 Position 2.1 8.6 0.622-80 5.3 5.3^^^-69 Inter.ShellLong.Weld Seams 101-124B,C (120'', 240"" Azimuth)Position 1.1 34.5 0.773-80 26.7 26.7-27 Position 2.1 8.6 0.773-80 6.6 6.6^^^-67 Intermediate to Lower Shell Girth Weld Seam 101-171 Position 1.1 34.5 0.773-80 26.7 26.7-27 Position 2.1 8.6 0.773-80 6.6 6.6^^^-67LowerShellLong.Weld Seams 101-142A.C (60&deg;.300''Azimuth)
Position 1.1 34.5 0.773-80 26.7 26.7-27 Position 2.1 8.6 0.773-80 6.6 6.6^'^-67LowerShellLong.Weld Seam (180''Azimuth)
Position 1.1 34.5 0.622-80 21.5 21.5-37 Position 2.1 8.6 0.622-80 5.3 5.3^^^-69 Notes: a.b.0.d.e.f.g-Calculation of ARTvalueswasbasedoncalculatedfluenceprojectionsandmeasureddata fromthepreviouscapsuleanalysisresults (CapsuleV,Ref.10).Itshouldbenotedthatthefluenceprojectionsfrom CapsuleV(Ref.10)werehigherthan those from CapsuleX(Ref.12).However,thechemistryfactorsdeterminedfromsurveillancedata(Table5-2)arenowhigherbutstilllowerthanthe correspondingPosition1.1chemistryfactor.
Therefore, the limiting ARTvaluesfromPlateB8805-2couldnotbe exceededbyanupdatedplateB8805-3ARTvalueorupdatedweldARTvalues.Thus,theoriginal limitingARTvalueisstillvalid.Note,the surveillanceplatedataisnow deemed"Non-Credible,"butthis hasnoimpact basedonthe preceding discussion.
Initial RTndt values are measured values.ARTndt=CF*FFM=2*(ai^+ART=InitialRTndt+ARTndt+Margin (&deg;F);(RoundedperASTME29,usingthe"RoundingMethod").
Weld data deemed credible per References 10 and 12.Plate dataisnow deemed"Non-Credible." SeeNote"a." Neutron Fluence value usedforallmaterialisthe highestvaluefrom Reference 10for36EFPYwith exception to intermediateshelllongitudinalweld 101-124Aandlowershelllongitudinalweld 101-1428 which used the fluenceat0&deg;fromTable5-4for36EFPY.Itshouldbenotedthatthefluenceprojectionsfrom Reference 10 arehigherthanthe updated fluence analysis in Reference 12.SeeNote"a." 15 Revision 5 VogtleUnit1-Pressure Temperature Limits Report Southern Nuclear Table 5-7 Summary of theVogtleUnit1 Reactor VesselBeltlineMaterialART Values Material RG1.99 R2 Method 1/4 ART (&deg;F)3/4 ART (>>F)Intermediate Shell Plate B8805-1 Position 1.1 90 75 Intermediate Shell Plate B8805-2 Position 1.1 110 95 Intermediate Shell Plate B8805-3 Position 1.1 105 89 Position 2.1 73 66 Lower Shell Plate B8606-1 Position 1.1 89 71 Lower Shell Plate B8606-2 Position 1.1 91 74 Lower Shell Plate B8606-3 Position 1.1 88 75 Inter.ShellLongitudinalWeld Seam 101-124A(0&deg;Azimuth)
Position 1.1-18-37 Position 2.1-65-69 Inter.ShellLong.Weld Seams 101-124B,C(120&deg;,240&deg;Azimuth)
Position 1.1-7-27 Position 2.1-62-67 Intermediate to Lower Shell Girth Weld Seam 101-171 Position 1.1-7-27 Position 2.1-62-67LowerShellLong.Weld Seams 101-142A,C(60&deg;,300&deg;Azimuth)
Position 1.1-7-27 Position 2.1-62-67 Lower ShellLong.Weld Seam 101-142B (180&deg;Azimuth)Position 1.1-18-37 Position 2.1-65-69 16 Revision 5 VogtleUnit1-Pressure Temperature Limits Report Soutliern Nuclear Table 5-8 RTpts CalculationsforVogtleUnit1Beltline Region Materialsat36EFPY Material RG1.99 R2 Method CF m Fluence ff(v ARTpts^'>CF)(T)Margin^"*^(T)RTpts^^(T)Intermediate Shell Plate B8805-1 Position 1.1 53.1 2.06 1.197 63.6 0 34 97.6 Intermediate Shell Plate B8805-2 Position 1.1 53.1 2.06 1.197 63.6 20 34 117.6 Intermediate Shell Plate B8805-3 Position 1.1 38.4 2.06 1.197 46.0 30 34 110.0 Position 2.1 37.8 2.06 1.197 45.2 30 34(6)109.2 Lower Shell Plate B8606-1 Position 1.1 32.8 2.06 1.197 39.3 20 34 93.3 Lower Shell Plate B8606-2 Position 1.1 35.2 2.06 1.197 42.1 20 34 96.1 Lower Shell Plate B8606-3 Position 1.1 41.9 2.06 1.197 50.2 10 34 94.2 Inter.Shell Longitudinal Weld Seam 101-124A.B.C Position 1.1 34.5 2.06 1.197 41.3-80 41.3 2.6 Position 2.1 20.8 2.06 1.197 24.9-80 24.9-30.2 Intermediate to Lower Shell Girth Weld Seam 101-171 Position 1.1 34.5 2.06 1.197 41.3-80 41.3 2.6 Position 2.1 20.8 2.06 1.197 24.9-80 24.9-30.2 Lower Shell Long.Weld Seams 101-142A.B.C Position 1.1 34.5 2.06 1.197 41.3-80 41.3 2.6 Position 2.1 20.8 2.06 1.197 24.9-80 24.9-30.2 Notes: 1.FF=fluence factor=f<">2.ARTpts=CF*FF3.Initial RTndt values are measured values.4.M=2*(ai^+5.RTpTs-RTnqj(U)+ARTpxs+Margin (&deg;F)6.Noreliefinthemargintermfortheplate surveillance data since it was deemednotcredible.
17 Revision 5 VogtleUnit1-Pressure Temperature Limits Report Southern Nuclear Table 5-9 RTpts CalculationsforVogtleUnit1BeltlineRegion Materialsat57EFPY Material RG 1.99 R2 Method CF (T)Fluence FF(1)ARTpts<2)(-F)IRTndt(u/^^
(-F)Margin^"*'(T)RTpts^^(<<F)Intermediate Shell Plate B8805-1 Position 1.1 53.1 3.24 1.309 69.5 0 34 103.5 Intermediate Shell Plate B8805-2 Position 1.1 53.1 3.24 1.309 69.5 20 34 123.5 Intermediate Shell Plate 88805-3 Position 1.1 38.4 3.24 1.309 50.3 30 34 114.3 Position 2.1 37.8 3.24 1.309 49.5 30 34^)113.5 Lower Shell Plate B8606-1 Position 1.1 32.8 3.24 1.309 42.9 20 34 96.9 Lower Shell Plate B8606-2 Position 1.1 35.2 3.24 1.309 46.1 20 34 100.1 Lower Shell Plate B8606-3 Position 1.1 41.9 3.24 1.309 54.9 10 34 98.9 Inter.Shell Longitudinal Weld Seam 101-124A.B.C Position 1.1 34.5 3.24 1.309 45.2-80 45.2 10.4 Position 2.1 20.8 3.24 1.309 27.2-80 27.2-25.6 Intermediate to Lower Shell Girth Weld Seam 101-171 Position 1.1 34.5 3.24 1.309 45.2-80 45.2 10.4 Position 2.1 20.8 3.24 1.309 27.2-80 27.2-25.6 Lower ShellLong.Weld Seams 101-142A.B.C Position 1.1 34.5 3.24 1.309 45.2-80 45.2 10.4 Position 2.1 20.8 3.24 1.309 27.2-80 27.2-25.6 Notes: 1.FF=fluence factor=f&deg;">>2.ARTpts=CF*FF3.Initial RTndt values are measured values.iiiiai I NOT v;4.M=2*(01^+5.RTpTs=RTndt(U)ARTpts Margin (&deg;F)6.NoreliefInthemargintermfortheplate surveillance data since it was deemednotcredible.
18 Revision 5 Vogtle Unit1-Pressure Temperature Limits Report Southern Nuclear 6.0 References 1.WCAP-14040-NP-A,Revision4,"Methodology usedtoDevelopCold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," J.D.Andrachek, et.al.2.WCAP-16142-P, Revision 1,"ReactorVesselClosure HeadA/essel Flange RequirementsEvaluationforVogtleUnits1and2,"WarrenBamford,et.al.,February 2004.3.Code of Federal Regulations, 10CFR50,AppendixH, Reactor Vessel Material Surveillance Program Requirements, U.S.Nuclear Regulatory Commission, Washington, D.C.4.WCAP-11011, Georgia Power Company Alvin W.VogtleUnitNo.2 Reactor Vessel Radiation Surveillance Program,L.R.Singer, February 1986.5.ASTM E23 StandardTestMethodNotchedBarImpactTestingof MetallicMaterials,in ASTM Standards, American SocietyforTestingandMaterials,Philadelphia, PA.6.ASME Code CaseN-640,"Alternative Reference Fracture Toughness for DevelopmentofP-T Limit Curves for Section XI, Division 1," February 26,1999.7.Section XI of theASMEBoiler and Pressure Vessel Code,AppendixG, Fracture ToughnessCriteriafor Protection Against Failure.8.ASTM E185-82, AnnualBookofASTM Standards, Section 12, Volume 12.02, Standard Practice for Conducting SurveillanceTestsfor Light-Water Cooled Nuclear Power Reactor Vessels.9.Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor VesselMaterials,U.S.
Nuclear Regulatory Commission, May 1988.10.WCAP-15067, Analysis of CapsuleVFromthe Southern NuclearVogtleElectric Generating PlantUnit1 Reactor Vessel Radiation Surveillance Program, T.J.Laubham,et.al., dated September 1998.[Note thattheTesting/Analysis reports for surveillance capsules U andYfromVogtleUnit1 were documented under WCAP-12256 and WCAP-13931,Rev.1, respectively]
11.CVGRAPH,Hyperbolic Tangent Curve-Fitting Program, Version 5.0.2, developed by ATI Consulting, February 2003.12.WCAP-16278, Analysis of CapsuleXFrom the Southern Nuclear Operating CompanyVogtleUnit1 Reactor Vessel Radiation Surveillance Program,K.G.Knight,et.al., dated July 2004.19 Revisions Vogtle Electric Generating PlantUnit1 Revision 5 Pressure and Temperature Limits ReportUnit2 Revision 5 Pressure and Temperature Limits Report Enclosure 2 Unit 2 PTLR, Revision 5 Southern Nuclear Operating Company Vogtle Unit 2 Pressure Temperature Limits Report Revision 5, March 2014 Vogtle Unit2-Pressure Temperature Limits Report Southern Nuclear Table of Contents List of Tables iiiListof Figures iv 1.0 RCS Pressure Temperature Limits Report (PTLR)1 2.0 Operating Limits 1 2.1 RCS Pressure and Temperature(P/T)Limits(LCO 3.4.3)13.0Cold Overpressure Protection Systems (COPS)(LCO 3.4.12)1 3.1 Pressurizer PORV Setpoints 2 3.2 Arming Temperature 2 4.0 Reactor Vessel Material Surveillance Program 2 5.0 Supplemental Data Tables 3 6.0 References 19 Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear List of TablesTable2-1VogtleUnit2 HeatupLimitsat36EFPY (Without Uncertainties for Instrumentation Errors)6Table2-2VogtleUnit2 Cooldown Limits at36EFPY (Without Uncertainties for Instrumentation Errors)7Table3-1Vogtle Unit2DataPointsfor COPS PORV Setpoints 8Table5-1 ComparisonoftheVogtleUnit2 SurveillanceMaterial30 ft-lb TransitionTemperatureShiftsandUpperShelfEnergy Decreases with Regulatory Guide 1.99, Revision 2, Predictions 10Table5-2CalculationofChemistryFactorsUsing Vogtle Unit2Surveillance Capsule Data 11Table5-3ReactorVessel Beltline Material Unirradiated Toughness Properties forVogtleUnit2 12Table5-4PeakCalculatedNeutronFluenceProjectionsatKey AzimuthalLocationsontheReactorVesselClad/Base Metal Interface for Vogtle Unit 2 (10^n/cm^,E>1.0 MeV)13Table5-5Vogtle Unit2CalculationoftheAdjusted Reference Temperature (ART)Values for the1/4TLocation
@36EFPY 14Table5-6VogtleUnit2CalculationoftheARTValuesforthe3/4TLocation@36EFPY..
15Table5-7 Summary of theVogtleUnit2 Reactor VesselBeltlineMaterialART Values 16Table5-8 RTprsCalculationsfor Vogtle Unit 2 BeltlineRegionMaterialsat36EFPY 17Table5-9 RTrtsCalculationsfor Vogtle Unit 2 BeltlineRegionMaterialsat57EFPY 18 III Revision 5 Vogtle Unit2-Pressure Temperature Limits Report Southern Nuclear List of FiguresFigure2-1VogtleUnit2 Reactor Coolant Systenn Heatup Limitations (Heatup Rate of 100&deg;F/hr)Applicable for theFirst36 EFPY(WithoutMarginsfor Instrumentation Errors)4Figure2-2VogtleUnit2 Reactor Coolant SystemCooldownLimitations (Cooldown Ratesupto 100&deg;F/hr)Applicable for theFirst36EFPY (Without Margins for Instrumentation Errors)5Figure3-1VogtleUnit2MaximumAllowableNominalPORV Setpoints for COPS 9 iv Revision 5 Vogtle Unit2-Pressure Temperature Limits Report Southern Nuclear1.0RCS Pressure Temperature Limits Report (PTLR)ThisPTLRforVogtleUnit2 has been prepared in accordance with the requirements of Technical Specification (TS)5.6.6.The TS addressedinthisreport arelistedbelow:
LCO 3.4.3 RCS Pressure and Temperature(P/T)LimitsLCO3.4.12Cold Overpressure Protection Systems (COPS)Revisions to the PTLR shall be provided to the NRC after issuance.2.0RCS Pressure and Temperature(P/T)Limits(LCO3.4.3)
ThelimitsforTS 3.4.3 are presented in the subsectionswhichfollow and weredevelopedusingthe NRC approved methodology in WCAP-14040, Revision 4'^'with exception of WCAP-16142-P,Revision(eliminationof the flange requirement).
The operability requirements associated with the COPS are specifiedinLCO 3.4.12 and were determined to adequately protect the RCS against brittle fracture in the eventofa cold overpressure transient in accordancewiththemethodologyspecifiedinTS5.6.6.
2.1RCSP/TLimits(LCO 3.4.3)2.1.1Theminimumboltup temperatureis60&deg;F.2.1.2TheRCS temperature rate-of-changelimitsare;a.Amaximum heatup rate of 100&deg;Finany 1-hour period.b.Amaximumcooldownrateof 100&deg;Finany1-hourperiod.c.Amaximum temperature change of lessthanor equal to 10&deg;Finany 1-hourperiodduring inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.2.1.3TheRCSP/Tlimitsfor heatup,cooldown,inservicehydrostaticandleak testing, and criticality are specified by Figures 2-1 and 2-2.3.0 Cold Overpressure Protection Systems (LCO 3.4.12)The setpoints for the pressurizer Power OperatedReliefValves(PORVs) and arming temperature are presented in the subsectionswhichfollow.
These setpoints and arming temperature have been developed using the NRC-approved methodology specified in TS 5.6.6.Revision 5 Vogtle Unit2-Pressure Temperature Limits Report Soutiiern Nuclear 3.1 Pressurizer PORV Setpoints The pressurizer PORV setpoints are specified in Figure 3-1 andTable3-1.Thelimitsfor the COPS setpoints are contained in the36EFPY steady-state curves(Table2-2),which are beltline conditions and are not compensated for pressure differences between the pressurizer transmitter and the reactormidplane/beltlineorforinstrument inaccuracies.
The pressure difference between the pressurizer transmitter and the reactor vessel midplane/beltlinewithfour reactor coolant pumps in operationis74psi.Note: These setpoints include an allowance for the 50&deg;F thermal transport effect for heat injection transients.
A calculation has been performedtoconfirm that the setpoints will maintain the system pressure within the established limits when the pressure difference between the pressure transmitter and reactor midplane and maximum temperature/pressure instrument uncertainties are applied to the setpoints.3.2Arming Temperature COPSshallbe armed whenanyRCScoldleg temperatureis<220&deg;F.4.0 Reactor Vessel Material Surveillance Program The reactor vessel material irradiation surveillance specimens shall be removed and examined to determine changes in material properties.
The removal schedule is provided in UFSAR Table 5.3.1-9.The results of these examinations shall be used to update Figures 2-1, 2-2, and 3-1.Thepressurevesselsteel surveillance program (WCAP-HSSl'"')
is in compliance withAppendixto 10CFR50,"ReactorVesselMaterial Surveillance Program Requirements."Thematerial test requirementsandthe acceptance standardutilizethe reference nil-ductility temperature RTndt,whichis determined in accordancewithASTME23Theempirical relationship between RTndt and the fracture toughness of thereactorvesselsteelisdevelopedinaccordance withCodeCase N-640''ofSection XI of theASMEBoiler and Pressure Vessel Code,AppendixG,"Fracture Toughness Criteria for Protection Against Failure"'^l The surveillance capsule removalschedulemeetsthe requirements of ASTM El 85-82''.The removalscheduleis provided in UFSAR Table 5.3.1-9.Removal of these specimen capsules were completedforUnit2at refueling outage 2R13.Refer to UFSAR paragraph 5.3.1.6.1.4fora description of the external neutron monitoring system also know as external vessel neutron dosimetry system (EVNDS)used following removal of the last specimen capsules.Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear 5.0 Supplemental Data Tables Table 5-1 contains a comparison of measured surveillance material 30 ft-lb transition temperatureshiftsand upper shelf energy decreaseswithRegulatoryGuide 1.99, Revision 2^', predictions.Table5-2 showscalculationsofthesurveillancematerialchemistryfactorsusing surveillance capsuledata.Notethatinthecalculationofthesurveillanceweldchemistryfactor,theratio procedurefromRegulatoryGuide 1.99,Revision2 wasfollowed.Theratioin question is equal to 1.19.Table5-3 provides the requiredVogtleUnit2 reactor vessel toughness data.Table5-4providesa summaryofthefluence valuesusedinthe generationofthe heatup and cooldown limit curves and the PTS evaluation.Table5-5and5-6showthecalculationofthe1/4Tand3/4Tadjusted reference temperature at36EFPYfor each beltline material in theVogtleUnit2 reactor vessel.The limitingbeltlinematerial was thelowershellplate R8-1.Table5-7providesasummaryofthe adjusted reference temperature (ART)valuesof the VogtleUnit2 reactor vessel beltline materials at the 1/4T and 3/4T locationsfor36 EFPY.Table5-8 provides RTrts valuesforVogtleUnit2at36EFPY.Table5-9 provides RTrts valuesforVogtleUnit2at57EFPY.
Revision 5 VogtleUnit2-Pressure Temperature Limits Report MATERIAL PROPERTY BASIS Limiting Material: Lower Shell Plate R8-1LimitingART Values at 36 EFPY:1/4T, 120&deg;F 3/4T, 107&deg;F 2500 Leakiest Limit Unacceptable Operation Heatup Rate 60Deg.F/Hr Soutliern Nuclear Acceptable Operation 52 CO&#xa3;3 (0 (0 p Critica Limit 60Deg.F/Hr T3 s<<3 O re O Heatup Rate 100Deg.F/Hr Critical Limit 100Deg.F/HrCriticaiityLimit based on inservice iiydrostatic test temperature (ISCF)fortiie service period up to36EFPY Tiie lower iimt for RCS pressureis-14.7 psig 0 50 100 150 200 250 300 350 400 450500550 Moderator Temperature(Deg.F)Figure2-1VogtleUnit2 Reactor Coolant System Heatup Limitations (Heatup Rate of 100T/hr)Applicable for the First36EFPY (Witiiout Margins for Instrumentation Errors)(Plotted Data provided on Table 2-1)Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear MATERIAL PROPERTY BASIS Limiting Material: Lower Shell Plate R8-1LimitingART Values at36EFPY:1/4T, 120&deg;F 3/4T, 107&deg;F 52 (0&#xa5;3 (A (0&#xa3;Q. a 3 O (0 O 2500 2250 2000 1750 1500 1250 1000 750 500 250 0 Una iccept M m able wpciaiiuii Acceptable Operation Cooldown Rates,&deg;F/Hi steady-stat 40*60-100 r e 1 03 H 1 1 altup imoeratun 8, eo'F The lower limit for RCS pressure is-14.7 psig 0 50 100 150 200 250300350 400 450 500 550 Moderator Temperature(Deg.F)Figure 2-2 Vogtle Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100T/hr)Applicable for the First 36 EFPY (Without Margins for Instrumentation Error)(Plotted Data provided on Table 2-2)Revision 5 VogtleUnit2-Pressure Temperature Limits Report Table 2-1 VogtleUnit2 Heatup Limits at 36 EFPY (Without Uncertainties for Instrumentation Errors)Southern Nuclear 60&deg;F/hr Heatup 60F/hr Heatup 100F/hr Heatup 100F/hr Heatup Leak Test Limit Criticality Limit Criticality Limit T 1 P T 1 P T 1 P T 1 P Q.1-60-14.7 180-14.7 60-14.7 180-14.7 163 2000 60 717 180 734 60 684 180 684 180 2485 65 717 180 727 65 684 180 684 70 717 180 720 70 684 180 684 75 717 180 717 75 684 180 684 80 717 180 717 80 684 180 684 85 717 180 721 85 684 180 684 90 721 180 729 90 684 180 684 95 729 180 739 95 684 180 684 100 739 180 753 100 684 180 686 105 753 180 769 105 686 180 691 110 769 180 788 110 691 180 699 115 788 180 811 115 699 180 709 120 811 180 837 120 709 180 722 125 837 180 866 125 722 180 737 130 866 180 899 130 737 180 756 135 899 180 936 135 756 180 777 140 936 185 977 140///185 801 145 977 190 1023 145 801 190 829 150 1023 195 1074 150 829 195 860 155 1074 200 1130 155.860 200 896 160 1130 205 1193 160 896 205 935 165 1193 210 1262 165 935 210 979 170 1262 215 1339 170 979 215 1029 175 1339 220 1424 175 1029 220 1084 180 1424 225 1517 180 1084 225 1144 185 1517 230 1621 185 1144 230 1212 190 1621 235 1735 190 1212 235 1287 195 1735 240 1861 195 1287 240 1369 200 1861 245 2000 200 1369 245 1461 205 2000 250 2154 205 1461 250 1562 210 2154 255 2324 210 1562 255 1673 215 2324 215 1673 260 1796 220 1796 265 1932 225 1932 270 2082 230 2082 275 2248 235 2248 280 2430 240 2430 Revision 5 VogtleUnit2-Pressure TemperatureLimitsReport Table 2-2VogtleUnit2 Cooldown Limits at 36 EFPY (Without Uncertainties for Instrumentation Errors)Southern Nuclear Steady State 20F/hr 40F/hr 60&deg;F/hr 100&deg;F/hr T 1 P T 1 P T 1 P T 1 P T 1 P 60-14.7 60-14.7 60-14.7 60-14.7 60-14.7 60 722 60 681 60 640 60 599 60 518 65 734 65 694 65 654 65 614 65 537 70 747 70 708 70 670 70 632 70 557 75 762 75 724 75 687 75 651 75 581 80 778 80 742 80 706 80 672 80 606 85 796 85 761 85 728 85 695 85 635 90 816 90 783 90 752 90 721 90 667 95 838 95 807 95 778 95 750 95 703 100 862 100 833 100 807 100 782 100 742 105 889 105 863 105 839 105 818 105 786 110 918 110 895 110 875 110 858 110 834 115 951 115 931 115 914 115 901 115 888 120 987 120 971 120 958 120 950 120 948 125 1027 125 1015 125 1007 125 1003 130 1071 130 1063 130 1060 135 1120 135 1117 140 1173 145 1233 150 1299 155 1371 160 1452 165 1541 170 1639 175 1747 180 1867 185 2000 190 2146 195 2308 Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear Table 3-1 Vogtle Unit2DataPointsforthe Maximum Allowable NominalCOPSPORVSetpoints Temperature (Deg.F)PORV Setpoint (psig)70 580 90 580 140 612 201 760 202 760 350 760 Revision 5 VogtleUnit2-Pressure TemperatureLimitsReport Southern Nuclear CO Q-O UJ CO o CL LLI 900 850 800 750 700 CD 650<O-I<600 550<500 o 450 (201,760)i i 1///(70.58(I)i 400 0 50100150200250 300AUCTIONEEREDLOWMEASUREDRCSTEMPERATURE(DEGF) 350 Figure 3-1: Vogtle Unit 2 Maximum Allowable Nominal PORV Setpoints for COPS Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear Comparison of theVogtleUnit Upper Shelf Energy Table 5-1 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Decreases with Regulatory Guide 1.99, Revision 2, Predictions 30 ft-lb Transition Temperature Shift Upper Shelf Energy Decrease Material Capsule Fluence (X 10^n/cm^^Predicted (OF)(a)Measured (OF)(b)Predicted (%)Measured Lower Shell Plate B8628-1''(Longitudinal)
U 0.356 22.2 2.0 15 0 Y 1.12 31.9 5.8 19.5 0 X 1.78 36.0 29.4 22 3 W 2.98 40.0 39.0 25 6 Lower Shell Plate B8628-1<'(Transverse) u 0.356 22.2 0.0^&deg;^15 0 Y 1.12 31.9 1.9 19.5 0 X 1.78 36.0 29.8 22 7 w 2.98 40.0 45.5 25 1 Weld Metal'" u 0.356 26.0 0.00^&deg;^15 0 Y 1.12 37.5 18.7 19.5 7 X 1.78 42.2 19.9 22 7 w 2.98 47.0 31.4 25 5 HAZ Metal u 0.356-0.00^&deg;^0 Y 1.12-0.00^&deg;^-0 X 1.78-0.00^&deg;^-7 w 2.98...3.2-6 Notes: a.b.c.d.e.f.BasedonRegulatoryGuide 1.99,Revision2,methodologyusingthemeanweightpercentvaluesofcopperand nickel of the surveillance material.Calculated using measured Charpy dataplottedusingCVGRAPH,Version Valuesarebasedonthe definitionofuppershelf energy given in ASTM E185-82^lActualvaluesfor ARTndtare-7.1(Plate),-17.3(Weld).-24.3 (HAZ Cap.U),-10.1(HAZCap.Y)and-2.5 (HAZ Cap.X).Thisphysicallyshouldnotoccur,thereforeforconservatismavalueofzero willbereported (I.e.,No Change in T30).The heat numberforlowershell plateB8628-1is C-3500-2.The SurveillanceweldwasfabricatedfromWireHeatNo.87005,FluxTypeLinde 124,FluxLotNo.
1061.10 Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear Table 5-2CalculationofChemistry FactorsusingVogtleUnit2 Surveillance Capsule Data Material Capsule Capsule FF^^)ARTndt'"'FF*ARTndt FF^Lower Shell*''Plate B8628-1 (,Longitudina\)
U 0.356 0.715 2.0 1.43 0.511 Y 1.12 1.03 5.8 5.97 1.06 X 1.78 1.16 29.4 34.10 1.35 W 2.98 1.29 39.0 50.31 1.66 Lower Shell*" Plate B8628-1{Transverse) u 0.356 0.715 0.0^^0.00 0.511 Y'1.12 1.03 1.9 1.96 1.06 X 1.78 1.16 29.8 34.57 1.35 w 2.98 1.29 45.5 58.70 1.66 SUM: 187.04 9.162 CFb8628.i=Z(FF*RTndt)1-S(FF')=(187.04)+(9.162)=20.4F Surveillance Weld Material^^^(Heat 87005)U 0.356 0.715 0.0^^0.00 0.511 Y 1.12 1.03 22.25(^8.22.92 1.06 X 1.78 1.16 23.68(19.9^^
27.47 1.35 W 2.98 1.29 37.37(31.4)^&deg;^
48.21 1.66 SUM: 98.60 4.581 CFsurv.we.d
=I(FF*RW)Z(FF^)=(98.60)4-(4.581)=21.5&deg;F Notes:a.f=Calculated fluence from capsule Wdosimetry analysis results'''^',{x 10^n/cm^,E>1.0 MeV).b.FF=fluencefactor=
f*"^'**.c.ARTndtvaluesarethe measured 30 ft-lbshiftvaluestakenfromApp.CofRef.12.d.Thesurveillanceweldmetal ARTndtvalueshavebeenadjustedbyaratiofactorof1.19.e.Actual valuesforARTndtare-7.1(Plate)and-17.3(Weld).Thisphysicallyshouldnotoccur;thereforefor conservatism a value of zero will be used.f.The heat numberforlowershellplateB8628-1isC-3500-2.g.SurveillanceWeldwasfabricatedfromWireHeatNo.87005,FluxTypeLinde124,FluxLotNo.1061.
11 Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear Table 5-3 ReactorVesselBeltlineMaterialUnirradiated Toughness PropertiesforVogtle Unit 2 Material Description Cu (%)Ni(%)Initial RTndt^'Closure Head Flange R7-1{Heat#125L630VA1)
-0.72 10T Vessel Flange R1-1-0.87-60&deg;F Intermediate Shell Plate R4-1 (Heat#0-3527-1) 0.07 0.63 10&deg;F Intermediate Shell Plate R4-2 (Heat#0-3527-2) 0.06 0.61 10&deg;F Intermediate Shell Plate R4-3 (Heat#0-3552-1) 0.05 0.60 30&deg;F Lower Shell Plate B8825-1 (Heat#0-3500-1) 0.06 0.62 40&deg;F Lower Shell Plate R8-1 (Heat#0-4304-1)0.07 0.63 40&deg;F Lower Shell Plate B8628-1 (Heat#0-3500-2) 0.05 0.59 IntermediateShellLongitudinalWeld Seams 101-124A, B&C 0.05 0.15-10&deg;FLowerShellLongitudinalWeld Seams 101-142A.B&C 0.05 0.15-10&deg;F Intermediate to Lower Shell Plate Circumferential Weld Seam 101-171 0.05 0.15-30&deg;F Surveillance Weld^&deg;^0.04 0.13-Notes:a.The initial RTndt valuesforthe platesandwelds are based on measured data.b.TheweldmaterialintheVogtleUnit2surveillanceprogramwas madeofthe samewireandflux asthereactor vesselintermediatetolowershellgirth seamweld(101-171).
Theseweldswerefabricatedusingweldwire heatno.87005,Linde 124Flux,lotno.1061.Theintermediateshelllongitudinalweld seams(101-124A,B,C)andthelowershelllongitudinalweld seams (101-142A,B,C) were fabricatedusingweldwire heat no.87005,Linde0091Flux,lotno.0145.
Hence the surveillanceweldis representativeofall beltline welds.12 Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear Table 5-4 Peak Calculated Neutron Fluence ProjectionsatKeyAzimuthalLocationsonthe ReactorVesselClad/Base MetalInterfacefor Vogtle Unit 2 (n/cm^,E>1.0 MeV)Azimuthal Location EFPY 016&deg;30&deg;45&deg;13.29(a)4.01E+18 5.91E+18 7.02E+18 7.20E+18 14.59 4.42E+18 6.52E+18 7.70E+18 7.87E+18 32.00 9.87E+18 1.46E+19 1.69E+19 1.70E+19 40.00 1.24E+19 1.84E+19 2.12E+19 2.11E+19 48.00 1.49E+19 2.21E+19 2.54E+19 2.53E+19 54.00 1.68E+19 2.49E+19 2.86E+19 2.85E+19(a)Theendofcycle 10(Actual)when Capsule"W" was withdrawn.
13 Revision 5 VogtleUnit2-Pressure TemperatureLimitsReport Southern Nuclear Table 5-5VogtleUnit2CalculationoftheARTValuesforthe1/4TLocation@36 Material RG1.99 R2 Method CF m FF IRTndt^'^ARTndt^'^Margin*"'ART*'Intermediate Shell Plate R4-1 Position 1.1 44.0 1.051 10 46.2 34 90 Intermediate Shell Plate R4-2 Position 1.1 37.0 1.051 10 38.9 34 83 Intermediate Shell Plate R4-3 Position 1.1 31.0 1.051 30 32.6 32.6 95 Lower Shell Plate B8825-1 Position 1.1 37.0 1.051 40 38.9 34 113 Lower Shell Plate R8-1 Position 1.1 44.0 1.051 40 46.2 34 120 Lower Shell Plate B8628-1 Position 1.1 31.0 1.051 50 32.6 32.6 115 Position 2.1 12.9 1.051 50 13.6 13.6^'^77 IntermediateShellLongitudinal Weld Seams 101-124A.B, C Position 1.1 43.3 1.051-10 45.5 45.5 81 Position 2.1 16.7 1.051-10 17.6 17.6^'^25 Lower Shell Longitudinal Weld Seams 101-142A.B.C Position 1.1 43.3 1.051-10 45.5 45.5 81 Position 2.1 16.7 1.051-10 17.6 17.6^^^25 Intermediate to Lower Shell Circ, Weld Seam 101-171 Position 1.1 43.3 1.051-30 45.5 45.5 61 Position 2.1 16.7 1.051-30 17.6 17.6^'^5 Notes: a.b.c.d.e.f.g-Calculation of ARTvalueswasbasedoncalculatedfluence projectionsandmeasureddata fromtheprevious capsuleanalysisresults(CapsuleX, Ref.10).Itshouldbenotedthatthefluenceprojections fromCapsuleX (Ref.10)werehigherthanthosefromCapsuleW(Ref.
12).However,thechemistryfactorsdeterminedfromsurveillancedata(Table5-2)arenowhigher,but stilllowerthanthecorresponding Position1.1chemistryfactor.Therefore,the limitingARTvalues from Plate R8-1couldnotbe exceededbyanupdatedplate B8628-1 ARTvalueor updatedweldARTvalues.Thus,theoriginal limitingARTvalueisstillvalid.
Initial RTndt values are measured values.ARTnqt=CF*FF M=2'(Oi'+ART=Initial RTndt+ARTndt+Margin (&deg;F);(Roundedper ASTME29,usingthe"Rounding Method").Data deemed credible per References 10 and 12.Neutron Fluencevalueusedforallmaterialisthe highestvaluefrom Reference 10for36EFPY.ItshouldbenotedthatthefluenceprojectionsfromReference 10arehigherthantheupdatedfluenceanalysisinReference 12.See Note"a." 14 Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear Table 5-6VogtleUnit2CalculationoftheARTValuesforthe3/4TLocation@36 Material RG1.99 R2 Method CF m FF IRTnd/&deg;^ARTndt Margin^"'ART^^Intemriedlate Shell Plate R4-1 Position 1.1 44.0 0.763 10 33.6 33.6 77 Intermediate Shell Plate R4-2 Position 1.1 37.0 0.763 1028.228.2 66 Intermediate Shell Plate R4-3 Position 1.1 31.0 0.763 30 23.7 23.7 77 Lower Shell Plate B8825-1 Position 1.1 37.0 0.763 40 28.2 28.2 96 Lower Shell Plate R8-1 Position 1.1 44.0 0.763 40 33.6 33.6 107 Lower Shell Plate B8628-1 Position 1.1 31.0 0.763 50 23.7 23.7 97 Position 2.1 12.9 0.763 50 9.8 9.8^'^70 IntermediateShellLongitudinal Weld Seams 101-124A,B.C Position 1.1 43.3 0.763-10 33,0 33.0 56 Position 2.1 16.7 0.763-10 12.7 12.7^'^15 Lower Shell Longitudinal Weld Seams 101-142A,B.C Position 1.1 43.3 0.763-10 33.0 33.0 56 Position 2.1 16.7 0.763-10 12.7 12.7^^^15 Intermediate to Lower Shell Circ.Weld Seam 101-171 Position 1.1 43.3 0.763-30 33.0 33.0 36 Position 2.1 16.7 0.763-30 12.7 12.7^^^-5 Notes: a.b.c.d.e.f.g-CalculationofARTvalueswas basedoncalculatedfluenceprojectionsand measureddatafromtheprevious capsuleanalysisresults(CapsuleX,Ref.
10).ItshouldbenotedthatthefluenceprojectionsfromCapsuleX (Ref.10)werehigherthanthose fromCapsuleW(Ref.
12).However,thechemistryfactorsdetermined fromsurveillancedata(Table5-2)arenow higher, but stilllowerthanthecorresponding Position1.1chemistry factor.Therefore,the limitingARTvalues from Plate R8-1couldnotbeexceededbyanupdatedplate B8628-1 ARTvalueorupdatedweldARTvalues.Thus,theoriginal limitingARTvalueisstillvalid.
Initial RTndt values are measured values.ARTndt=CF*FFM=2*(01^+ART=Initial RTndt+ARTndt+Margin (&deg;F);(Roundedper ASTME29,usingthe"Rounding Method").Data deemed credible per References 10 and 12.Neutron Fluence value usedforallmaterialisthe highestvaluefrom Reference 10for36EFPY.It should benotedthatthefluenceprojectionsfromReference 10arehigherthantheupdatedfluenceanalysisin Reference 12.See Note"a." 15 Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear Table 5-7 Summary of theVogtleUnit2 Reactor VesselBeltlineMaterialART Values Material RG1.99 R2 Method 1/4 ART m 3/4 ART Intermediate Shell Plate R4-1 Position 1.1 90 71 Intermediate Shell Plate R4-2 Position 1.1 83 66 Intermediate Shell Plate R4-3 Position 1.1 95 77 Lower Shell Plate B8825-1 Position 1.1 113 96 Lower Shell Plate R8-1 Position 1.1 120 107 Lower Shell Plate B8628-1 Position 1.1 115 97 Position 2.1 77 70 IntermediateShellLongitudinal Weld Seams 101-124A.B.C Position 1.1 81 56 Position 2.1 25 15LowerShell Longitudinal Weld Seams 101-142A, B, C Position 1.1 81 56 Position 2.1 25 15 Intermediate to Lower Shell Giro.Weld Seam 101-171 Position 1.1 61 36 Position 2.1 5-5 16 Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear Table 5-8 RTpts CalculationsforVogtleUnit2BeltlineRegion Materialsat36EFPY Material RG L99 R2 Method CF rn Flueace arW (^F)rF)Margin*'rF)RW rF)Intermediate Shell Plate R4-I Pi>S)lton I.I 44.0 1.93 1.18 51.9 10 34 95.9 Intermediate Shell Plate R4-2 Position 1.1 37.0 1.93 1.18 4.V7 10 34 87.7 Intermediate Shell Plate R4-3 Position I.I 31.0 1.93 1.18 36.6 30 34 100.6 Lower Shell Plate B8825-I Position l.l 37.0 1.93 1.18 43.7 40 34 117.7 i Lower Shell PlalcR8-l Position 1.1 44.0 1.93 1.18 51.9 40 M 125.9 Lower Shell Plate B8628-I Position 1.1 31.0 1.93 1.18.%.6 50.34 120.6 Position 2.1 20.4 1.93 1.18 24.1 50 17 91.1 Imer.Shell Longitudinal Weld Scam I0I.I24A3.C Position l.l 43.3 1.93 1.18 51.1-10 51.1 92.2 Position 2.1 21.5 1.93 1.18 25.4-10 25.4 40.8 Intcrmcdiaie lo Lower Shell Girth Weld Seam I0M7I Position l.l 43.3 1.93 I.I8 51.1-30 51.1 72.2 Position 2.1 21.5 L93 1.18 25.4-30 25.4 20.8 Lower Shell Umg.Weld Seam I0M42A,B,C Position l.l 43.3 1.93 1.18 51.1-10 51.1 92.2 Pasition 2.1 21.5 1.93 1.18 25.4-10 25.4 40.8 Notes: 1.flucncc faaor=f 2.ARJpk=CF-FF 3.Initial RTkot values are measured values 4.M=2+Oa")"'5.l^ris~R^nukw ARTl'l\-f Mai^n (F)17 Revision 5 VogtleUnit2-Pressure Temperature Limits Report Southern Nuclear Table 5-9 RTpTs CalculationsforVogtleUnit2BeltlineRegionMaterialsat57EFPY Material RG 1.99 R2 Metliod CF rn Fluence jylf.ARTpts^^>>CF)IRTNDT.t,'-''
CF)Margin^''Cf)RW^F)Inicrmcdiaic Shell Plate R4.1 Position LI 44.0 3.06 L295 57.0 10 34 10 LO Intermediate Shell Plate R4-2 Position I.I 37.0 3.06 1.295 47.9 10 34 91.9 Intermediate Shell Plate Position LI 31.0 3.06 1.295 40.1 30 34 104.1 Lower Shell Plate B8825-I Position LI 37.0 3.06 1.295 47.9 40 34 121.9 Lower Shell Plate R8-I Position LI 44.0 3.06 L295 57.0 40 34 131.0 Lower Shell Plate B8628-I Position LI 31.0 3.06 1.295 40.1 50 34 124.1 Position 2,1 20.4 3.06 1.295 26.4 50 17 93.4 Inter.Shell Longitudinal Weld Seam I0I-124A.B,C Position LI 43.3.3.06 1.295 56.1-10 56 102.1 Position 2.1 21.5 3.06 L295 27.x-10 27.8 45.6 Intermediate to Lower Shell Girth Weld Seam 101-171 Position Li 43.3 3.06 L295 56.1-30 56 1 82.1 Position 2.1 21.5 3.06 1.295 27.8-30 27.8 I 25.6 Lower Shell Long.Weld Seam 10I-142A,B,C Position LI 43.3 3.06 1.295 56.1-10 56 102.1 Pasition 2.1;21.5 3.06 1.295 27.8-10 27.8 45.6 Notes: 1.FF=nucnccfactOf 2.ARTm=CF'FF 3.Initial RTsnrvaluesare measured values 4.M=2*(0r+0^V'^
5.RTl>>js=RTnutiuj ARTi'is Margin (F)18 Revision 5 Vogtle Unit2-Pressure Temperature Limits Report Southern Nuclear 6.0 References 1.WCAP-14040-NP-A,Revision4,"Methodology usedtoDevelopCold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves", J.D.Andrachek, et.al.2.WCAP-16142-P,Revision1,"ReactorVesselClosure HeadA/essel Flange Requirements EvaluationforVogtleUnits1 and 2", Warren Bamford,et.al., February 2004.3.Code of Federal Regulations, 10CFR50, Appendix H, Reactor Vessel Material Surveillance Program Requirements, U.S.Nuclear Regulatory Commission, Washington, D.C.4.WCAP-11381, Georgia Power Company Alvin W.VogtleUnitNo.2 Reactor Vessel Radiation Surveillance Program,L.R.Singer, April 1986.5.ASTM E23 StandardTestMethod Notched BarImpactTestingofMetallicMaterials,inASTM Standards, American SocietyforTestingandMaterials, Philadelphia, PA.6.ASME Code CaseN-640,"Alternative Reference Fracture Toughness for DevelopmentofP-T Limit Curves for Section XI, Division 1," February 26,1999.7.Section XI of theASMEBoiler and Pressure Vessel Code,AppendixG, Fracture ToughnessCriteriafor Protection Against Failure.8.ASTM E185-82,AnnualBookofASTM Standards, Section12,Volume12.02, Standard Practice for Conducting SurveillanceTestsfor Light-Water Cooled Nuclear Power Reactor Vessels.9.Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, U.S.Nuclear Regulatory Commission, May 1988.10.WCAP-15159, Analysis of CapsuleXFromthe Southern NuclearVogtleElectric Generating PlantUnit2 Reactor Vessel Radiation Surveillance Program,T.J.Laubham,et.al., dated March 1999.[Note that the Testing/Analysis reports for surveillance capsules U andYfromVogtleUnit2 were documented under WCAP-13007 and WCAP-14532, respectively]
11.CVGRAPH, Hyperbolic Tangent Curve-Fitting Program, Version 5.0.2 developed by ATI Consulting, February 2003.12.WCAP-16382, Analysis of Capsule W From the Southern Nuclear Operating CompanyVogtleUnit2 Reactor Vessel Radiation Surveillance Program, T.J.Laubham,et.a!., dated January 2005.19 Revision 5}}