ML14351A427

000N2528-SRLR, Revision 1, Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988 Mwt) / MELLLA (99-105% Flow).

ML14351A427
Person / Time
Site:	Nine Mile Point
Issue date:	01/31/2014
From:	Global Nuclear Fuel
To:	Office of Nuclear Reactor Regulation
References
NMP2L 2568 000N2528-SRLR, Rev. 1
Download: ML14351A427 (66)

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ATTACHMENT 2SUPPLEMENTAL RELOAD LICENSING REPORT FORNINE MILE POINT 2, RELOAD 14 CYCLE 15,EXTENDED POWER UPRATE (3988 MWT) / MELLLA (99-105 % FLOW)Nine Mile Point Nuclear Station, LLCDecember 11, 2014 GNFGlobal Nuclear FuelA Joint Venture of GE, Toshiba, & Hitachi000N2528-SRLRRevision 1Class IJanuary 2014Supplemental Reload Licensing ReportforNine Mile Point 2Reload 14 Cycle 15Extended Power Uprate (3988 MWt) / MELLLA (99-105% Flow)Copyright 2014 Global Nuclear Fuel-Americas, LLCAll Rights Reserved Nine Mile Point 2 000N2528-SRLRReload 14 Revision 1Important Notice Regarding Contents of This ReportPlease Read CarefullyThis report was prepared by Global Nuclear Fuel -Americas, LLC (GNF-A) solely for use by Nine MilePoint Nuclear Station, LLC ("Recipient") in support of the operating license for Nine Mile Point 2 (the"Nuclear Plant"). The information contained in this report (the "Information") is believed by GNF-A tobe an accurate and true representation of the facts known by, obtained by or provided to GNF-A at thetime this report was prepared.The only undertakings of GNF-A respecting the Information are contained in the contract betweenRecipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") andnothing contained in this document shall be construed as amending or modifying the Fuel Contract. Theuse of the Information for any purpose other than that for which it was intended under the Fuel Contract,is not authorized by GNF-A. In the event of any such unauthorized use, GNF-A neither (a) makes anyrepresentation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness ofthe Information or that such unauthorized use may not infringe privately owned rights, nor (b) assumesany responsibility for liability or damage of any kind which may result from such use of suchinformation.The content of this SRLR will only serve the licensing of Nine Mile Point 2 Cycle 15 EPU/MELLLA.Page 2 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1AcknowledgementThe engineering and reload licensing analyses, which form the technical basis of this SupplementalReload Licensing Report, were performed by GNF-A/GEH Nuclear Analysis personnel. TheSupplemental Reload Licensing Report was prepared by M. Thomas. This document has been verified byR. McCord.Page 3 Nine Mile Point 2 000N2528-SRLRReload 14 Revision 1Table of Contents1. Plant Unique Items 52. Reload Fuel Bundles 53. Reference Core Loading Pattern 64. Calculated Core Effective Multiplication and Control System Worth 65. Standby Liquid Control System Shutdown Capability 66. Reload Unique Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters 77. Selected Margin Improvement Options 98. Operating Flexibility Options 109. Core-wide AOO Analysis Results 1110. Rod Withdrawal Error AOO Summary 1411. Cycle SLMCPR and OLMCPR Summary 1512. Overpressurization Analysis Summary 1713. Fuel Loading Error Results 1714. Control Rod Drop Analysis Results 1715. Stability Analysis Results 1816. Loss-of-Coolant Accident Results 22Appendix A Analysis Conditions 47Appendix B Thermal-Mechanical Compliance 48Appendix C Decrease in Core Coolant Temperature Event 49Appendix D Off-Rated Limits 50Appendix E Expanded Operating Domain Analysis 56Appendix F TRACG04 AOO Supplementary Information 58Appendix G Interim Methods LTR (NEDC-33173P-A Revision 4) Supplemental Information 59Appendix H List of Acronyms 62Page 4 Nine Mile Point 2Reload 14000N2528-SRLRRevision IThe basis for this report is General Electric Standard Application for Reactor Fuel, NEDE-240 11-P-A-20, December 2013; and the U.S. Supplement, NEDE-2401 1-P-A-20-US, December 2013.A proprietary Fuel Bundle Information Report (FBIR) supplements this licensing report. The FBIRspecifies the thermal-mechanical linear heat generation rate limits and also provides a description of thefuel bundles to be loaded. The document number for this report is 000N0123-FBIR.1. Plant Unique ItemsAppendix A:Appendix B:Appendix C:Appendix D:Appendix E:Appendix F:Appendix G:Appendix H:Analysis ConditionsThermal-Mechanical ComplianceDecrease in Core Coolant Temperature EventOff-Rated LimitsExpanded Operating Domain AnalysisTRACG04 AOO Supplementary InformationInterim Methods LTR (NEDC-33173P-A Revision 4) Supplemental InformationList of Acronyms2. Reload Fuel BundlesCycle NumberFuel Type LoadedIrradiated:GE 14-P 1OCNAB434-8G7.0/7G6.0-120T- 150-T6-3233 (GE14C) 13 80GE14-Pl0CNAB416-17GZ-120T-150-T6-3235 (GE14C) 13 12GE 14-P 1OCNAB417-17GZ- 120T- 150-T6-3236 (GE 14C) 13 4GE 14-PIOCNAB434-15GZ-120T-150-T6-4039 (GE 14C) 14 120GE 14-P 1OCNAB422-17GZ- 120T- 150-T6-4041 (GE 14C) 14 60GE 14-P0OCNAB412-15GZ-120T-1 50-T6-4040 (GE14C) 14 104GE 14-P 1OCNAB422-17GZ- 120T- 150-T6-4042 (GE 14C) 14 32GE 14-P 1 OCNAB412-14GZ- 1 20T- 1 50-T6-4043 (GE 14C) 14 16New:GE 14-P 1 OCNAB422-16GZ- 1 20T- 1 50-T6-4244 (GE 14C) 15 64GE 14-P 10CNAB418-16GZ- 120T- 150-T6-4243 (GE14C) 15 56GE 14-P1OCNAB419-17GZ- 120T- 150-T6-4242 (GE14C) 15 96GE14-P1OCNAB418-15GZ-120T-150-T6-4241 (GEI4C) 15 56GE 14-P I OCNAB430-14GZ- 120T- 1 50-T6-4240 (GE 1 4C) 15 40GE14-P1OCNAB430-15GZ-120T-150-T6-4239 (GE14C) 15 24Total: 1 764Page 5 Nine Mile Point 2Reload 14000N2528-SRLRRevision 13. Reference Core Loading PatternCore Average Cycle ExposureExposure34134 MWd/MT 18164 MWd/MTNominal previous end-of-cycle exposure: (30966 MWd/ST) (16478 MWd/ST)Minimum previous end-of-cycle exposure (for cold 33583 MWd/MT 17613 MWd/MTshutdown considerations): (30466 MWd/ST) (15978 MWd/ST)14094 MWd/MT 0 MWd/MTAssumed reload beginning-of-cycle exposure: (12786 MWd/ST) (0 MWdIST)Assumed reload end-of-cycle exposure (rated 33032 MWd/MT 18938 MWd/MTconditions): (29966 MWd/ST) (17180 MWd/ST)Reference core loading pattern: Figure 14. Calculated Core Effective Multiplication and Control System WorthBeginning of Cycle, keffectiveUncontrolled (20'C) 1.132Fully controlled (20'C) 0.959Strongest control rod out (most reactive condition, 20'C) 0.989R, Maximum increase in strongest rod out reactivity during the cycle (Ak) 0.0000 MWd/MTCycle exposure at which R occurs (0 MWd/ST)5. Standby Liquid Control System Shutdown CapabilityBoron (ppm) Shutdown Margin (Ak)(at 20'C) (at 1601C, Xenon Free)Analytical Requirement Achieved780 >0.010 0.019Page 6 Nine Mile Point 2I'A000N2528-SR.LRRP~vicnn 16. Reload Unique Anticipated Operational Occurrences (AOO) Analysis Initial ConditionParameters 1Operating domain: ICF (HBB)Exposure range : BOC to MOC (Application Condition: 1, 3 )Peaking FactorsFuel Bundle Bundle InitialDesign Local Radial Axial R-Factor Power FlowDesign___ _(MWt) (1000 lb/hr) MCPRGE14C 1.0 1.36 1.27 0.98 7.071 126.5 1.59Operating domain: ICF (HBB)Exposure range : MOC to EOC (Application Condition: 1, 3)Exposure range : BOC to EOC (Application Condition: 2 )Peaking FactorsFuel Bundle Bundle InitialLocal Radial Axial R-Factor Power FlowDesign 1. .3(MWt) (1000 lb/hr) MCPRGE14C 1.0 1.37 1.42 0.97 7.147 128.1 1.51Operating domain: LCF (HBB)Exposure range : BOC to MOC (Application Condition: 1, 3)Peaking FactorsFuel Bundle Bundle InitialDesign Local Radial Axial R-Factor Power FlowRaias129 0.7 (MWt) (1000 lb/hr) MCPRGE14C 1.0 1.36 1.29 0.97 7.065 100.8 1.48Operating domain: LCF (HBB)Exposure range : MOC to EOC (Application Condition: 1, 3)Exposure range : BOC to EOC (Application Condition: 2 )Peaking FactorsFuel Bundle Bundle InitialLocal Radial Axial R-Factor Power FlowDesign I .(MWt) (1000 lb/hr) MCPRGE14C 1.0 1.38 1.34 0.98 7.217 100.8 1.381 Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.Page 7 Nine Mile Point 2V 1 1,A000N2528-SR-LRPiAXAC~n IOperating domain: ICF (UB)Exposure range : MOC to EOC (Application Condition: 1, 3)Exposure range : BOC to EOC (Application Condition: 2 )Peaking FactorsFuel Bundle Bundle InitialLocal Radial Axial R-Factor Power FlowDesign 1.28 (MWt) (1000 lb/hr) MCPRGE14C 1.0 1.28 1.26 0.97 6.674 129.4 1.73Operating domain: LCF (UB)Exposure range : MOC to EOC (Application Condition: 1, 3)Exposure range_: BOC to EOC (Application Condition: 2)Peaking FactorsFuel Bundle Bundle InitialDesign Local Radial Axial R-Factor Power FlowDesign___ _(MWt) (1000 lb/hr) MCPRGE14C 1.0 1.31 1.22 0.97 6.833 101.6 1.57Page 8 Nine Mile Point 2Reload 14000N2528-SRLRRevision 17. Selected Margin Improvement Options 2Recirculation pump trip:Rod withdrawal limiter:Thermal power monitor:Improved scram time:Measured scram time:Exposure dependent limits:Exposure points analyzed:YesNoYesYes(Option B)NoYes2Table 7-1 Cycle Exposure Range DesignationName Exposure Range 3BOC to MOC BOC 15 to EOR 15 -3104 MWd/MT (2816 MWd/ST)MOC to EOC EOR15 -3104 MWd/MT (2816 MWd/ST) to EOC 15BOC to EOC BOC15 to EOC152 Refer to the GESTAR basis document identified at the beginning of this report for the margin improvementoptions currently supported therein.3 End of Rated (EOR) is defined as the cycle exposure corresponding to all rods out, 100% power/100% flow, andnormal feedwater temperature. For plants without mid-cycle OLMCPR points, EOR is not applicable.Page 9 Nine Mile Point 2 000N2528-SRLRReload 14 Revision 18. Operating Flexibility Options 4The following information presents the operational domains and flexibility options which are supportedby the reload licensing analysis.Extended Operating Domain (EOD): YesEOD type: Maximum Extended Load Line Limit (MELLLA)Minimum core flow at rated power: 99.0 %Increased Core Flow: YesFlow point analyzed throughout cycle: 105.0%Feedwater Temperature Reduction: NoARTS Program: YesSingle Loop Operation: YesEquipment Out of Service:Safety/relief valves Out of Service: Yes(credit taken for 16 valves)ADS Out of Service: YesTurbine Bypass Valve Out of Service YesEnd Of Cycle Recirculation Pump Trip Out of Service YesMain Steam Isolation Valve Out of Service YesPressure Regulator Out of Service Yes4 Refer to the GESTAR basis document identified at the beginning of this report for the operating flexibility optionscurrently supported therein.Page 10 Nine Mile Point 2Reload 14000N2528-SRLRRevision 19. Core-wide AOO Analysis Results "6Methods used: GEXL-PLUS, TRACG04Operating domain: ICF (HBB)Exposure range : BOC to MOC (Application Condition: 1, 3)Uncorrected ACPR/ICPREvent Flux STP GE14C Fig.(% rated) (% rated) GEI4CFig.Load Rejection w/o Bypass 545.9 110.0 0.2088 2FW Controller Failure 517.1 112.4 0.2001 3Operating domain: ICF (HBB)Exposure range : MOC to EOC (Application Condition: 1, 3)Exposure range : BOC to EOC (Application Condition: 2 )Uncorrected ACPR/ICPREvent Flux STP GE14C Fig.(% rated) (% rated)Turbine Trip w/o Bypass 614.5 110.8 0.2139 4FW Controller Failure 569.0 1 113.4 0.2108 5Operating domain: LCF (HBB)Exposure range : BOC to MOC (Application Condition: 1, 3)Uncorrected ACPR/ICPREvent Flux STP GE14C Fig.(% rated) (% rated)Load Rejection w/o Bypass 436.7 108.4 0.2026 6FW Controller Failure 367.9 110.3 0.1890 75 Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.6 The Heat Flux Q/A (% rated) output is not available from TRACG04, so the Simulated Thermal Power (STP) (%rated) is shown.Page 11 Nine Mile Point 2Reload 14000N2528-SRLRRevision IOperating domain: LCF (HBB)Exposure range : MOC to EOC (Application Condition: 1, 3)Exposure range : BOC to EOC (Application Condition: 2 )Uncorrected ACPRIICPREvent Flux STP GE14C Fig.Event___________ (% rated) (% rated) GEI4CFig.Load Rejection w/o Bypass 481.1 109.3 0.2053 8FW Controller Failure 413.9 1 111.4 0.1924 9Operating domain: ICF with TBVOOS (HBB)Exposure range : BOC to EOC (Application Condition: 2)Uncorrected ACPR/ICPREvent Flux STP GE14C Fig.(% rated) (% rated) GEI4CFig.FW Controller Failure 675.9 114.9 0.2294 10Operating domain: LCF with TBVOOS (HBB)Exposure range : BOC to EOC (Application Condition: 2)Uncorrected ACPR/ICPREvent Flux STP GE14C Fig.(% rated) (% rated) GEI4CFig.FW Controller Failure 495.3 112.9 0.2171 11Operating domain: ICF with RPTOOS (HBB)Exposure range : BOC to MOC (Application Condition: 3)Uncorrected ACPR/ICPREvent Flux STP GE14C Fig.Event_____________(% rated) (% rated)Turbine Trip w/o Bypass 655.8 110.8 0.2249 12FW Controller Failure 582.1 113.4 0.2156 13Operating domain: ICF with RPTOOS (HBB)Exposure range : MOC to EOC (Application Condition: 3)Uncorrected ACPRIICPREvent Flux STP GE14C Fig.Event_____________(% rated) (% rated)Load Rejection w/o Bypass 645.5 111.7 0.2475 14FW Controller Failure 631.6 114.3 0.2280 15Page 12 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1Operating domain: LCF with RPTOOS (HBB)Exposure range : BOC to MOC (Application Condition: 3)Uncorrected ACPR/ICPREvent Flux STP GE14C Fig.(% rated) (% rated)Load Rejection w/o Bypass 484.2 109.1 0.1995 16FW Controller Failure 404.8 111.1 0.1877 17Operating domain: LCF with RPTOOS (HBB)Exposure range : MOC to EOC (Application Condition: 3)Uncorrected ACPRIICPREvent Flux STP GE14C Fig.(% rated) (% rated)Load Rejection w/o Bypass 532.2 110.1 0.1994 18FW Controller Failure 453.7 112.2 0.1870 19Page 13 Nine Mile Point 2Reload 14000N2528-SRLRRevision 110. Rod Withdrawal Error AOO SummaryThe Rod Withdrawal Error (RWE) is analyzed in NEDC-33286P, Nine Mile Point Nuclear Station Unit 2APRM/RBM/Technical Specifications / Maximum Extended Load Line Limit Analysis (ARTS/MELLLA),Revision 0, March 2007.RWE Results:RBM Setpoint (%) ACPR108.0 0.23111.0 0.25114.0 0.25117.0 0.29Unblocked 0.25'The more limiting of the cycle specific and the generic ACPR values are reported in the table above. TheRWE OLMCPR is determined by adding the ACPR for the desired RBM setpoint from the table above tothe SLMCPR in Section 11.The ARTS RWE analysis validated that the following MCPR values provide the required margin for fullwithdrawal of any control rod during this cycle:For Power < 90%For Power > 90%MCPR > 1.70MCPR > 1.40The RBM operability requirements have been evaluated and shown to be sufficient to ensure that theSLMCPR and cladding 1% plastic strain criteria will not be exceeded in the event of a RWE.7 The cycle specific unblocked response is used to validate the MCPR operating limits for a full withdrawalprovided in the paragraph below the table.Page 14 Nine Mile Point 2Reload 14000N2528-SRLRRevision 111. Cycle SLMCPR and OLMCPR Summary 8 9Two Loop Operation (TLO) safety limit:Single Loop Operation (SLO) safety limit:Stability MCPR Design Basis:ECCS MCPR Design Basis:1.071.09See Section 15See Section 16 (Initial MCPR)Non-pressurization Events:Exposure range: BOC to EOCAll Fuel TypesRod Withdrawal Error (117.0 % RBM Setpoint) 1.36Loss of Feedwater Heating 1.21Fuel Loading Error (Mislocated) Not LimitingFuel Loading Error (Misoriented) 1.26Rated Equivalent SLO Pump Seizure 10 1.31Limitin2 Pressurization Events OLMCPR Summary Table:"Appi.TCond. Exposure Range Option A Option BGE14C GE14C1 Equipment in ServiceBOC to MOC 1.61 1.37MOC to EOC 1.62 1.382 TBV OOSBOC to EOC 1.63 1.423 RPT OOSBOC to MOC 1.73 1.40MOC to EOC 1.79 1.468 Exposure range designation is defined in Table 7-1.9 For SLO, the MCPR operating limit is 0.02 greater than the two loop value.10 The cycle-independent OLMCPR for the recirculation pump seizure event for GE14C is 1.44 based on the cycle-specific SLO SLMCPR. When adjusted for the off-rated power/flow conditions of SLO, this limit corresponds to arated OLMCPR of 1.31. This limit does not require an adjustment for the SLO SLMCPR." Each application condition (Appl. Cond.) covers the entire range of licensed flow and feedwater temperatureunless specified otherwise. The OLMCPR values presented apply to rated power operation based on the two loopoperation safety limit MCPR.Page 15 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1Pressurization Events: 12Operating domain: ICF (HBB)Exposure range : BOC to MOC (Application Condition: 1, 3 )Option A Option BGE14C GE14CLoad Rejection w/o Bypass 1.61 1.37Operating domain: ICF (HBB)Exposure range : MOC to EOC (Application Condition: 1, 3)Exposure range : BOC to EOC (Application Condition: 2 )Option A Option BGEI4C GE14CTurbine Trip w/o Bypass 1.62 1.38Operating domain: ICF with TBVOOS (HBB)Exposure range : BOC to EOC (Application Condition: 2 )Option A Option BGEI4C GE14CFW Controller Failure 1.63 1.42Operating domain: ICF with RPTOOS (HBB)Exposure range : BOC to MOC (Application Condition: 3 )Option A Option BGEI4C GE14CTurbine Trip w/o Bypass 1.73 1.40Operating domain: ICF with RPTOOS (HBB)Exposure range : MOC to EOC (Application Condition: 3 )Option A Option BGE14C GEI4CLoad Rejection w/o Bypass 1.79 1.4612 Application condition numbers shown for each of the following pressurization events represent the applicationconditions for which this event contributed in the determination of the limiting OLMCPR value.Page 16 Nine Mile Point 2Reload 14000N2528-SRLRRevision 112. Overpressurization Analysis Summary13Pdome Pv Plant(psig) (psig) ResponseMSIV Closure (Flux Scram) -ICF (HBB) 1277.9 1313.4 Figure 20MSIV Closure (Flux Scram) -LCF (HBB) 1277.9 1307.0 Figure 2113. Fuel Loading Error ResultsVariable water gap misoriented bundle analysis: Yes 14Misoriented Fuel Bundle ACPRGE14-P1OCNAB434-15GZ-120T-150-T6-4039 (GE14C) 0.17GE14-P1OCNAB422-17GZ-120T-150-T6-4041 (GE14C) 0.18GE 14-P 1OCNAB412-15GZ- 120T-150-T6-4040 (GE 14C) 0.18GE 14-P 1OCNAB422-17GZ- 120T-150-T6-4042 (GE 14C) 0.18GE 14-P 1 OCNAB412-14GZ- 120T- 150-T6-4043 (GE 14C) 0.19GE 14-P1OCNAB430-15GZ-120T-150-T6-4239 (GE14C) 0.18GE14-P1OCNAB430-14GZ-120T-150-T6-4240 (GE 14C) 0.17GE14-P1OCNAB418-15GZ-120T-150-T6-4241 (GE14C) 0.18GE 14-P 1OCNAB419-17GZ- 120T-150-T6-4242 (GE 14C) 0.18GE 14-P 1OCNAB418-16GZ- 120T-150-T6-4243 (GE 14C) 0.19GE 14-P 1OCNAB422-16GZ-120T-150-T6-4244 (GE14C) 0.1914. Control Rod Drop Analysis ResultsNine Mile Point 2 is a banked position withdrawal sequence plant, so the control rod drop accidentanalysis is not required. NRC approval is documented in NEDE-2401 1-P-A-US.13 Overpressure calculated at an initial dome pressure of 1020 psig.14 Includes a 0.02 penalty due to variable water gap R-factor uncertainty.Page 17 Nine Mile Point 2 000N2528-SRLRReload 14 Revision 115. Stability Analysis Results15.1 Stability Option III SolutionNine Mile Point 2 has implemented BWROG Long Term Stability Solution Option III using theOscillation Power Range Monitor (OPRM) as described in Reference 1 in Section 15.4. The plantspecific Hot Channel Oscillation Magnitude (HCOM) (Reference 2 in Section 15.4) and other cyclespecific stability parameters are used in the Cycle 15 Option III stability evaluation. Backup StabilityProtection (BSP) regions are used by the plant in the event that the Option III OPRM system is declaredinoperable.The following Option Ill OPRM stability setpoint determination described in Section 15.2 and theimplementation of the associated BSP Regions described in Section 15.3 provide the stability licensingbases for Nine Mile Point 2 Cycle 15.15.2 Detect and Suppress EvaluationA reload Option III evaluation has been performed in accordance with the licensing methodologydescribed in Reference 3 in Section 15.4. The stability based OLMCPR is determined for two conditionsas a function of OPRM amplitude setpoint. The two conditions evaluated are: (1) a postulated oscillationat 45% rated core flow quasi steady-state operation (SS), and (2) a postulated oscillation following a tworecirculation pump trip (2PT) from the limiting rated power operation state point.The OPRM-setpoint-dependent OLMCPR(SS) and OLMCPR(2PT) values are calculated for Cycle 15 inaccordance with the BWROG regional mode DIVOM guidelines described in Reference 4 in Section15.4. The Cycle 15 Option III evaluation provides adequate protection against violation of the SLMCPRfor the two postulated reactor instability events as long as the plant OLMCPR is equal to or greater thanOLMCPR(SS) and OLMCPR(2PT) for the selected OPRM setpoint in Table 15.2-2.The relationship between the OPRM Successive Confirmation Count Setpoint and the OPRM AmplitudeSetpoint is provided in Table E-I of Reference 3 in Section 15.4 and Table 15.2-1. For intermediateOPRM Amplitude Setpoints, the corresponding OPRM Successive Confirmation Count Setpoints havebeen obtained by using linear interpolation.The OPRM setpoints for TLO are conservative relative to SLO and are, therefore, bounding.Page 18 Nine Mile Point 2Reload 14000N2528-SRLRRevision ITable 15.2-1 Relationship between OPRM Successive Confirmation Count Setpoint andOPRM Amplitude SetpointSuccessive OPRMConfirmation Count AmplitudeSetpoint Setpoint6 >1.048 1.059 >1.0610 >1.0711 >1.0812 >1.0913 >1.1014 >1.1115 >1.1316 >1.1417 >1.1618 ?1.1919 ?1.2120 >1.24Page 19 Nine Mile Point 2Relnad 14000N2528-SRLRRevision 1Table 15.2-2 OPRM Setpoint Versus OLMCPROPRM Amplitude OLMCPR(SS) OLMCPR(2PT)Setpoint1.04 1.16 1.091.05 1.18 1.101.06 1.20 1.121.07 1.22 1.141.08 1.24 1.161.09 1.26 1.181.10 1.28 1.201.11 1.30 1.221.12 1.32 1.241.13 1.35 1.261.14 1.37 1.29OLMCPR Off-rated Rated PowerAcceptance OLMCPR OLMCPR (seeCriteria @45% flow Section 11)15.3 Backup Stability ProtectionThe BSP region boundaries were calculated for Nine Mile Point 2 Cycle 15 for normal feedwatertemperature operation. The endpoints of the regions are defined in Table 15.3-1. The region boundaries,shown in Figure 22, are defined using the Modified Shape Function (MSF). See Reference 5 in Section15.4.Table 15.3-1 BSP Region Intercepts for Normal Feedwater TemperatureHighestRegion Boundary Power Flow Core DR ChannelIntercept (%) (%) DRAl 56.5 40.0 < 0.80 < 0.56B1 41.4 29.5 < 0.80 < 0.56A2 64.5 50.0 < 0.80 < 0.56B2 28.7 28.9 < 0.80 < 0.56The Cycle 15 BSP region boundaries for normal feedwater temperature operation presented herein areadequate to bound a variation in nominal feedwater temperature of +/- 20'F.Page 20 Nine Mile Point 2 000N2528-SRLRReload 14 Revision 115.4 References1. B WR Owners' Group Long-term Stability Solutions Licensing Methodology, NEDO-31960-A,November 1995 (including Supplement 1).2. GENE-A13-00381-05, Rev. 1, Reactor Long-Term Stability Solution Option III: LicensingBasis Hot Channel Oscillation Magnitude for Nine Mile Point 2, April 1998.3. Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for ReloadApplications, Licensing Topical Report, NEDO-32465-A, August 1996.4. Plant-Specific Regional Mode DIVOM Procedure Guideline, GE-NE-0000-0028-9714-Ri, June2005.5. OD YSY Application for Stability Licensing Calculations Including Option I-D and H Long TermSolutions, Licensing Topical Report, NEDE-33213P-A, April 2009.Page 21 Nine Mile Point 2Reload 14000N2528-SRLRRevision 116. Loss-of-Coolant Accident Results16.1 10CFR50.46 Licensing ResultsThe ECCS-LOCA analysis is based on the SAFER/GESTR-LOCA methodology. The licensing basisresults applicable to the GEI4C fuel type in the new cycle are summarized in the following table.Table 16.1-1 Licensing ResultsCore-WideLicensing Local Me-WateFuel Type Basis PCT Oxidation Reatio(OF) Reaction(°F) (%) (%)GE14C 1540 < 1.00 < 0.10The SAFER/GESTR ECCS-LOCA analysis results for the GE14C fuel type are documented in Section16.4, Reference 1.16.2 10CFR50.46 Error EvaluationThe 10 CFR 50.46 errors applicable to the Licensing Basis PCT are shown in the following table.Table 16.2-1 Impact on Licensing Basis PeakCladding Temperature for GE14C10CFR50.46 Error NotificationsNumber Subject PCT ImpactNumberSubject (OF)2011-02 Heat Deposition Parameter +302011-03 Heat Deposition Definition -52012-01 PRIME code Implementation for fuel rod T/M 0performance, replacing GESTRTotal PCT Adder (OF) +25After accounting for the error impact, the GEl4 Licensing Basis PCT with the total PCT adder remainsbelow the 1OCFR50.46 limit of 2200 'F.Page 22 Nine Mile Point 21V I A000N2528-SR-LR]?,,; ;- I16.3 ECCS-LOCA Operating LimitsThe ECCS-LOCA MAPLHGR operating limits for all fuel bundles in this cycle are shown in thefollowing table.Table 16.3-1 MAPLHGR LimitsBundle Type(s):GE14-P10CNAB434-8G7.0/7G6.0-120T-150-T6-3233 (GEl4C)GE14-P1OCNAB416-17GZ-120T-150-T6-3235 (GE14C)GE14-PlOCNAB417-17GZ-120T-150-T6-3236 (GE14C)GE14-P1OCNAB434-15GZ-120T-150-T6-4039 (GE14C)GE 14-P 1OCNAB422-17GZ- 120T-150-T6-4041 (GE 14C)GE 14-P 1OCNAB412-15GZ- 120T-150-T6-4040 (GE 14C)GE 14-P 10CNAB422-17GZ- 120T-150-T6-4042 (GE 14C)GE14-P1OCNAB412-14GZ-120T-150-T6-4043 (GE14C)GE14-P1OCNAB430-15GZ-120T-150-T6-4239 (GE 14C)GE14-P1OCNAB430-14GZ-120T-150-T6-4240 (GE 14C)GE14-PlOCNAB418-15GZ-120T-150-T6-4241 (GE14C)GE 14-P 1OCNAB419-17GZ- 120T-150-T6-4242 (GE 14C)GE 14-P 1OCNAB418-16GZ- 120T-150-T6-4243 (GE 14C)GE 14-P 1OCNAB422-16GZ- 120T-150-T6-4244 (GE 14C)Average Planar Exposure MAPLHGR LimitGWd/MT GWd/ST kW/ft0.00 0.00 12.8216.00 14.51 12.8221.09 19.13 12.8263.50 57.61 8.0070.00 63.50 5.00The MAPLHGR limits for GE14C fuel, shown in Table 16.3-1, are unaffected by changes to the LHGRcurve being implemented in the new cycle.The power and flow dependent LHGR multipliers are sufficient to provide adequate protection for theoff-rated conditions from an ECCS-LOCA analysis perspective and there is no need for MAPLHGRmultipliers, in addition to off-rated LHGR multipliers.The single loop operation multiplier on LHGR and MAPLHGR and the ECCS-LOCA analytical initialMCPR value applicable to the GE14C fuel type in the new cycle core are provided in the following table.Page 23 Nine Mile Point 2 000N2528-SRLRReload 14 Revision 1Table 16.3-2 Initial MCPR and Single Loop Operation Multiplier on LHGR andMAPLHGRSingle Loop OperationFuel Type Initial MCPR Multiplier on LHGR andMAPLHGRGE14C 1.25 0.7816.4 ReferencesThe SAFER/GESTR-LOCA analysis base report(s) applicable to the new cycle core are:References for GE14C1. Project Task Report Constellation Generation Group Nine Mile Point Nuclear Station Unit2 Extended Power Uprate Task T0407: ECCS-LOCA SAFER/GESTR, 0000-0080-7568-Ri,Revision 1, February 2009.Page 24 Nine Mile Point 2Reload 14000N2528-SRLRRevision 177787777778777810101010101013131010101010108771316151615161612121616151615161377712162014201218121919121812201420161277111520201810181218121218121810182020151177 79 10 1013 16 1516 20 1420 20 1812 20 1020 11 1813 17 1017 13 1710 17 1018 10 1710 19 1118 12 1911 19 1219 12 1919 12 1911 19 1218 12 1910 19 1118 10 1710 17 1017 13 1713 17 1020 11 1812 20 1020 20 1816 20 1413 16 159 10 107 78 7 7 710 10 10 1015 16 15 1612 20 14 2018 10 18 2010 18 10 2018 14 18 1110 18 10 1719 10 17 1311 17 10 1717 10 17 1011 17 11 1919 10 19 1212 18 12 1917 13 19 1217 13 19 1212 18 12 1919 10 19 1211 17 11 1917 10 17 1011 17 10 1719 10 17 1310 18 10 1718 14 18 1110 18 10 2018 10 18 2012 20 14 2015 16 15 1610 10 10 108 7 7 771216201420121812191912181220142016127771316151615161612121616151615161377810101010101013131010101010108777877777787771 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59Fuel Type7=GEI 4-PI OCNAB434-8G7.0/7G6.0-120T- I 50-T6-3233 (Cycle 13) 14=GE14-Pl0CNAB412-14GZ-120T-150-T6-4043 (Cycle 14)8=GE14-PIOCNAB416-17GZ-120T-150-T6-3235 (Cycle 13) 15=GE14-PIOCNAB430-15GZ-120T-150-T6-4239 (Cycle 15)9=GE14-PIOCNAEB417-17GZ-120T-150-T6-3236 (Cycle 13) 16=GE14-PIOCNAB430-14GZ-120T-150-T6-4240 (Cycle 15)10=GE14-PIOCNAB434-15GZ-120T-150-T6-4039 (Cycle 14) 17=GE14-PI0CNAB418-15GZ-120T-150-T6-4241 (Cycle 15)1 1=GE04-PIOCNAB422-17GZ-120T-l 50-T6-4041 (Cycle 14) 18=GE14-PIOCNAB419-17GZ-120T-150-T6-4242 (Cycle 15)12=GE14-P1OCNAB412-15GZ-120T-150-T6-4040 (Cycle 14) 19=GE14-PIOCNAB418-16GZ-120T-150-T6-4243 (Cycle 15)13=GE14-PIOCNAB422-17GZ-120T-150-T6-4042 (Cycle 14) 20=GE14-P10CNAB422-16GZ-120T-150-T6-4244 (Cycle 15)Figure 1 Reference Core Loading PatternPage 25 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1LRNBPICF..TNMI-EISKIs140120100I60wt 604020700400500200100aUK1400135013001250~120oj1100105010000 1 2 3 4 5 6Time (sec)16012080-400.4060 4.03.550 3.02.540 2.030 1.0-1.5201 .0'SA -0.510 -1.0-1.50 -2.0-80 , t , , , , -i0 1 2 3tft~C.A. ~3~S~~'S Tirne (sa)02 3 4Time (sec)6Figure 2 Plant Response to Load Rejection w/o Bypass(MOC ICF (HBB))Page 26 Nine Mile Point 2D.1 A 1A000N2528-SRLRD ; ; 1FWCFICFjNMIaESKGIis140120100u80S40560 4048030400a320 _1201240116010130012001100lO0080000 5 10 15 20Thme (see)0 5 10Time (sec)15 2016014012010080so402040-20-20T _ _01009080706050403020100ISIA.5U-j4.03.53.02.52.01.50.50.0-0.5-1.0-1.5-2.0-Totld Reactivity-4-Sawn Reeil-Doppler Teniperature Rouvitly-.-VoidReatvt10Tkme (sec)15 2005 10Time (sec)1520Figure 3 Plant Response to FW Controller Failure(MOC ICF (HBB))Page 27 Nine Mile Point 2A 1A000N2528-SRLRD e;c 1%, uau .1 a ns.v II.nTTNBPKGIIs1401201004802e040TTNBPICFTNEO-EIS700 806OO 7060500505400.3020020100 100 014001350130012501200~1100105010000 1 2 3 4 5 aTkne (sec)02 3 4 5 6Time (sec)160Stmn FlowTubie Stwa FlowNR Ievel12080so-4040-400 1 2 3 4 5 6.tSW. 2 Time (see)60504030~201j.51004.03.53.02.52,01.0.0560.0-0.5-1.0-1.5-2.02 3Time (sec)4 5 6Figure 4 Plant Response to Turbine Trip w/o Bypass(EOC ICF (HBB))Page 28 Nine Mile Point 2Relnod 14000N2528-SRLRRevkinin 1FWCFICF.TNEO-EISKG11s14012010080U4t604020040302010130012001100010005 10 15 20Thme (sec)010Time (sec)15 2016014012010080I640200-20-4001009080706050403020100UIUII1.IU4.03.53.02.52.01.51.00ý5*0.0-0.5-1.0-1.5-2.0TOW .acbvtty--- Scrwm Raty-Dopplr Toemprsture Rem"kv~--Void Rdik10Time (Sec)15 2005 10Tim. (see)15 20Figure 5 Plant Response to FW Controller Failure(EOC ICF (HBB))Page 29 Nine Mile Point 2Reload 14000N2528-SRLRRevision IKG11512010080W6040200LRNBPMLPTNMI-EIS480 8070400so-320 5240 401601 302080100 01350130012501200IIS11501050100095016012080400-40D-80 -H -04.03.53.0aISIIA3S-J2.52.01.51.0~0.5So.o-0.5-1.0-1.5-2.03Tim. (sec)0 1 2 3Time (sac)4 5 6Figure 6 Plant Response to Load Rejection w/o Bypass(MOC LCF (HBB))Page 30 Nine Mile Point 2Reload 14000N2528-SRLRRevision IFWCFMLPjNM1-E1SKG115140 -120.100-Core Inlet Flow*ý Sarnilded Thermael Power-. Natanm FhixKSo 4-4203W030WI.240.180112060130012001100]iU,I60 ý4o 4-20-016014012010080.~6040200-20-401000U5 10Thu (sec)15D100 4.090 3.53.0802.5701~ 2.0so 11.040 0,50.030 K20-1.010 -1.50 -2.0tttSo..O j Figure 7 Plant Response to FW Controller Failure(MOC LCF (HBB))Page 31 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1LRNBPMLPJNEO-EISKG115560140013501204801300100400wt60I.320.2401J'21250~1200j1150 I4016011002080105000100016060 4.012080403.550 3.02.540 2.01.530 1.00.5201, 0.0* -0.510 -1.0-1.50 -2.0I--*-o leacbOWWy-Sewvn ROaci0-DoppWe Torenpursk RowAelty-.Vold Rebk-40-W00 1 2 3Time (sft)4 5 1,*.Q. t.5SFigure 8 Plant Response to Load Rejection w/o Bypass(EOC LCF (HBB))Page 32 Nine Mile Point 2Reload 14000N2528-SRLRRevision IFWcFMLPTNEO-EISKGI15140120 4100IUK.5804--core Inlet FloSmIstded Thermnal Power-Neubmn Flux580 4048030400320240 916010130012Do1100D1000soI4o 420,0800 01 5 10Tbm (see)15 2016014012010080Uso40100 4.090 3.53.0802.570i 22.040.ODO30 -0.520-1.010 -1.50 -2.0Scram -Doppler Temperiure Reactivity-- Void Rea ty0-20-400 5 10.ý. Time (eei)15 200 5 10Time (sec)15 20Figure 9 Plant Response to FW Controller Failure(EOC LCF (HBB))Page 33 Nine Mile Point 2Reload 14000N2528-SRLRRevision IFwVcF1CFJ-NEO-TOVOCISKG115140120100402,04080708050ws o114030201001400135013001250I1200i1100105010000 5 10Tkne ("ee)15 200 5 10 15 20Time (See)140120100806040200-20-40-60-e Steam~ Flow-- Turbine Steami Flow--a- NR level0 5 10 15 20100 4.090 3.53.08o.1 2.570so 1.0401 0.150.030 0* -0.520-1.010 -1.50 -2.0I--* lOKOOw ~Acty--a- Scram Reactivity-Doppler Temperature Reactivity-VoidReatvt-R I+ I005 10Time (sec)15 20Ut.*CwD 0 tnwT*me (sae)Figure 10 Plant Response to FW Controller Failure(EOC ICF with TBVOOS (HBB))Page 34 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1FWCFMLP_TNEO-TBVOOSKGI15140120.ý100.-C or Inbt-Mtm~ F1SmidThwmai Powm560.480,400UUK.5804-6040 1SU320240160so1400135013001250120051150110010501000200I I I -~0510Tin. (s")15 20140120100soso402010-20-40-000 5 10TR~tAA 13*5 *34*, Tin. (usc)100 4.090 3.53.080.2.5706 ,,50 11.040 -0.50.030 K-0520-1.010 -1.50 -2.015 200 5 10Tine (sec)15 20Figure 11 Plant Response to FW Controller Failure(EOC LCF with TBVOOS (HBB))Page 35 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1TTNSPICFjNMI-RPTOOSKGIIs140120100v 8040,0a~04020.0-8080706050140302010014001350130012501200511501100105010004.03.53.02.52.01.51.0U0.:o.10.0-0.5-1.0-1.5-2.0fk.m-cm" 2mmt,~Figure 12 Plant Response to Turbine Trip w/o Bypass(MOC ICF with RPTOOS (HBB))Page 36 Nine Mile Point 2Reload 14000N2528-SRLRRevision IKGIis14012010040200FWCFICFTNMI-RPTOOS-700 4060030,50040001J20-300 e200101000 0130012D0O110001000Time (sac)16014012010080II40200-20-40--.0100908070605040302010IIII,-J*14.03.53.02.52.01.0.0.5-1.0-1.5-2.0TO- -OOW-U-Scram Recit-Doppler Temporours, ReactiityVoid Roalvt10Tk (is")0510Time (sec)15 20Figure 13 Plant Response to FW Controller Failure(MOC ICF with RPTOOS (HBB))Page 37 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1LRNBPICFTNEO-RPTOOSKGI1572 sso1009080706040302010014501400135013001250112100115011001050100095016012080U4004.03.53.02.52.01.51.00.50.0-0.5-1.0-1.5-2.0-40-800 1 2 3 4 5 6Figure 14 Plant Response to Load Rejection w/o Bypass(EOC ICF with RPTOOS (HBB))Page 38 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1pWcFICFjNEO-RPTOOSKGIIs140120,100*v 80IF8--Core IWhat Flow--Sirnuilaed Themfna Power700 60600505oo40400. 2S1303" 2020013001250120011501100105010004-404102001000 05 10Thm (sec)152016014012010080Il40200-20F. ~dVwgtf HMt--Stearn FloTurbine Stemn Flow--NRI lel100 4.090 3.53.080.1 2.570"S 2.06 0 1.550 1*)1.0-0.0.30 49* 0.520-1.010 -1.50 -2.0-400 5 10I*AM-CAW-o w.. Tkne (50c)15 20Figure 15 Plant Response to FW Controller Failure(EOC ICF with RPTOOS (HBB))Page 39 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1LRNBPMLPJNMI.RPTOOSK15140120100a' 604020058o480400320 124011608014001350130012501200i1100105010000 1 2 3 4 5 6Time (see)160 .oodwae FlowSteam FlowTurbine Steam FlowNR level120803400-400 1 2 3 4 5 6M* ý-~ Time (ee)60 4.03.550 3.0.2.540 2.01.520 1.001 -0.5'a10 -1.0-1.50 -2.02 3 4 5 6Tine (Sec)Figure 16 Plant Response to Load Rejection w/o Bypass(MOC LCF with RPTOOS (HBB))Page 40 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1FW4CFMLP..TNMI-RPTOOSKG14AtI120 4-100soIe 604020010fO Inlt lW-~Simutiid Thwnii Power--Neuton Flux _420 40360303002401 12012010600 0130012001100i10005 10Tim. (sec)15 216014012010080Is40200-20100 4.090 3.53.080i 2.570 2.0so 1.040 10-50.0*0 -0.520-1.010 -1.50 -2.0-Scrub, Reac#Aty--Doppler Temp~reure R..c*4ft-Voi ReahtUI1/2I I I-400 5 10TRýCft Tike (-ec)15 2005 10Time (sec)15 20Figure 17 Plant Response to FW Controller Failure(MOC LCF with RPTOOS (HBB))Page 41 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1LRNSPMLP...NE0-RPTOOSKGI1s140120100~6040200--Corn Inmt Flow--Sknudied Thwmnu Powet~-Natka Fkm560 80480 706040050320~1 40240 A0160 0201400135013001250120051150 I110010501 2 3Tuim Isem)4 5o80 100 0C80 4.03.550 3.02.530! 1.0H 0.50.010 -1.0-1.50 -2.01000Tim. (sec)*1UK10ý-C." MýSýWý,Figure 18 Plant Response to Load Rejection w/o Bypass( EOC LCF with RPTOOS (HBB))Page 42 Nine Mile Point 2ý1-olA 1A000N2528-SRLRRi-xtccinn IPWVCFMLPJTNEO-RPTOOSKG115140120100.80402000 5 10 15 20Tin. (see)4030120lO004.03.53.02.5-2.01.00.50.0-0.5-1.0-1.5-2.013001200110010005 10Time (sec)15 20160.140120100801602040-20-40010090807060~4012010010Time (sec)15 2010Tine (sec)Figure 19 Plant Response to FW Controller Failure(EOC LCF with RPTOOS (HBB))Page 43 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1MSIVFICF_TNEO-OvmpressKGI1514012010080at 604020012010080at4020Tim. (sec)420 1009o36080300 70I 6240 601801 40120 302060100 060 4.03.550 3.0,1 2.540 S 2.01.530 >' 1.0-201 ; oo-1.50 -2.0145014001350130012501120051150IL110010501000950Time (sGec)0 ~- --U I.-~H0 1 20 M..C ¶3OlIwR3 4Time (sec)Figure 20 Plant Response to MSIV Closure (Flux Scram) -ICF (HBB)Page 44 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1KGI1sMSIVFMLPTNEO-Overpress-420 100-903608o30O 70602401" 80 40120 320oSo100 0u80014501400135013001250j1200j1150I.1100105010009500 1 2 3 4 5 6 7Time (see)Time (see)120-,1008040200 1T*Oc.wfl ~tS 2M lSfl60 4.03.550 3.02.5U40 2.0l.530 1.0201 0.0-0.510 -1.0-1.50 -2.0Figure 21 Plant Response to MSIV Closure (Flux Scram) -LCF (HBB)Page 45 Nine Mile Point 2Reload 14000N2528-SRLRRevision 10Aa-U1101009080706050403020100-L Na" Urlto UnI-a- cienue Operating Domainx ISP Scram Rejgot, Bot~ndary--------SP C-ontrolled Ent- --eg-n Boundar---------- ----------... ....l+~ ~~~~~ ~~ --A1- ---"- ---..................L -L102 0 4 06 0 0 9 0 1 2Ia10 20 30 40 50 60 70 80 90 100 110 120Core Flow(%)Figure 22 BSP Region BoundariesPage 46 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1Appendix AAnalysis ConditionsThe reactor operating conditions used in the reload licensing analysis for this plant and cycle arepresented in Table A-1. The pressure relief and safety valve configuration for this plant are presented inTable A-2. Additionally, the operating flexibility options listed in Section 8 are supported by the reloadlicensing analysis.Table A-1 Reactor Operating ConditionsAnalysis ValueParameter ICF LCF 15NFWT NFWTThermal power, MWt 3988.0 3988.0Core flow, Mlb/hr 114.0 92.2Reactor pressure (core mid-plane), psia 1051.0 1047.2Inlet enthalpy, Btu/lb 530.0 525.2Non-fuel power fraction 16 N/A N/ASteam flow, Mlb/hr 17.63 17.63Dome pressure, psig 1020.2 1020.2Turbine pressure, psig 975.5 975.6Table A-2 Pressure Relief and Safety Valve ConfigurationValve Type Number of Lowest SetpointValves (psig)Dual Safety/Relief Valve 18 1121.0 (Relief Mode)1200.0 (Safety Mode)I5 The low core flow analysis condition used a bounding core flow value.16 For TRACG methodology, the direct moderator heating is a function of moderator density.Page 47 Nine Mile Point 2P In-A 1A000N2528-SRLRRPý1;cinn 1Appendix BThermal-Mechanical ComplianceA thermal-mechanical compliance check is performed for all analyzed transients to assure that the fuelwill operate without violating the thermal-mechanical design limits. These limits are designed such thatreactor operation within these limits provides assurance that the fuel will not exceed any thermal-mechanical design or licensing limits during all modes of operation. The fuel thermal-mechanical limitsare met for the current cycle.Page 48 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1Appendix CDecrease in Core Coolant Temperature EventThe Loss-of-Feedwater Heating event was analyzed at 100% rated power using the BWR SimulatorCode. The use of this code is consistent with the approved methodology. The transient plots, neutron fluxand heat flux values normally reported in Section 9 are not an output of the BWR Simulator Code;therefore, those items are not included in this document. The OLMCPR result is shown in Section 11.Page 49 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1Appendix DOff-Rated LimitsOff-Rated Power Dependent LimitsARTS power dependent thermal limits have been confirmed for operation with Equipment In-Service,Turbine Bypass Valves Out-Of-Service (TBVOOS), Recirculation Pump Trip Out-Of-Service (RPTOOS)and Pressure Regulator Out-Of-Service (PROOS). The Kp/MCPRp and LHGRFACp thermal limitsapplicable to the Equipment In-Service, TBVOOS and RPTOOS conditions are documented in ReferenceD-1. The Kp/MCPRp and LHGRFACp thermal limits applicable to the PROOS condition aredocumented in References D-4 and D-2. The off-rated power dependent limits provided in References D-4 and D-2 have been validated for this cycle.The MCPRp limits provided in References D-4 and D-2 are based on a SLMCPR of 1.07; therefore, aSLMCPR adjustment is not required for this cycle. The Reference D-2 limits for PROOS below 55%power have been adjusted as a result of the shift in fuel thermal monitor threshold and scaling of Pbypasssimilar to the adjustment shown in Reference D-3.The MCPRp and LHGRFACp limits below the turbine power/scram bypass setpoint of 26% rated powerhave only been evaluated for core flow less than or equal to 75% of rated core flow. Therefore, theMCPRp and LHGRFACp limits below 26% power are not applicable above 75% of rated core flow.MCPRp Limits for:Equipment In-ServiceLimits for Power < 26.0%Flow > 75.0% Flow <75.0%Power (%) Limit Power (%) LimitMCPRp MCPRp23.0 Not Analyzed 23.0 2.4726.0 Not Analyzed 26.0 2.39Limits for Power >26.0%Power (%) LimitKp26.0 1.51155.0 1.33655.0 1.19360.0 1.15085.0 1.056100.0 1.000Page 50 Nine Mile Point 2.1 -nA 1A00ON2528-SRLRMCPRp Limits for:TBVOOSLimits for Power < 26.0%Flow > 75.0% Flow < 75.0%Power (%) Limit Power (%) LimitMCPRp MCPRp23.0 Not Analyzed 23.0 3.2726.0 Not Analyzed 26.0 3.00Limits for Power > 26.0%Power (%) LimitKp26.0 1.51155.0 1.33655.0 1.19360.0 1.15085.0 1.056100.0 1.000MCPRp Limits for:RPTOOSLimits for Power < 26.0%Flow > 75.0% Flow < 75.0%Power (%) Limit Power (%) LimitMCPRp MCPRp23.0 Not Analyzed 23.0 2.4726.0 Not Analyzed 26.0 2.39Limits for Power > 26.0%Power (%) LimitKp26.0 1.51155.0 1.33655.0 1.19360.0 1.15085.0 1.062100.0 1.000Page 51 Nine Mile Point 2Reload 14000N2528-SRLRRevision IMCPRp Limits for:PROOSLimits for Power < 26.0%Flow > 75.0% Flow < 75.0%Power (%) Limit Power (%) LimitMCPRp MCPRp23.0 Not Analyzed 23.0 2.4726.0 Not Analyzed 26.0 2.39Limits for Power > 26.0%Power (%) LimitKp26.0 1.51190.0 1.12290.0 1.038100.0 1.000LHGRFACp Limits for:Equipment In-ServiceLimits for Power < 26.0%Flow > 75.0% Flow < 75.0%Power (%) Limit Power (%) Limit23.0 Not Analyzed 23.0 0.59726.0 Not Analyzed 26.0 0.613Limits for Power >26.0%Power (%) Limit26.0 0.613100.0 1.000LHGRFACp Limits for:TBVOOSLimits for Power < 26.0%Flow > 75.0% Flow < 75.0%Power (%) Limit Power (%) Limit23.0 Not Analyzed 23.0 0.53526.0 Not Analyzed 26.0 0.556Limits for Power > 26.0%Power (%) Limit26.0 0.613100.0 1.000Page 52 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1LHGRFACp Limits for:RPTOOSLimits for Power < 26.0%Flow > 75.0% Flow < 75.0%Power (%) Limit Power (%) Limit23.0 Not Analyzed 23.0 0.59726.0 Not Analyzed 26.0 0.613Limits for Power?> 26.0%Power (%) Limit26.0 0.613100.0 1.000LHGRFACp Limits for:PROOSLimits for Power < 26.0%Flow > 75.0% Flow < 75.0%Power (%) Limit Power (%) Limit23.0 Not Analyzed 23.0 0.59726.0 ---Not Analyzed 26.0 0.613Limnts for Power >_ 26.0%Power (%) Limit26.0 0.61390.0 0.85090.0 0.948100.0 1.000Page 53 Nine Mile Point 2Reload 14000N2528-SRLRRevkinin IOff-Rated Flow Dependent LimitsARTS flow dependent thermal limits are documented in Reference D-1. The off-rated flow dependentlimits provided in Reference D-l have been validated for this cycle.The MCPRf limits provided in Reference D-1 are based on a SLMCPR of 1.07; therefore, a SLMCPRadjustment is not required for this cycle.MCPRf Limits for:Equipment In-ServiceLimits for a Maximum Runout Flow of 112.0%Flow (%) LimitMCPRf30.0 1.6687.3 1.25112.0 1.25MCPRf Limits for:TBVOOSLimits for a Maximum Runout Flow of 112.0%Flow (%) LimitMCPRf30.0 1.6687.3 1.25112.0 1.25MCPRf Limits for:RPTOOSLimits for a Maximum Runout Flow of 112.0%Flow (%) LimitMCPRf30.0 1.6687.3 1.25112.0 1.25MCPRf Limits for:PROOSLimits for a Maximum Runout Flow of 112.0%Flow (%) LimitMCPRf30.0 1.6687.3 1.25112.0 1.25Page 54 Nine Mile Point 20 1 A 1A00ON2528-SRLRV ; ; INIne Mile 2"LLHGRFACf Limits for:Equipment In-ServiceLimits for a Maximum Runout Flow of 112.0%Flow (%) Limit30.0 0.62585.0 1.000112.0 1.000LHGRFACf Limits for:TBVOOSLimits for a Maximum Runout Flow of 112.0%Flow (%) Limit30.0 0.62585.0 1.000112.0 1.000LHGRFACf Limits for:RPTOOSLimits for a Maximum Runout Flow of 112.0%Flow (%) Limit30.0 0.62585.0 1.000112.0 1.000LHGRFACf Limits for:PROOSLimits for a Maximum Runout Flow of 112.0%Flow (%) Limit30.0 0.62585.0 1.000112.0 1.000ReferencesD-1 Nine Mile Point Nuclear Station Unit 2 -APRAMRBM/Technical Specifications / MaximumExtended Load Line Limit Analysis (ARTS/MELLLA), NEDC-33286P, Revision 0, March 2007.D-2 Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900: Transient Analysis, GE-NE-0000-0055-2373-RO, Revision 0, February 2007.D-3 Nine Mile Point Nuclear Station Unit 2 Extended Power Uprate, Task T0900: Transient Analysis,0000-0069-6612-Ri, Revision 1, January 2009.D-4 Nine Mile Point Nuclear Power Plant, Unit 2, TRACG Implementation for Reload LicensingTransient Analysis (T1309), 0000-0157-9895-R1, Revision 1, October 2013.Page 55 Nine Mile Point 2 000N2528-SRLRReload 14 Revision 1Appendix EExpanded Operating Domain AnalysisExpanded operating domain analyses were performed for Maximum Extended Load Line Limit AnalysisPlus (MELLLA+) operation, Increased Core Flow (ICF) operation up to 105% of rated core flow, turbinebypass valve out-of-service (TBVOOS), recirculation pump trip out-of-service (RPTOOS), and pressureregulator out-of-service (PROOS). The MELLLA+ analysis is bounding for the MELLLA domain.Coastdown operation beyond full power to 40% power under conditions bounded by 105% core flow isconservatively bounded by the MCPR operating limits given in Section 11 of this document at theapplicable core flow and feedwater temperature conditions in the expanded operating domain. The basisfor this statement is contained in Reference E-1.100% Core Flow (Standard Domain)It has been established that ICF and/or MELLLA domain results bound the standard (rated core flow)domain. Therefore, a cycle-specific analysis is not performed for the standard domain.Maximum Extended Load Line Limit AnalysisThe operating domain MELLLA was established for Nine Mile Point 2 in Reference E-2.Increased Core FlowOperation with ICF throughout the operating cycle was justified for Nine Mile Point 2 in Reference E-3.The MSIV closure event (flux scram) was analyzed at 100% rated thermal power and both 85% and105% rated core flow at the rated dome pressure.An operational band of -20'F from nominal feedwater temperature is supported this cycle for allApplication Conditions specified in Section 11.Turbine Bypass Valve Out of Service (TBVOOS)Operation with TBVOOS was justified for Nine Mile Point 2 in Reference E-3.EOC Recirculation Pump Trip Out of Service (EOC RPTOOS)Operation with EOC RPTOOS was justified for Nine Mile Point 2 in Reference E-3.Pressure Regulator Out of Service (PROOS)Operation with PROOS was addressed for Nine Mile Point 2 from a thermal limits perspective only inReference E-3.Page 56 Nine Mile Point 2 000N2528-SRLRReload 14 Revision 1References for Appendix E:E-1 General Electric Standard Application for Reactor Fuel (GESTAR II), NEDE-2401 I-P-A-20,December 2013 and the U.S. Supplement, NEDE-2401 1-P-A-20-US, December 2013.E-2 Safety Analysis Report for Nine Mile Point Nuclear Station Unit 2 Constant Pressure PowerUprate, NEDC-33351P, Revision 0, May 2009.E-3 Project Task Report, Constellation Generation Group, Nine Mile Point Nuclear Station Unit 2Extended Power Uprate, Task T0900: Transient Analysis, 0000-0069-6612-Ri, Revision 1,January 2009.Page 57 Nine Mile Point 2 000N2528-SRLRReload 14 Revision 1Appendix FTRACG04 AOO Supplementary InformationReference F-I provides the results of the evaluations supporting the application of TRACG04 for AOOanalyses for Nine Mile Point 2. Section 11 of this report presents the MCPR limits based on theTRACG04 methodology of Reference F-2.The safety evaluation report for licensing topical report NEDE-32906P (Reference F-2) concluded thatthe application of TRACG04 methods to AOO and overpressure transient analyses were acceptablesubject to certain limitations and conditions. Nine Mile Point 2 Cycle 15 is in compliance with theselimitations and conditions.References for Appendix FF-1. Nine Mine Point Nuclear Power Plant, Unit 2, TRACG Implementation for Reload LicensingTransient Analysis (T1309), 0000-0157-9895-R1, Revision 1, October 2013.F-2. Migration to TRACGO4/PANACll from TRACGO2/PANACIO for TRACG AOO and ATWSOverpressure Transients, NEDE-32906P, Supplement 3-A, Revision 1, April 2010.Page 58 Nine Mile Point 2 000N2528-SRLRReload 14 Revision 1Appendix GInterim Methods LTR (NEDC-33173P-A Revision 4)Supplemental InformationThe safety evaluation for licensing topical report NEDC-33173P-A Revision 4 (Reference G-1)concluded that the application of GEH/GNF methods to expanded operating domains was acceptablesubject to certain limitations and conditions. Several of these limitations and conditions request thatadditional, application-specific information be provided in the SRLR. The information provided belowresponds to these requests for the identified items.Limitation and Condition 9.10/9.11 (Transient LHGR 2/3)Limitation and Condition 9.10 states:"Each EPU and MELLLA+ fitel reload will document the calculation results of theanalyses demonstrating compliance to transient T-M acceptance criteria. The plant T-Mresponse will be provided with the SRLR or COLR, or it will be reported directly to theNRC as an attachment to the SRLR or COLR."Limitation and Condition 9.11 states:"To account for the impact of the void history bias, plant-specific EPU and MELLLA+applications using either TRACG or ODYN will demonstrate an equivalent to 10 percent marginto the fiel centerline melt and the 1 percent cladding circumferential plastic strain acceptancecriteria due to pellet-cladding mechanical interaction for all of limiting AO0 transient events,including equipment out-of-service. Limiting transients in this case, refers to transients where thevoid reactivity coefficient plays a significant role (such as pressurization events). If the voidhistory bias is incorporated into the transient model within the code, then the additional 10percent margin to the fitel centerline melt and the 1 percent cladding circumferential plasticstrain is no longer required. "Appendix B documents the fact that the results for all analyzed transients demonstrate compliance withthermal-mechanical acceptance criteria.Table G-1 summarizes the percent margin to the Thermal Overpower and Mechanical Overpoweracceptance criteria.As referenced in Appendix F the void history bias was incorporated into the transient model within theTRACG04 code, and therefore the 10 percent margin to the fuel centerline melt and the 1 percentcladding circumferential plastic strain acceptance criteria is no longer required.Page 59 Nine Mile Point 2 000N2528-SRLRReload 14 Revision 1Table G-1 Margin to the Thermal Overpower and Mechanical Overpower Acceptance CriteriaCriteria GE14CThermal Overpower 28.5%Mechanical Overpower 14.9%Limitation and Condition 9.17 (Steady-State 5 Percent Bypass Voiding)Limitation and Condition 9.17 states:"The instrumentation specification design bases limit the presence of bypass voiding to 5percent (LRPM (sic) levels). Limiting the bypass voiding to less than 5 percent for longterm steady operation ensures that instrumentation is operated within the specification.For EPU and MELLLA + operation, the bypass voiding will be evaluated on a cycle-specific basis to confirm that the void firaction remains below 5 percent at all LPRMlevels when operating at steady-state conditions within the MELLLA + upper boundary.The highest calculated bypass voiding at any LPRM level will be provided with the plant-specific SRLR. "The bypass voiding was evaluated for the licensed core loading and confirmed that the bypass voidfraction remained below 5 percent at all LPRM levels when operating at steady-state conditions withinthe licensed upper boundary.Limitation and Condition 9.18 (Stability Setpoints Adjustment)Limitation and Condition 9.18 states:"The NRC staff concludes that the presence bypass voiding at the low-flow conditionswhere instabilities are likely can result in calibration errors of less than 5 percent forOPRM cells and less than 2 percent for APRM signals. These calibration errors must beaccounted for while determining the setpoints for any detect and suppress long termmethodology. The calibration values for the different long-term solutions are specified inthe associated sections of this SE, discussing the stability methodology. "The OPRM system will incorporate a 5% calibration error on the OPRM setpoints to address the bypassvoiding uncertainty at low-flow conditions. This calibration error has been included in the OPRMamplitude setpoints. However, the APRM calibration error required by this limitation and condition isnot applicable.Page 60 Nine Mile Point 2 000N2528-SRLRReload 14 Revision 1Limitation and Condition 9.19 (Void-Quality Correlation 1)Limitation and Condition 9.19 states:"For applications involving PANCEA(sic)/ODYN/ISCORITASC for operation at EPUand MELLLA +, an additional 0.01 will be added to the OLMCPR, until such time thatGE expands the experimental database supporting the Findlay-Dix void-qualitycorrelation to demonstrate the accuracy and petformance of the void-qualitv correlationbased on experimental data representative of the current fuel designs and operatingconditions during steady-state, transient, and accident conditions."The OLMCPR limitation requiring an additional 0.01 adder on the OLMCPR does not apply to EPU orMELLLA+ licensing calculations when TRACG04 methods are used (Reference G-2). Therefore, theOLMCPR adder is not applied to Nine Mile Point 2 Cycle 15.References for Appendix GG-1.Applicability of GE Methods to Expanded Operating Domains, NEDC-33173P-A, Revision 4,November 2012.G-2. Migration to TRACG04 / PANA ClI firom TRACG02 / PANACIO for TRACG AO0 and ATWSOverpressure Transients, NEDE-32906P, Supplement 3-A, Revision 1, April 2010.Page 61 Nine Mile Point 2Reload 14000N2528-SRLRRevision IAppendix HList of AcronymsAcronym DescriptionACPR Delta Critical Power RatioAk Delta k-effective2RPT (2PT) Two Recirculation Pump TripADS Automatic Depressurization SystemADSOOS Automatic Depressurization System Out of ServiceAOO Anticipated Operational OccurrenceAPRM Average Power Range MonitorARTS APRM, Rod Block and Technical Specification Improvement ProgramBOC Beginning of CycleBSP Backup Stability ProtectionBWROG Boiling Water Reactor Owners GroupCOLR Core Operating Limits ReportCPR Critical Power RatioDIRPT Delta MCPR over Initial MCPR for a two-Recirculation Pump TripDIVOM Delta CPR over Initial MCPR vs. Oscillation MagnitudeDR Decay RatioDS/RV Dual Mode Safety/Relief ValveECCS Emergency Core Cooling SystemELLLA Extended Load Line Limit AnalysisEOC End of Cycle (including all planned cycle extensions)EOR End of Rated (All Rods Out 100%Power / 100%Flow / NFWT)EPU Extended Power UprateER Exclusion RegionFFWTR Final Feedwater Temperature ReductionFMCPR Final MCPRFOM Figure of MeritFWCF Feedwater Controller FailureFWHOOS Feedwater Heaters Out of ServiceFWTR Feedwater Temperature ReductionGESTAR General Electric Standard Application for Reactor FuelGETAB General Electric Thermal Analysis BasisGSF Generic Shape FunctionHAL Haling BumHBB Hard Bottom BumHBOM Hot Bundle Oscillation MagnitudeHCOM Hot Channel Oscillation MagnitudeHFCL High Flow Control LineHPCI High Pressure Coolant InjectionICA Interim Corrective ActionICF Increased Core FlowPage 62 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1Acronym DescriptionIMCPR Initial MCPRIVM Initial Validation MatrixKf Off-rated flow dependent OLMCPR multiplierKp Off-rated power dependent OLMCPR multiplierL8 Turbine Trip on high water level (Level 8)LCF Low Core FlowLHGR Linear Heat Generation RateLHGRFACf Off-rated flow dependent LHGR multiplierLHGRFACp Off-rated power dependent LHGR multiplierLOCA Loss of Coolant AccidentLOSC Loss of Stator CoolingLPRM Local Power Range MonitorLRHBP Load Rejection with Half BypassLRNBP Load Rejection without BypassLTR Licensing Topical ReportMAPFACf Off-rated flow dependent MAPLHGR multiplierMAPFACp Off-rated power dependent MAPLHGR multiplierMAPLHGR Maximum Average Planar Linear Heat Generation RateMCPR Minimum Critical Power RatioMCPRf Off-rated flow dependent OLMCPRMCPRp Off-rated power dependent OLMCPRMELLLA Maximum Extended Load Line Limit AnalysisMELLLA+ MELLLA PlusMOC Middle of CycleMRB Maximal Region BoundariesMSF Modified Shape FunctionMSIV Main Steam Isolation ValveMSIVOOS Main Steam Isolation Valve Out of ServiceMSR Moisture Separator ReheaterMSROOS Moisture Separator Reheater Out of ServiceMTU Metric Ton UraniumMWd Megawatt dayMWd/ST Megawatt days per Standard TonMWd/MT Megawatt days per Metric TonMWt Megawatt ThermalN/A Not ApplicableNBP No BypassNCL Natural Circulation LineNFWT Normal Feedwater TemperatureNOM Nominal BumNTR Normal Trip ReferenceOLMCPR Operating Limit MCPROOS Out of ServicePage 63 Nine Mile Point 2D, I A IA000N2528-SRLRV 1Acronym DescriptionOPRM Oscillation Power Range MonitorPbypass Reactor power level below which the TSV position and the TCV fastclosure scrams are bypassedPdome Peak Dome PressurePsI Peak Steam Line PressurePv Peak Vessel PressurePCT Peak Clad TemperaturePHE Peak Hot ExcessPLHGR Peak Linear Heat Generation RatePLU Power Load UnbalancePLUOOS Power Load Unbalance Out of ServicePRFDS Pressure Regulator Failure DownscalePROOS Pressure Regulator Out of ServiceQ/A Heat FluxRBM Rod Block MonitorRC Reference CycleRCF Rated Core FlowRFWT Reduced Feedwater TemperatureRPS Reactor Protection SystemRPT Recirculation Pump TripRPTOOS Recirculation Pump Trip Out of ServiceRV Relief ValveRVM Reload Validation MatrixRWE Rod Withdrawal ErrorSC Standard CycleSL Safety LimitSLMCPR Safety Limit Minimum Critical Power RatioSLO Single Loop OperationSRLR Supplemental Reload Licensing ReportS/RV (SRV) Safety/Relief ValveSRVOOS Safety/Relief Valve(s) Out of ServiceSS Steady StateSSV Spring Safety ValveSTU Short Tons (or Standard Tons) of UraniumTBSOOS Turbine Bypass System Out of ServiceTBV Turbine Bypass ValveTBVOOS Turbine Bypass Valves Out of ServiceTCV Turbine Control ValveTCVOOS Turbine Control Valve Out of ServiceTCVSC Turbine Control Valve Slow ClosureTLO Two Loop OperationTRF Trip Reference FunctionTSIP Technical Specifications Improvement ProgramTSV Turbine Stop ValvePage 64 Nine Mile Point 2Reload 14000N2528-SRLRRevision 1Acronym DescriptionTSVOOS Turbine Stop Valve Out of ServiceTT Turbine TripTTHBP Turbine Trip with Half BypassTTNBP Turbine Trip without BypassUB Under BumPage 65