ML13358A373

Monticello - Enclosure 1, Reload 26 Cycle 27 Supplemental Reload Licensing Report, 000N0154-SRLR, Revision 5, Extended Power Uprate and Maximum Extended Load Line Limit Plus

ML13358A373
Person / Time
Site:	Monticello
Issue date:	12/31/2013
From:	Global Nuclear Fuel - Americas
To:	Office of Nuclear Reactor Regulation
References
L-MT-13-126, TAC ME3145 000N0154-SRLR, Rev. 5
Download: ML13358A373 (51)

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L-MT-1 3-126ENCLOSURE 1MONTICELLO NUCLEAR GENERATING PLANTRELOAD 26 CYCLE 27 SUPPLEMENTAL RELOAD LICENSING REPORT,000N0154-SRLR, REVISION 5EXTENDED POWER UPRATE (EPU)ANDMAXIMUM EXTENDED LOAD LINE LIMIT PLUS (MELLLA+)50 pages follow GN.FGlobal Nuclear FuelA Joint Venture of GE, Toshiba, & Hitachi000N0154-SRLRRevision 5Class IDecember 2013Supplemental Reload Licensing ReportforMonticelloReload 26 Cycle 27Extended Power Uprate (EPU)andMaximum Extended Load Line Limit Plus (MELLLA+)Copy'right 2013 Global Nuclear Fuel-A ruericas, LLCAll Rights Reserved Monticello 00ON0154-SRLRReload 26 Revision 5Important Notice Regarding Contents of This ReportPlease Read CarefullyThis report was prepared by Global Nuclear Fuel -Americas, LLC (GNF-A) solely for use by NorthernStates Power Company (NSP) ("Recipient") in support of the operating license for Monticello (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.This report supports the licensing work done for the Nuclear Plant EPU/MELLLA+ license. This reloaddesign was initiated prior to the PRIME transition commitment to utilize PRIME for reload analyses. Thecycle-specific reload analyses are based on GESTR-M, with one exception, and the PCT impact ofPRIME was evaluated as part of 10 CFR 50.46 Error Notification 2012-01. The one exception is theDSS-CD BSP analysis, which was performed using PRIME. The use of PRIME for the DSS-CD BSPanalysis is consistent with NEDO-33173 Supplement 4-A, Rev. 1, "Implementation of PRIME Modelsand Data in Downstream Methods," November 2012.Page 2 Monticello 00ON0154-SRLRReload 26 Revision 5AcknowledgementThe engineering and reload licensing analyses, which form the technical basis of this SupplementalReload Licensing Report, were performed by GNF-A/GEH Nuclear Analysis personnel. The revision ofthe Supplemental Reload Licensing Report was prepared by J. Su. This revised document has beenverified by L. Leatherwood.Page 3 Monticello 000N0154-SRLRReload 26 Revision 5Table of Contents1. Plant Unique Items 52. Reload Fuel Bundles 63. Reference Core Loading Pattern 64. Calculated Core Effective Multiplication and Control System Worth 75. Standby Liquid Control System Shutdown Capability 76. Reload Unique GETAB AOO Analysis -Initial Condition Parameters 77. Selected Margin Improvement Options 88. Operating Flexibility Options 99. Core-wide AOO Analysis Results, 910. Rod Withdrawal Error AOO Summary 1011. Cycle SLMCPR and OLMCPR Summary 1112. Overpressurization Analysis Summary 1213. Fuel Loading Error Results 1214. Control Rod Drop Analysis Results 1315. Stability Analysis Results 1316. Loss-of-Coolant Accident Results 16Appendix A Analysis Conditions 29Appendix B Thermal-Mechanical Compliance 30Appendix C Decrease in Core Coolant Temperature Event 31Appendix D Off-Rated Limits 32Appendix E Mislocated Fuel Loading Error 37Appendix F Turbine Trip with Bypass and Degraded Scram 38Appendix G Monticello Non-Standard SRLR Items 39Appendix H TRACG04 AOO Supplementary Information 41Appendix I NEDC-33173P-A Supplementary Information 42Appendix J MELLLA+ Supplementary Information 46Appendix K List of Acronyms 47Page 4 Monticello 00ON0154-SRLRReload 26 Revision 5The basis for this report is General Electric Standard Application for Reactor Fuel, NEDE-2401 I-P-A-19, May 2012; and the U.S. Supplement, NEDE-2401 1-P-A-19-US, May 2012.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 0000-0146-5423-FBIR.1. Plant Unique ItemsAppendix A: Analysis ConditionsAppendix B: Thermal-Mechanical ComplianceAppendix C: Decrease in Core Coolant Temperature EventAppendix D: Off-Rated LimitsAppendix E: Mislocated Fuel Loading ErrorAppendix F: Turbine Trip with Bypass and Degraded ScramAppendix G: Monticello Non-Standard SRLR ItemsAppendix H: TRACG04 AOO Supplementary InformationAppendix I: NEDC-33173P-A Supplementary InformationAppendix J: MELLLA+ Supplementary InformationAppendix K: List of AcronymsPage 5 MonticelloReload 26000N0154-SRLRRevision 52. Reload Fuel BundlesCycle NumberFuel Type LoadedIrradiated:GE 14-P 1ODNAB392-16GZ- 100T- 45-T6-2931 (GE 14C) 24 9GE14-PI0DNAB392-17GZ-1OOT-145-T6-2932 (GE14C) 24 11GE 14-P10DNAB392-16GZ-1OOT-145-T6-2931 (GE14C) 25 40GE 14-P1 0DNAB424-14GZ-1 OOT-145-T6-3 100 (GE 14C) 25 16GE 14-PIODNAB375-16GZ-100T- 145-T6-3101 (GE 14C) 25 52GE 14-P1ODNAB392-16GZ-1OOT-145-T6-3102 (GE 14C) 25 40GE14-P1ODNAB391-12GZ-100T-145-T6-3 103 (GE14C) 25 16GE 14-PIODNAB373-16GZ-1OOT-145-T6-3375 (GE14C) 26 32GE 14-PI ODNAB391-16GZ-1OOT-145-T6-3376 (GE14C) 26 40GEl 4-PI ODNAB391-15GZ-1OOT-145-T6-3377 (GE14C) 26 32GE 14-PI ODNAB391-12GZ-1OOT-145-T6-3378 (GE 14C) 26 44New:GE 1 4-P I ODNAB389-11 GZ- 100T- 145-T6-4178 (GE 14C) 27 24GE 14-P1ODNAB386-16GZ-1OOT-145-T6-4177 (GE14C) 27 24GE 14-PIODNAB386-16GZ-100T-145-T6-4176 (GE14C) 27 48GE 14-P1ODNAB372-17GZ-1OOT-145-T6-4175 (GE14C) 27 56Total: 1 4843. Reference Core Loading PatternCore Average Cycle ExposureExposure30776 MWd/MT 12595 MWd/MTNominal previous end-of-cycle exposure: (27919 MWd/ST) (11426 MWd/ST)Minimum previous end-of-cycle exposure (for cold 30326 MWd/MT 12145 MWd/MTshutdown considerations): (27511 MWd/ST) (11018 MWd/ST)17040 MWd/MT 0 MWd/MTAssumed reload beginning-of-cycle exposure: (15459 MWd/ST) (0 MWd/ST)Assumed reload end-of-cycle exposure (rated 30929 MWd/MT 13889 MWd/MTconditions): (28059 MWd/ST) (12600 MWd/ST)Reference core loading pattern: Figure 1Page 6 MonticelloRelnad 9.00ON0154-SRLRReviqinn SReload 264. Calculated Core Effective Multiplication and Control System WorthBeginning of Cycle, keffectiveUncontrolled (20'C) 1.110Fully controlled (20'C) 0.955Strongest control rod out (most reactive condition, 20'C) 0.987R, 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 CapabilityShutdown Margin (Ak)Boron (ppm) (at 1601C, Xenon Free)Analytical Requirement Achieved660 >0.010 0.0216. Reload Unique Anticipated Operational Occurrences (AOO) Analysis Initial ConditionParametersOperating domain: ICF (HBB)Exposure range : BOC to EOC (Application Condition: 1)Peaking FactorsFuel Bundle Bundle InitialDesign Local Radial Axial R-Factor Power FlowDesign___ _(MWt) (1000 lb/hr) MCPRGE14C 1.0 1.42 1.42 0.974 5.877 112.8 1.76Operating domain: LCF (HBB)Exposure range : BOC to EOC (Application Condition: 1)Peaking FactorsFuel Bundle Bundle InitialDesign Local Radial Axial R-Factor Power FlowDesign___ _(MWt) (1000 lb/hr) MCPRGE14C 1.0 1.44 1.32 0.975 5.966 83.8 1.58Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.Page 7 MonticelloReload 2600ON0154-SRLRRevision 5Operating domain: ICF (UB)Exposure range : BOC to EOC (Application Condition: 1)Peaking FactorsFuel Bundle Bundle InitialDesign Local Radial Axial R-Factor Power FlowDesign__ __(MWt) (1000 lb/hr) MCPRGE14C 1.0 1.41 1.25 0.974 5.839 111.2 1.87Operating domain: LCF (UB)Exposure range BOC to EOC (Application Condition: 1)Peaking FactorsFuel Bundle Bundle InitialDesign Local Radial Axial R-Factor Power FlowDesign__ __(MWt) (1000 lb/hr) MCPRGE14C 1.0 1.40 1.35 0.975 5.798 83.2 1.697. 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:NoNoYesYes(Option B)NoNoI2 Refer to the GESTAR basis document identified at the beginning of this report for the margin improvementoptions currently supported therein.Page 8 Monticello OOONO 1 54-SRLRReload 26 Revision 5Table 7-1 Cycle Exposure Range DesignationName Exposure Range 3BOC to EOC BOC27 to EOC278. 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: Extended Power Uprate (EPU)Maximum Extended Load Line Limit Plus (MELLLA+)Minimum core flow at rated power: 80.0 %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 5 valves)PROOS Yes9. Core-wide AOO Analysis Results 5,6Methods used: GEXL-PLUS, TRACG043 End of Rated (EOR) is defined as the cycle exposure corresponding to all rods out, 100% power/]00% flow, andnormal feedwater temperature. For plants without mid-cycle OLMCPR points, EOR is not applicable.4 Refer to the GESTAR basis document identified at the beginning of this report for the operating flexibility optionscurrently supported therein.5 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 9 MonticelloReload 2600ON0154-SRLRRevision 5Operating domain: ICF (UB)Exposure range : BOC to EOC (Application Condition: 1)Uncorrected ACPRIICPREvent Flux STP GE14C Fig.(% rated) (% rated) GE14CFig.FW Controller Failure 548.5 114.4 0.238 2Turbine Trip with Bypass 621.3 110.3 0.291 3Turbine Trip w/o Bypass 550.8 108.5 0.228 4Load Rejection w/o Bypass 335.4 106.2 0.169 5Inadvertent HPCI /L8 530.8 120.5 0.248 610. Rod Withdrawal Error AOO SummaryThe Rod Withdrawal Error (RWE) event was analyzed in the GE BWR Licensing Topical ReportAverage Power Range Monitor, Rod Block Monitor and Technical Specification Improvement (ARTS)Program for Monticello Nuclear Generating Plant, NEDC-30492-P, April 1984.RWE Results:RBM Setpoint (%) ACPR114.0 0.25The 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 ITSP and LTSP MCPR limits associated with the HTSP reported in the above table are bounded bythe Kp limits for this cycle.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%: MCPR > 1.70For Power 90%: MCPR > 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.Page 10 MonticelloReload 26000N0154-SRLRRevision 511. Cycle SLMCPR and OLMCPR Summary 7 8 9Two Loop Operation (TLO) safety limit: 1.15Single Loop Operation (SLO) safety limit: 1.15Stability MCPR Design Basis:EGGS MCPR Design Basis:Non-pressurization Events:See Section 15See Section 16 (Initial MCPR)Exposure range: BOG to EOCAll Fuel TypesRod Withdrawal Error (114.0 % RBM Setpoint) 1.40Loss of Feedwater Heating 1.34Fuel Loading Error (Mislocated) Not LimitingFuel Loading Error (Misoriented) 1.37Rated Equivalent SLO Pump Seizure 10 1.45Limiting Pressurization Events OLMCPR Summary Table: "Appl.Cond. Exposure Range Option A Option BGE14C GE14C1 Base CaseBOC to EOC 1.74 1.627 Exposure range designation is defined in Table 7-1.8 For SLO, the MCPR operating limit is equal to the two loop value.9 The safety limit values presented include a 0.03 adder in accordance with extended operating domain licensingcommitments up to and including operation in the MELLLA+ operating domain.'0 The cycle-independent OLMCPR for the recirculation pump seizure event for GE14C is 1.62 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 1.45. 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 11 MonticelloD I oA r,00ON0154-SRLRP-,QrA";nnPressurization Events:"2Operating domain: ICF (UB)Exposure range : BOC to EOC (Application Condition: 1)Option A Option BGEI4C GE14CFW Controller Failure Not Limiting Not LimitingTurbine Trip with Bypass 1.62 1.62Turbine Trip w/o Bypass Not Limiting Not LimitingLoad Rejection w/o Bypass Not Limiting Not LimitingInadvertent HPCI /L8 1.74 1.5412. Overpressurization Analysis Summary "Event PsI Pdome Pv Plant(psig) (psig) (psig) ResponseMSIV Closure (Flux Scram) -ICF (1-BB) 1321 1327 1351 Figure 7MSIV Closure (Flux Scram) -LCF (HBB) 1306 1312 1333 Figure 813. Fuel Loading Error ResultsVariable water gap misoriented bundle analysis: Yes 14Misoriented Fuel Bundle ACPRGE 14-PI ODNAB373-16GZ-1OOT-145-T6-3375 (GE14C) 0.21GE 14-PIODNAB391-16GZ-1OOT-145-T6-3376 (GE14C) 0.15GE14-PI ODNAB391-15GZ-100T-145-T6-3377 (GE14C) 0.07GE14-P1ODNAB391-12GZ-1OOT-145-T6-3378 (GE14C) 0.15GE14-P1ODNAB372-17GZ-1OOT-145-T6-4175 (GE14C) 0.21GE14-PIODNAB386-16GZ-1OOT-145-T6-4176 (GE14C) 0.18GE 14-P 1ODNAB386-16GZ- 1OOT-145-T6-4177 (GE 14C) 0.22GE I4-PI ODNAB389-11GZ-I OOT- 145-T6-4178 (GE 14C) 0.2012 Application condition numbers shown for each of the following pressurization events representconditions for which this event contributed in the determination of the limiting OLMCPR value.3 Overpressure calculated at an initial dome pressure of 1010 psig.14 Includes a 0.02 penalty due to variable water gap R-factor uncertainty.the applicationPage 12 Monticello 00ON0154-SRLRReload 26 Revision 514. Control Rod Drop Analysis ResultsThis is a banked position withdrawal sequence plant, therefore, the control rod drop accident analysis isnot required. NRC approval is documented in NEDE-2401 l-P-A-19-US.15. Stability Analysis ResultsNorthern States Power Company is seeking approval for operating Monticello in the MELLLA+operating domain, which would provide greater core flow flexibility, particularly as power approaches120% of the Original Licensed Thermal Power. SLO will not be allowed in conjunction with operation inthe MELLLA+ domain. Implementation of MELLLA+ operating domain requires the use of the Detectand Suppress Solution -Confirmation Density (DSS-CD) stability solution. Stability results foroperation at EPU with MELLLA+ and DSS-CD are contained in this section.15.1 Stability DSS-CD SolutionMonticello will implement the stability DSS-CD solution using the Oscillation Power Range Monitor(OPRM) as described in Reference 1 in Section 15.4. Plant-specific analyses for the DSS-CD Solutionare provided in Reference 2 in Section 15.4. The Detect and Suppress function of the DSS-CD solutionbased on the OPRM system relies on the Confirmation Density Algorithm (CDA), which constitutes thelicensing basis. The Backup Stability Protection (BSP) solution may be used by the plant in the event thatthe OPRM system is declared inoperable.The CDA enabled through the OPRM system and the BSP solution described in Reference 2 in Section15.4 provide the stability licensing bases for Monticello Cycle 27. The safety evaluation report forReference I in Section 15.4 concluded that the DSS-CD solution is acceptable subject to certain cycle-specific limitations and conditions. These cycle-specific limitations and conditions are met forMonticello Cycle 27.15.2 Detect and Suppress EvaluationA reload DSS-CD evaluation has been performed in accordance with the licensing methodologydescribed in Reference 1 in Section 15.4 to confirm the Amplitude Discriminator Setpoint (SAD) of theCDA established in Reference 2 in Section 15.4. The Cycle 27 DSS-CD evaluation and the results for theDSS-CD Reload Confirmation Applicability Checklist documented in Table 15-1 demonstrate that: 1) theDSS-CD Solution is applicable to Monticello Cycle 27; and, 2) the SAD=I.10 established in Reference 2in Section 15.4 is confirmed for operation of Monticello Cycle 27.The SAD=I. 10 setpoint is applicable to TLO and to SLO.Page 13 MonticelloReload 2600ON0154-SRLRRevision 5Table 15-1 DSS-CD Reload Confirmation Applicability ChecklistMonticelloParameter DSS-CD Criterion Cycle 27 Results AcceptanceBWR Product Line BWR/3-6 design BWR/3 ConfirmedFuel Product Line GE14 and earlier GE designs GEl4 Confirmedý EPU/MELLLA+ including EPU/MELLLA+Operating Domain currently licensed operational including currently Confirmed(TLO) flexiblity features licensed operationalflexibility features flexibility featuresEPU/MELLLAOperating Domain c EPU/MELLLA including including currently Confirmed(SLO) currently licensed operational licensed operationalflexibility features flexibility features< 120°F (EPU/MELLLA)Rated TFw Reduction No TFw Reduction No TFw Reduction Confirmed(MELLLA+ Extension)Margin for TLO(see Table 2-2 in see Table 2-2 in Reference 2 0.29 ConfirmedReference 2 in Section in Section 15.415.4)Margin for SLO(see Table 2-2 in see Table 2-2 in Reference 2 0.37 ConfirmedReference 2 in Section in Section 15.415.4)15.3 Backup Stability ProtectionReference 1 in Section 15.4 describes two BSP options that are based on selected elements from threedistinct constituents: BSP Manual Regions, BSP Boundary, and Automated BSP (ABSP) setpoints.The Manual BSP region boundaries and the BSP Boundary were calculated for Monticello Cycle 27 fornormal feedwater temperature operation. The endpoints of the regions are defined in Table 15-2. TheScram Region boundary, the Controlled Entry Region boundary, and the BSP Boundary are shown inPage 14 Monticello0 1 A 1A00ON0154-SRLRD. ; "- 1;MnIcel -ON v5- RLFigure 9.The ABSP APRM Simulated Thermal Power setpoints associated with the ABSP Scram Region fromReference 3 are confirmed for Cycle 27 and are defined in Table 15-3. These ABSP setpoints bound bothTLO and SLO.Table 15-2 BSP Endpoints for Normal Feedwater TemperatureEndpoint Power Flow DefinitionEndpint (%) (%)Scram RegionBoundary, HFCLBI 42.6 33.7 Scram RegionBoundary, NCLControlled EntryA2 83.6 58.9 Region Boundary,HFCLB2 28.6 31.2 Controlled EntryRegion Boundary, NCLA3 100.0 85.2 BSP BoundaryIntercept, HFCLBSP BoundaryB3 75.3 57.4 Intercept, MELLLA+Boundary at MinimumFlowPage 15 MonticelloReload 26000N0154-SRLRRevision 5Table 15-3 ABSP Setpoints for the Scram RegionParameter Symbol ValueSlope of ABSP APRM flow-m 1.30biased trip linear segment.ABSP APRM flow-biased tripsetpoint power intercept.Constant Power Line for Trip PBSP-TRIP 38.0 % RTP*from zero Drive Flow to FlowBreakpoint value.ABSP APRM flow-biased tripsetpoint drive flow intercept. WBSP.TRJP 55.8 % RDF**Constant Flow Line for Trip.Flow Breakpoint value WBSP.BREAK 37.9 % RDF*** RTP -Rated Thermal Power** RDF -Recirculation Drive Flow15.4 References1. General Electric Boiling Water Reactor Detect and Suppress Solution -Confirmation DensitV,NEDC-33075P-A, Revision 6, January 2008.2. Safey Analysis Report for Monticello Maximum Extended Load Line Limit Analysis Plus,NEDC-33435P, Revision 1, December 2009.3. Instrument Limits Calculation, Northern States Power -Minnesota (NSPM). MonticelloNuclear Generating Plant, Average Power Range Monitor NUMAC PRNM Setpoints -MELLLA+ Automnatic Backup Stabilit, Protection (ABSP), 0000-0105-4810-R2 MNGP-M+ABSP-APRM-Calc-2009-P, Revision 2, June 2011.16. Loss-of-Coolant Accident Results 1516.1 1OCFR50.46 Licensing ResultsThe ECCS-LOCA analysis is based on the SAFER/GESTR-LOCA methodology. The licensing results inthe new cycle are summarized in the following table.'5 Lattice numbers are defined in the Fuel Bundle Infornation Report, 0000-0146-5423-FBIR.Page 16 Monticello000N0154-SRLRR~vidinn 'Pplnnrl 26 Revision 5Table 16.1-1 Licensing ResultsCore-WideLicensing Local Me-WateFuel Type Basis PCT Oxidation Re atio(OF) Reaction(°F) (%) (%)GE14C 2140 <10.00 < 0.20The SAFER/GESTR-LOCA analysis results for GE14C are documented in Reference 1 for EPU andReference 2 for MELLLA+ in Section 16.4.The RHR intertie open line analysis is documented in Reference 3 for GEI4C in Section 16.4. Reference1 for GE14C extends the Reference 3 analysis to EPU. Reference 2 for GE14C extends the Reference 3analysis to MELLLA+. These analyses indicate that plant operation up to 376 MWt with the RHR intertieline open is acceptable from an ECCS performance standpoint, provided a MAPLHGR multiplier of 0.75is implemented or that the peak bundle power does not exceed 3.9 MWt.In addition to the power and flow dependent multipliers, Monticello also requires an ECCS MAPLHGRmultiplier of 0.9908 for operation at or below 99% core flow. This multiplier ensures that the off-ratedlimits assumed in the EPU ECCS-LOCA analyses bound the cycle-specific off-rated limits calculated forMELLLA+ operation.For GE 14C, the large break Appendix K ECCS-LOCA result at EPU power and MELLLA+ core flow is2123°F as documented in Reference 2. The large break Appendix K ECCS-LOCA result at EPU powerand rated core flow is 2119'F as documented in Reference 1.16.2 10CFR50.46 Error EvaluationThe 1OCFR50.46 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 Impact(OF)2012-01 PRIME Code Implementation for Fuel Rod T/M +10PeTforaance, Replacing GESTRTotal PCT Adder (Ff) +0Page 17 MonticelloReload 2600ON0154-SRLRRevision 5After accounting for the error impact, the GEI4C Licensing Basis PCT remains below the IOCFR50.46limit of 2200'F, the Local Oxidation remains below the I OCFR50.46 limit of 17%, and the Core-WideMetal-Water Reaction remains below the 1OCFR50.46 limit of 1%.16.3 ECCS-LOCA Operating LimitsThe ECCS-LOCA composite MAPLHGR operating limits for all fuel bundles in thisEPU/MELLLA+ analysis are identical to the EPU MAPLHGR operating limits provided in theMonticello Cycle 27 EPU SRLR as documented in Reference 4.The core monitoring system monitors LHGR limits and ECCS-LOCA MAPLHGR limits separately;therefore, the new ECCS-LOCA MAPLHGR limits shown in Reference I for GEI4C in Section 16.4 areunaffected by changes to the LHGR curve, and application of the GE14L-B36-G7-IMLTR LHGR curveis acceptable from the ECCS-LOCA perspective.The single loop operation multiplier on MAPLHGR and the ECCS-LOCA analytical initial MCPR valuesapplicable to GE 14C fuel type in the new cycle core are shown in the following table.Table 16.3-15 Initial MCPR and Single Loop Operation Multiplier on MAPLHGRFuel Type Initial MCPR Single Loop OperationMultiplier on MAPLHGRGE14C 1.350 0.83The GE14C SLO multiplier applies to the EPU operating domain only, and SLO operation in theMELLLA+ domain is not permitted.Monticello has an ECCS-LOCA PLHGR of 11.62 kW/ft for GEI4C fuel type.16.4 ReferencesThe SAFER/GESTR-LOCA analysis base reports applicable to the new cycle core are listed below.Page 18 Monticello 00ON0154-SRLRReload 26 Revision 5References for GE14C1. Project Task Report Nuclear Management Company, LLC (NMC) Monticello NuclearGenerating Plant Extended Power Uprate Task T0407: ECCS-LOCA SAFER/GESTR, GE-NE-0000-0060-9286-TR-R2, Revision 2, October 2011.2. Project Task Report Northern States Power -Minnesota (NSPM) Monticello NuclearGenerating Plant MELLLA + Task T0407: ECCS-LOCA SAFER/GESTR, 0000-0096-6889-TR-R1, Revision 1, October 2011.3. Monticello Nuclear Plant GEl4 ECCS-LOCA Evahlation with the RHR Intertie Line Open,NSA 01-459, October 10, 2001.4. Supplemental Reload Licensing Report for Monticello Reload 26 Cicle 27 Extended Power"Uprate (EPU), 0000-0146-5423-SRLR-R3, October 2013.Page 19 MonticelloR elnad 00ON0154-SRLRPpvicinn5Reload 26 Revision 5525o484644424038363432302826242220181614121086425 116 99 109 106 95 116 79 109 9 11 139 9 14 207 15 20 108 15 18 1810 20 19 1514 18 18 1213 18 12 1713 18 12 1714 18 18 1210 20 19 158 15 18 187 15 20 109 2 14 209 9 11 139 106 75 6 9 9 6 511 9 10 10 9 119 9 7 8 10 3 13 13 14 109 9 15 15 20 18 18 18 18 2011 14 20 18 19 18 12 12 18 1913 20 10 18 15 12 17 17 12 157 18 19 14 17 7 15 15 7 1718 15 14 17 15 17 8 8 17 1519 14 10 13 17 10 12 12 10 1714 17 13 7 13 17 7 7 17 1317 15 17 13 17 12 19 19 12 177 17 10 17 12 17 13 13 17 1215 8 12 7 19 13 7 7 13 1915 8 12 7 19 13 7 7 13 197 17 10 17 12 17 13 13 17 1217 15 17 13 17 12 19 19 12 1714 17 13 7 13 17 7 7 17 1319 14 10 13 17 10 12 12 10 1718 15 14 17 15 17 8 8 17 157 18 19 14 17 7 15 15 7 1713 20 10 18 15 12 17 17 12 1511 14 20 18 19 18 12 12 18 199 9 15 15 20 18 18 18 18 209 9 7 8 10 14 13 13 3 1011 9 10 10 9 115 6 9 9 6 58 7 9 915 15 9 918 20 14 11 9 518 10 20 13 10 914 19 18 7 13 11 917 14 15 18 20 14 113 10 14 19 10 20 157 13 17 14 18 18 1513 17 15 17 15 19 2017 10 17 7 12 18 187 12 8 15 17 12 187 12 8 15 17 12 1817 10 17 7 12 18 1813 17 15 17 15 19 207 13 17 14 18 18 1513 10 14 19 10 20 1517 14 15 18 20 14 914 19 18 7 13 11 918 10 20 13 10 918 20 14 11 7 615 15 9 98 7 9 999781014131314108799119101091156991651 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51Fuel TypeI=GE 14-P 010DNAB392-16GZ- I GOT-I 45-T6-2931 (Cycle 25) 12=GEI 4-P)lODNAB373-16GZ- I OOT-145-T6-3375 (Cycle 26)2=GE I 4-Pl 0DNAB375-16GZ-1 OT-1 45-T6-3 101 (Cycle 25) 13=GEI 4-PIODNAB391-16GZ-I0OT-145-T6-3376 (Cycle 26)3=GE 14-P I ODNAB391-15GZ- I OT-145-T6-3377 (Cycle 26) 14=GE14-PI ODNAB391-15GZ- I OT-145-T6-3377 (Cycle 26)5=GE14-PIODNAB392-16GZ-l OOT-145-T6-2931 (Cycle 24) 15=GE14-Pl ODNAB39 I-12GZ-1 OT-145-T6-3378 (Cycle 26)6=GE14-PIODNAB392-17GZ-IOOT-145-T6-2932 (Cycle 24) 16=GEI4-PIODNAB3 92-17GZ- I OOT-145-T6-2932 (Cycle 24)7=GEI 4-P I 0DNAB392-16GZ-0 OT-145-T6-2931 (Cycle 25) 17-GE= 4-PIODNAB372-17GZ- 10OT-145-T6-4175 (Cycle 27)8=GE 14-P I1DNAB424-14GZ- I OT-145-T6-3 100 (Cycle 25) 18=GE0 4-PF ODNAB386-16GZ- I GOT-1 45-T6-4176 (Cycle 27)9=GE 14-P 1GDNAB375-16GZ- I 0T-145-T6-3 101 (Cycle 25) 19=GE0 4-PF ODNAB386-16GZ-IOOT-145-T6-4177 (Cycle 27)10=GE 14-PIODNAB392-16GZ-10 GT-145-T6-3102 (Cycle 25) 20=GE14-PI0DNAB389-1 I GZ- IOT-145-T6-4178 (Cycle 27)1 I=GE14-PIODNAB391-12GZ-0O0T-145-T6-3103 (Cycle 25)Figure 1 Reference Core Loading PatternPage 20 MonticelloPD1,-A 14O00NO 154-SRLRSpXiAQnn r-I.- -MwCPUk...NFJCPEOC~h-Bs.Cas.U"I271401201004020I'5II13501300125012001150J110010501000 100500 5 10 15 20 25Thu. f")j 404.03.53.02.52.0I's1.00.60.0-1.0-1.5-2.0-TOW Roa**y--Stmm A***Ay-Deppler T-Paueo. Itdo"NVOW Roo*0 510 is 20 25Tkme is")5 10 15T ,kh -)2D 25Figure 2 Plant Response to FW Controller Failure(EOC ICF (UB))Page 21 Monticello1?I0H1 A 9f00ON0154-SRLRP~vikinn 'Revision 5TTUIJ4PWJlCFE-LOC~k-3aCas___00 w 0IKI27140120100ISOwt so4020012040013001200too0 1 2 3 4 5 6Tim. (s")0 1 2 3 4 5 6Thm (.)40301201110 1I0004100 1 2 3 4 5 6Time (see)0 1 2 3 4 5 aThin (a")Figure 3 Plant Response to Turbine Trip with Bypass(EOC ICF (UB))Page 22 MonticelloReload 2600ON0154-SRLRRevision 5TTNSPUB..NPWJCP..JOC4M-Ua..CasW(1KIT1401201006004020700 so600 7060600400' so~ 403001 302001350130012501200115011100105010D0100 110009500 1 2 3 4 5 aTkm (-e)0 1 2 3 4 5 6Tkm (SC)12060I4.03.53.02.52.01.51.0:05.0-0.5-1.0-1.5-2.004600 1 2 3 4 5 6..,A" Timlefts)0 1 2 3 4Trm to")aFigure 4 Plant Response to Turbine Trip w/o Bypass(EOC ICF (UB))Page 23 MonticelloRflnnd 9A00ON0154-SRLRP Revision 5NKII?14012010040200120LRNBPUSJ4PWJCP.-EOC4UU-Cas.III12001Iio0 1 2 3 4 5 aTW" (0")0 1 2 3 4 5 6Tm f"c)40so1400-403020100I-10-20-40C ImAWSAU.P 2UUVU2 3 4 5Tm losee)60 1 2 3 4 5 6Thu (-)Figure 5 Plant Response to Load Rejection w/o Bypass(EOC ICF (UB))Page 24 Monticello00ON0154-SRLRR P 1 2A Revision 5HPCHJSUSJ4FWJlCF...OC4m-Sa..Cas.EKI27140120100so4O0402001w120soj400-40560 so48W70400320' 50~ 40240j 301802D1350130012501200IOS105010O0so1009500 8 10 1S 20 25 30 35Tieh ts)0 5 10 15 20 25 30 35S("C)60 4.03.6-50 3.0i 2.51.530 1.00.5201 10.0-0.510 -1.0-1.50 -2.0TO-Mi RGOI4VS- rr Root#-Doppla Terniporabs Romel*vo Roda*4100 5 10 1s 20 25 30 35Time (See)0 5 10 1s 20 25 30 35Tme (see)Figure 6 Plant Response to Inadvertent HPCI /L8(EOC ICF (UB))Page 25 MonticelloD I AIAOOONO I 54-SRLRD , , Iz%,.kU-U LU v V*faUIi .IK127140120100so40200120so40MSIWFHBBJ4PWJlCF-OC4as...Cas.-____ 420 sosa 70300240'12020so 10 --0 a - .140040 4.03.S3.02.52.520 1.00.50°0to! -as6-1.0-1.50 -2.00 1Figure 7 Plant Response to MSIV Closure (Flux Scram) -(EOC ICF (HBB))Page 26 MonticelloID. ,l-A If,'00ON0154-SRLRMSIVH5BNPWLCFEOC4Ma.Caso2171140120100so4020012060400420 80603002401 s11401801 30120201400so o 40 0140 4.03.53.0-30 f 2.5-20 1.00.0-0.6-1.0-1.50 -2.0rim (se)3 411mg (-e)Thiw ("a)ThtOA UA pnn24:z~finn2Figure 8 Plant Response to MSIV Closure (Flux Scram) -(EOC LCF (HBB))Page 27 Monticello00ON0154-SRLRPA1,nQ;A 1;2291101009080CIO0030100Ce!, FISWW~lFigure 9 Manual BSP Regions and BSP Boundary for Normal Feedwater Temperature OperationPage 28 MonticelloReload 26000N0154-SRLRRevision 5Appendix 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 ValueICF LCFParameter NFWT NFWTThermal power, MWt 2004.0 2004.0Core flow, Mlb/hr. 60.5 46.1Reactor pressure (core mid-plane), psia 1041.0 1036.3Inlet enthalpy, Btu/lb 524.8 517.1Non-fuel power fraction"6 NA NASteam flow, Mlb/hr 8.39 8.39Dome pressure, psig 1010.2 1009.8Turbine pressure, psig 943.9 943.7Table A-2 Pressure Relief and Safety Valve ConfigurationNumber of Lowest SetpointValve Type Valves (psig)Safety/Relief Valve 8 1170 (Relief Mode)16 The non-fuel power fraction is not available from TRACG04Page 29 Monticello 00ON0154-SRLRReload 26 Revision 5Appendix BThermal-Mechanical ComplianceA thermal-mechanical compliance check is performed to assure that the fuel will operate withoutviolating the thermal-mechanical design limits. These limits are designed such that reactor operationwithin these limits provides assurance that the fuel will not exceed any thermal-mechanical design orlicensing limits during all modes of operation. The fuel thermal-mechanical limits are met for the currentcycle.Page 30 Monticello 00ON0154-SRLRReload 26 Revision 5Appendix 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 31 MonticelloReload 26000N0154-SRLRRevision 5Appendix DOff-Rated LimitsOff-Rated Power Dependent LimitsARTS power dependent thermal limits have been developed for operation with all Equipment In-Serviceand a Pressure Regulator Out-Of-Service (PROOS) in Reference D-1.The MCPRp limits provided in Reference D-I are based on a SLMCPR of 1.15.MCPRp Limits for:Base CaseLimits for Power < 40.0%Flow > 50.0% Flow < 50.0%Power (%) Limit Power (%) LimitMCPRp MCPRp25.0 3.62 25.0 2.8340.0 2.91 40.0 2.37Limits for Power _ 40.0%Power (%) LimitKp40.0 1.32360.0 1.15090.0 1.056100.0 1.000Page 32 MonticelloReload 26000N0154-SRLRRevision 5Reload 26 Revision 5MCPRp Limits for:Pressure Regulator Out-of-ServiceLimits for Power < 40.0%Flow > 50.0% Flow < 50.0%Power (%) Limit Power (%) LimitMCPRp MCPRp25.0 3.62 25.0 2.8340.0 2.91 40.0 2.37Limits for Power 40.0%Power (%) LimitKp40.0 1.55060.0 1.46085.0 1.24085.0 1.07290.0 1.056100.0 1.000LHGRFACp Limits for:Base CaseLim its for Power < 40.0%Flow > 50.0% Flow < 50.0%Power (%) Limit Power (%) Limit25.0 0.496 25.0 0.52240.0 0.519 40.0 0.638Limits for Power _ 40. 0%Power (%) Limit40.0 0.687100.0 1.000LHGRFACp Limits for:Pressure Regulator Out-of-ServiceLidits for Power < 40.0%Flow > 50.0% Flow < 50.0%Power (%) Limit Power (%) Limit25.0 0.496 25.0 0.52240.0 0.519 40.0 0.638Limits for Power _ 40.0%Power (%) Limit40.0 0.64585.0 0.82585.0 0.894100.0 1.000Page 33 Monticello00ON0154-SRLRRevisqion 5Reload 26 Revision 5MAPFACp Limits for:Base CaseLimits for Power < 40. 0%Flow > 50.0% Flow < 50.0%Power (%) Limit Power (%) Limit25.0 0.496 25.0 0.52240.0 0.519 40.0 0.638Limits for Power >_ 40. 0%Power (%) Limit40.0 0.687100.0 1.000MAPFACp Limits for:Pressure Regulator Out-of-ServiceLimits for Power < 40.0%Flow > 50.0% Flow < 50.0%Power (%) Limit Power (%) Limit25.0 0.496 25.0 0.52240.0 0.519 40.0 0.638Limits for Power _ 40. 0%Power (%) Limit40.0 0.64585.0 0.82585.0 0.894100.0 1.000Off-Rated Flow Dependent LimitsThe flow dependent ARTS thermal limits are documented in Reference D-1. The off-rated flowdependent limits provided in Reference D-1 have been validated for this cycle. The flow dependentLHGRFAC/MAPFAC limits include an ECCS-LOCA MAPLHGR limit for core flow <99.0% rated flow.The MCPRf limits provided in Reference D-1 are based on a SLMCPR of 1.15.MCPRf Limits for:Base CaseLimits for a Maximum Runout Flow of 107.0%Flow (%) LimitMCPRf30.0 1.6494.4 1.23107.0 1.23Page 34 MonticelloReload 2600ON0154-SRLRRevision 5MCPRf Limits for:Pressure Regulator Out-of-ServiceLimits for a Maximnum Runout Flow of 107.0%Flow (%) Limit__MCPRf30.0 1.6494.4 1.23107.0 1.23LHGRFACf Limits for:Base CaseLimits for a Maximntu Runout Flow of 107. 0%Flow (%) Limit30.0 0.66078.6 0.99199.0 0.99199.0 1.000107.0 1.000LHGRFACf Limits for:Pressure Regulator Out-of-ServiceLimits for a Maximnum Runout Flow of 107.0%Flow (%) Limit30.0 0.66078.6 0.99199.0 0.99199.0 1.000107.0 1.000MAPFACf Limits for:Base CaseLimits for a Maximaumt Runout Flow of 107. 0%Flow (%) Limit30.0 0.66078.6 0.99199.0 0.99199.0 1.000107.0 1.000Page 35 MonticelloReload 2600ON0154-SRLRRevision 5MAPFACf Limits for:Pressure Regulator Out-of-ServiceLimits for a Maximnum Runout Flow of 107.0%Flow (%) Limit30.0 0.66078.6 0.99199.0 0.99199.0 1.000107.0 1.000ReferenceD- 1 Monticello Nuclear Generating Plant Offirated Limits and Pressure Regulator Downscale FailureAnalysis at MELLLA+, 0000-0131-4356-RI, Revision 1, January 2012.Page 36 Monticello 00ON0154-SRLRReload 26 Revision 5Appendix EMislocated Fuel Loading ErrorThe Monticello Nuclear Generating Plant Cycle 27 Mislocated Fuel Loading Error analysis wasevaluated. The event is non-limiting for fuel types through GEl4 if the following condition is satisfied:OLMCPRI,,/,1cI > 1, / 1.07)This criterion has been demonstrated to be generically applicable to GE 14 reloads.The minimum OLMCPR calculated for Monticello Cycle 27 is 1.62 (shown in Section 11 for GEl4 fuelfrom BOC27 to EOC27) while the plant/cycle specific SLMCPR is 1.15. Using 1.15 in the equationyields 1.38 on the right side.Using these values the above equation would yield 1.62 > 1.38.Therefore, the Mislocated Fuel Loading Error is non-limiting for Monticello Cycle 27.Page 37 Monticello 00ON0154-SRLRReload 26 Revision 5Appendix FTurbine Trip with Bypass and Degraded ScramThe Turbine Trip with Bypass (TTWBP) event was analyzed with the postulated Option A degradedscram and an OLMCPR value was determined. No Option B analysis was performed for the TTWBP.The Option A calculated OLMCPR for the TTWBP is used for Option B and this value sets the OLMCPRlimit for Option B because it is higher than the most limiting OLMCPR calculated for a pressurizationevent. Therefore, if the cycle average scram time does not satisfy the criterion provided in Reference F-1and Monticello Nuclear Generating Plant decides to interpolate between Option A and Option B scramtimes, this can be accomplished by using the procedure provided in Reference F-i with the followingmodification to Equation 4 of Reference F-i:The modified equation to establish the new operating limit for pressurization events is given below:= MAX OLMCPRl B -B AOLMCPR, OLMCPRTT,..PT'4 -T'B IT '(4 )where: Ta,e and T1 are defined in Equations I and 3 of Reference F-1, respectively;TA = the technical specification limit on core average scram time to the20percent insertion positionOLMCPR Option B = the most limiting OLMCPR calculated for a pressurization event actuallyanalyzed for Option BAOLMCPR = the difference between OLMCPR Option A and OLMCPR Option BFor Monticello Cycle 27, the OLMCPRs for the HPCIL8 event are 1.74 for Option A and 1.54 for OptionB. Therefore, the AOLMCPR for the HPCIL8 event is 0.20. The OLMCPR for the TTWBP event is 1.62.This approach is cycle independent with the TTWBP analyzed in this manner as long as the cycle specificOLMCPR Option B and AOLMCPR values are used in the calculation.ReferenceF-1. Monticello Option B Licensing Basis, LRC03.040, March 24, 2003 from L. R. Conner to RickRohrer.Page 38 MonticelloReload 2600ON0154-SRLRRevision 5Appendix GMonticello Non-Standard SRLR ItemsThis appendix contains Monticello non-standard SRLR items that are being provided at the request ofXcel Energy.Additional Section 9 InformationFor the inadvertent HPCI event, the level 8 trip was modeled as the OPL-3 setpoint value. The turbinetrip signal is initiated manually after the narrow-range water level has reached equilibrium. This was donesince confirmation could not be obtained that a level 8 event would not occur during this event.Additional Section 11 InformationThe following table summarizes the cycle rated power and flow MCPR values for the events reported inthis SRLR. If the event's Option A or Option B limit are merged together in a single column, then theevent cannot be interpolated based on scram times. For a description of how to implement Option Bscram times see Appendix F.Cycle MCPR valuesExposure range: BOC27 to EOC27Option A Option BGE14C GE14CFW Controller Failure Not Limiting Not LimitingLoad Reject w/o Bypass Not Limiting Not LimitingTurbine Trip w/o Bypass Not Limiting Not LimitingInadvertent HPCI /L8 Turbine Trip 1.74 1.54Loss of Feedwater Heating 1.34Fuel Loading Error (misoriented) 1.37Fuel Loading Error (mislocated) Determined to be non-limitingSLO Pump Seizure 1.45Turbine Trip with Bypass 1.62Control Rod Withdrawal Error (RBM setpoint at 114%) 1.40Load Rejection with Bypass'7 Determined to be non-limitingLOCA Analysis Limit MCPR 1.35017 This event corresponds to "Single Turbine Control Valve Slow Closure (GESIL 502)". Since Cycle 22 results forthis event were far from limiting and no significant changes have occurred that would significantly increase thisevent's results for this cycle, this event was determined to be non-limiting.Page 39 Monticello OOONO154-SRLRReload 26 Revision 5Additional Section 12 InformationThe Dome Pressure Safety Limit, provided via the OPL-3, of 1332.0 psig is satisfied.Additional Section 16 InformationThese analyses indicate that plant operation up to 376 MWt with the RHR intertie line open isacceptable from an ECCS performance standpoint, provided a MAPLHGR multiplier of 0.75 isimplemented or that the peak bundle power does not exceed 3.9 MWt.In addition to the power and flow dependent multipliers, Monticello also requires an ECCSMAPLHGR multiplier of 0.9908 for operation at or below 99% core flow.No single-loop operation multiplier on PLHGR is required.Maximum Subcritical Banked Withdrawal Position (MSBWP)The Maximum Subcritical Banked Withdrawal Position analysis confirmed that the reference coreloading pattern satisfied cold shutdown margin requirements including bank position 04.Page 40 Monticello 000N0154-SRLRReload 26 Revision 5Appendix HTRACG04 AOO Supplementary InformationReference H-1 provides the results of the evaluations supporting the application of TRACG04 for AOOanalyses for Monticello. Section 11 of this report presents the MCPR limits based on the TRACG04methodology of Reference H-2.The safety evaluation report for licensing topical report NEDE-32906P Supplement 3 (Reference H-2)concluded that the application of TRACG04 methods to AOO and overpressure transient analyses wereacceptable subject to certain limitations and conditions. Several of these conditions request thatadditional, application-specific information be provided. The information provided below responds tothese requests for the identified items.Limitation/Condition 23 (Transient LHGR Limitation 3)The Transient LHGR Limitation 3 specified in Reference H-2 requires that in order to account for theimpact of void history bias, plant-specific EPU and MELLLA+ applications using either TRACG04 orODYN will demonstrate an equivalent to 10 percent margin to the fuel centerline melt and the 1 percentcladding circumferential plastic strain acceptance criteria due to pellet-cladding mechanical interactionfor all of the limiting AOO transient events, including equipment out-of-service. Limiting transients inthis case, refers to transients where the void reactivity coefficient plays a significant role (such aspressurization events).The analyses for Monticello Cycle 27 met the conditions of the Void Reactivity Coefficient CorrectionModel Condition (Limitation 21 of Reference H-2) and the Void Reactivity Coefficient Correction ModelBasis Condition (Limitation 22 of Reference H-2); and therefore per Limitation 23 of Reference H-2, thepressurization transient events are not required to demonstrate 10 percent margin to the fuel centerlinemelt and the 1 percent cladding circumferential plastic strain acceptance criteria.References for Appendix HH- 1. Monticello TRA CG Implementation for Reload Licensing Transient Analysis, 0000-0082-0062-R1,Revision 1, May 2010.H-2. Migration to TRACGO4/PANACll firom TRACGO2/PANACIO for TRACG AO0 and ATWSOverpressure Transients, NEDE-32906P, Supplement 3-A, Revision 1, April 2010.Page 41 Monticello 00ON0154-SRLRReload 26 Revision 5Appendix INEDC-33173P-A Supplementary InformationThe safety evaluation for licensing topical report NEDC-33173P-A (Reference I-I) concluded that theapplication of GEH/GNF methods to expanded operating domains was acceptable subject to certainlimitations and conditions. Several of these conditions request that additional, application-specificinformation be provided. The information provided below responds to these requests for the identifieditems.It is confirmed that the max allowable peak bundle power and average power density are not changedfrom the EPU license as documented in Reference 1-5.Limitation/Condition 5 (SLMCPR 2)For operation at MELLLA+, a 0.03 value was added to the cycle specific SLMCPR value which boundsthe 0.02 value as specified in the limitation. The SLMCPR values reported in Section 11 reflect thisadder.Limitation/Condition 6 (R-factor)The plant specific R-factor calculation at a bundle level was performed consistent with lattice axial voidconditions expected for the hot channel operating state applicable to this cycle of operation. ForMonticello Cycle 27 at the EPU/MELLLA+ licensed power level, a 60% void profile was used for thecalculation of bundle R-factors.Limitation/Condition 8 (ECCS-LOCA 2)This limitation is satisfied by reporting the Appendix K PCTs for the evaluated power and flow points inthe upper boundary of the expanded operating domains in Section 16.1 of this SRLR.Limitation/Condition 10 (Transient LHGR 2)The Transient LHGR 2 limitation specified in Reference 1-1 requires each EPU and MELLLA+ fuelreload to document the calculation results of the analyses demonstrating compliance to transient T-Macceptance criteria. Table 1-1 sunmmarizes the percent margin to the Thermal Overpower and MechanicalOverpower limits.Table I-1 Margin to the Thermal Overpower and Mechanical Overpower LimitsPage 42 Monticello 00ON0154-SRLRReload 26 Revision 5Criteria GE14CMechanical Overpower 7.91%Limitation/Condition 11 (Transient LHGR 3)The Transient LHGR 3 limitation specified in Reference I-1 requires that in order to account for theimpact of the void history bias, plant-specific EPU and MELLLA+ applications using either TRACG04or ODYN will demonstrate an equivalent to 10 percent margin to the fuel centerline melt and the 1percent cladding circumferential plastic strain acceptance criteria due to pellet-cladding mechanicalinteraction for all of the limiting AOO transient events, including equipment out-of-service. Limitingtransients in this case, refers to transients where the void reactivity coefficient plays a significant role(such as pressurization events)..However, as stated in Appendix H the void history bias was incorporated into the transient model withinthe TRACG04 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.Limitation/Condition 14 (Part 21 Evaluation of GESTR-M Fuel Temperature Calculation)GE 14 LHGR limits applied to Monticello Cycle 27 EPU/MELLLA+ incorporate a 350 psi penalty on fuelrod critical pressure in the fuel rod internal pressure design ratio. These limits comply with the NRC'sconclusions regarding this subject (Reference 1-2).Limitation/Condition 15 (Void Reactivity 1)This limitation/condition is the same as Limitation/Condition 22 of NEDE-32906P, which is described inAppendix H. Because Limitation/Condition 22 of NEDE-32906P is met, Limitation/Condition 15 fromNEDC-33173P is also met.Limitation/Condition 16 (Void Reactivity 2)This limitation/condition applies until the new TRACG/PANAC methodology is approved by theNRC. Monticello Cycle 27 EPU/MELLLA+ was analyzed with TRACG04/PANAC 11, so thislimitation/condition no longer applies.Limitation/Condition 17 (Steady State 5 Percent Bypass Voiding)The bypass voiding condition was evaluated for the licensed core loading and confirmed that the bypassvoid fraction remained below 5 percent at all LPRM levels when operating at steady-state conditionswithin the licensed upper boundary. For a power/flow condition that conservatively bounded the licensedpower/flow upper boundary, the bypass void fraction at the D level LPRM location was calculated to be0.0%.Limitation/Condition 19 (Void-Quality Correlation 1)Page 43 Monticello 00ON0154-SRLRReload 26 Revision 5The OLMCPR limitation requiring an additional 0.01 adder on tile OLMCPR does not apply to EPU orMELLLA+ licensing calculations when TRACG04 methods are used (Reference 1-3). Therefore, theOLMCPR adder is not applied to Monticello Cycle 27.Limitation/Condition 20 (Void-Quality Correlation 2)This limitation/condition applies until the new TRACG/PANAC methodology is approved by theNRC. Monticello Cycle 27 EPU/MELLLA+ was analyzed with TRACG04/PANAC 11, so thislimitation/condition no longer applies.NEDC-33006P-A Supplementary InformationThe safety evaluation for licensing topical report NEDC-33006P-A (Reference 1-4) approved theoperation of GE BWRs in the MELLLA+ expanded operating domain, subject to certainlimitations and conditions. One of these conditions requested that additional, application-specificinformation be provided as part of the SRLR. The infonnation provided below responds to thisrequest.Limitation/Condition 6 (SLMCPR Statepoints and CF Uncertainty)As requested in Limitation/Condition 6, the SLMCPR calculated results at specified off-ratedpower/flow conditions are reported in Table 1-2 below.Table 1-2 Two-Loop SLMCPR Results for MELLLA+ ConditionsPower (% Rated) Flow (% Rated) SLMCPR100 100 1.08100 80 1.1082.5 57.4 1.12100 105 1.07Limitation/Condition 10.B (ECCS-LOCA Off-Rated Multiplier)In addition to the power and flow dependent multipliers, Monticello also requires an ECCS MAPLHGRmultiplier of 0.9908 for operation at or below 99% core flow. This multiplier ensures that the off-ratedlimits assumed in the EPU ECCS-LOCA analyses bound the cycle-specific off-rated limits calculated forMELLLA+ operation.Limitation/Condition 18.D (ATWS TRACG Analysis)For operation in the MELLLA+ domain, SLO will not be allowed as expressed by EOOS options inSection 8, and per section 15 and Appendix J.References for Appendix IPage 44 Monticello 000N0154-SRLRReload 26 Revision 51-1. ApplicabilitY of GE Methods to Expanded Operating Domains, NEDC-33173P-A, Revision 4,November 2012.1-2. Applicabilio, of GE Methods to Expanded Operating Domains, NEDC-33173P-A, Revision 1,September 2010.1-3. Migration to TRACGO4/PANACII firom TRACGO2/PANACIO for TRACG AO0 and ATtWSOverpressure Transients, NEDE-32906P, Supplement 3-A, Revision 1, April 2010.1-4. General Electric Boiling Water Reactor Maritnum Extended Load Line Limit Analysis Plus, NEDC-33006P-A, Revision 3, June 2009.1-5. Supplemental Reload Licensing Report for Monticello Reload 26 Cycle 27 Extended Power Uprate(EPU), 0000-0146-5423-SRLR-R3, October 2013.Page 45 Monticello 00ON0154-SRLRReload 26 Revision 5Appendix JMELLLA+ Supplementary InformationThe pressurization transients are generally limiting at high core flow conditions. However, thetransients were performed at both the minimum MELLLA+ flow (80%) and the maximum ICFflow (105%). This ensures that the pressurization transient results bound MELLLA, MELLLA+and ICF operating conditions. Additionally, the loss of feedwater heating (LFWH) transient,which is more limiting at low core flow, was performed at the minimum MELLLA+ flow.Therefore, the limiting subcooling transient bounds MELLLA, MELLLA+ and ICF operatingconditions. Single loop operation (SLO) will not be allowed in conjunction with operation in theMELLLA+ domain.NEDC-33173P-A Revision 4 Limitations/ConditionsThe safety evaluation in licensing topical report NEDC-33173P-A Revision 4 (Applicability ofGE Methods to Expanded Operating Domains) concluded that the application of GEH/GNFmethods to expanded operating domains was acceptable subject to certain limitations andconditions. Several of these conditions request that additional, application-specific informationbe provided. The limitations/conditions for MELLLA+ have already been addressed inAppendix I.NEDC-32906P Supplement 3-A Limitations/ConditionsThe safety evaluation in licensing topical report NEDC-32906P Supplement 3-A (Migration toTRACGO4/PANACll from TRACGO2/PANACIO for TRACG AOO and ATWS OverpressureTransients) concluded that the application of TRACG04 methods to AOO and overpressuretransient analyses were acceptable subject to certain limitations and conditions. Thelimitations/conditions for MELLLA+ have already been addressed in Appendix I.NEDC-33006P-A Revision 3 Limitations/ConditionsThe safety evaluation in licensing topical report NEDC-33006P-A Revision 3 (General ElectricBoiling Water Reactor Maximum Extended Load Line Limit Analysis Plus) concluded that plant-specific MELLLA+ applications were acceptable subject to certain limitations/conditions.Several of these conditions request that additional, application-specific information be provided.These limitations/conditions are addressed in Appendix I.Page 46 MonticelloReload 2600ON0154-SRLRRevision 5Appendix KList of AcronymsAcronym DescriptionACPR Delta Critical Power RatioAk Delta k-effective2RPT (2PT) Two Recirculation Pump TripABSP Automated Backup Stability ProtectionADS Automatic Depressurization SystemADSOOS Automatic Depressurization System Out of ServiceAOO Anticipated Operational OccurrenceAPRM Average Power Range MonitorARTS APRM, Rod Block and Techmical Specification Improvement ProgramBOC Beginning of CycleBSP Backup Stability ProtectionBWROG Boiling Water Reactor Owners GroupCDA Confirmation Density AlgorithmCOLR Core Operating Limits ReportCPR Critical Power RatioDIRPT Delta MCPR over Initial MCPR for a two-Recirculation Pump TripD1VOM Delta CPR over Initial MCPR vs. Oscillation MagnitudeDR Decay RatioDSS-CD Detect and Suppress Solution -Confirmation DensityDS/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 1 00%Power / 1 00%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 LinePage 47 MonticelloOOONO I 54-SRLRQ. ; , 11MontclloU O--NO 1 54-SLRlAcronym DescriptionHPCI High Pressure Coolant InjectionHTSP High Trip Set PointICA Interim Corrective ActionICF Increased Core FlowIMCPR Initial MCPRITSP Intermediate Trip Set Point1VM 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 AccidentLPRM Local Power Range MonitorLRHBP Load Rejection with Half BypassLRNBP Load Rejection without BypassLTR Licensing Topical ReportLTSP Low Trip Set PointMAPFACf 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 BurnPage 48 MonticelloReload 2600ON0154-SRLRRevision 5Acronym DescriptionNTR Normal Trip ReferenceOLMCPR Operating Limit MCPROOS Out of ServiceOPRM 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 FlowRDF Recirculation Drive FlowRFWT Reduced Feedwater TemperatureRPS Reactor Protection SystemRPT Recirculation Pump TripRPTOOS Recirculation Pump Trip Out of ServiceRTP Rated Thermal PowerRV Relief ValveRVM Reload Validation MatrixRWE Rod Withdrawal ErrorSAD Amplitude Discriminator SetpointSC 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 ValveSTP Simulated Thermal PowerSTU Short Tons (or Standard Tons) of UraniumTBV Turbine Bypass ValveTBVOOS Turbine Bypass Valves Out of ServiceTCV Turbine Control ValveTCVOOS Turbine Control Valve Out of ServicePage 49 MonticelloReload 91;00ON0154-SRLRRevi'~inn 5Acronym DescriptionTCVSC Turbine Control Valve Slow ClosureTFW Temperature of FeedwaterTLO Two Loop OperationTRF Trip Reference FunctionTSIP Technical Specifications Improvement ProgramTSV Turbine Stop ValveTSVOOS Turbine Stop Valve Out of ServiceTT Turbine TripTTHBP Turbine Trip with Half BypassTTNBP Turbine Trip without BypassUB Under BumPage 50