ML15156A386

Limerick, Unit 2 - Issuance of the Core Operating Limits Report (Colr) for Reload 13, Cycle 14

ML15156A386
Person / Time
Site:	Limerick
Issue date:	05/15/2015
From:	Dougherty T J Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LG-15-067
Download: ML15156A386 (19)

Text

AmExelon Generation,T.S. 6.9.1.12LG-1 5-067May 15, 2015U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555j2~*~4- ~Limerick Generating Station, Unit 2Renewed Facility Operating License No NPF-85NRC Docket Nos. 50-353

Subject:

Issuance of the Core Operating Limits Report (COLR) for Reload 13, Cycle 14Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station(LGS) Unit 2 Reload 13 Cycle 14 which incorporates the revised cycle specific parametersresulting from the new configuration implemented for LGS, Unit 2.The COLR is being submitted to the NRC in accordance LGS, Unit 2 Technical Specification6.9.1.12.If you have any questions or require additional information, please contact Giuseppe Rubinaccioat 610-718-3560.Sincerely,-/-.3--- //Thomas J. Dougherty -Site Vice President-Limerick Generating StationExelon Generation Company, LLC

Attachment:

Core Operating Limits Report for Limerick Generating Station Reload 13, Cycle 14cc: D. Dorman, Administrator, Region I, USNRCS. Rutenkroger, USNRC Sr. Resident Inspector, LGSR. Ennis, USNRC Project Manager for LGSR. R. Janati, PADEP-BRP(w/attachments)(w/attachments)(w/attachments)(w/attachments)ýc'o ýocy--

Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportCOLR Limerick 2 Rev. 9CORE OPERATING LIMITS REPORTFORLIMERICK GENERATING STATION UNIT 2RELOAD 13, CYCLE 14(This is a complete re-write; no annotations are used.)Prepared By- ." ( g-s .olmýesv.parv.Reviewed By: ___F. TrikurIndependent Review .Reviewed By:Arthur Stefancyzk per TelecorJ- ;! 'Reviewed By:Approved By:A. Stefanczykiacto.gineenng-/T. -ementE g'meering Safety AnalysisJ. TusarManager -BWR Design (GNF)Date: 5,Date: ~Date: 511/2015Dat. : /Date: Z/Z/'/ -Date: L).()415_Station QualifiedReviewed By: )L. KorbeilStation Qualified Reviewer Exelon Nuclear -Nuclear FuelsCore Operating Limits Report COLR Limerick 2 Rev. 9Table of ContentsPage1.0 Terms and Definitions 42.0 General Information 63.0 MAPLHGR Limits 74.0 MCPR Limits 85.0 LHGR Limits I I6.0 Control Rod Block Setpoints 147.0 Turbine Bypass Valve Parameters 158.0 Stability Protection Setpoints 169.0 Modes of Operation 1710.0 Methodology 1811.0 References 18Page 2 of 18 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportCOLR Limerick 2 Rev. 9List of TablesTABLE 3-ITABLE 3-2TABLE 4-ITABLE 4-2TABLE 4-3TABLE 5-ITABLE 5-2TABLE 5-3TABLE 5-4TABLE 5-5TABLE 6-ITABLE 6-2TABLE 7-1TABLE 7-2.TABLE 8-iTABLE 8-2TABLE 9-IPageMAPLHGR versus Average Planar Exposure -All Fuel Types 7MAPLHGR Single Loop Operation (SLO) Multiplier- All Fuel Types 7Operating Limit Minimum Critical Power Ratio (OLMCPR) -All Fuel Types 9Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp -All Fuel Types 10Flow Dependent MCPR Limits MCPR(F) -All Fuel Types 10Linear Heat Generation Rate Limits -U02 Rods 11Linear Heat Generation Rate Limits -Gad Rods I ILHGR Single Loop Operation (SLO) Multiplier -All Fuel Types 12Power Dependent LHGR Multiplier LHGRFAC(P) -All Fuel Types 12Flow Dependent LHGR Multiplier LHGRFAC(F)-All Fuel Types 13Rod Block Monitor Setpoints 14Reactor Coolant System Recirculation Flow Upscale Trip 14Turbine Bypass System Response Time 15Minimum Required Bypass Valves To Maintain System Operability 15OPRM PBDA Trip Setpoints 16SLO OPRM PBDA Trip Setpoints 16Modes of Operation 17Page 3 of 18 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportCOLR Limerick 2 Rev. 91.0ARTSBASEDLODTSPEOOSEORFFWTIFWHOHTSPICFITSPKpLHGRLHGRJLHGRJLTSPMAPF/MAPFtMAPLIMCPRMCPRMCPRITerms and DefinitionsAPRM, RBM, and Technical Specification Improvement ProgramA case analyzed with Turbine Bypass System in service and Recirculation PumpTrip in service and Feedwater Temperature Reduction allowed (FFWTR includesFWHOOS or final feedwater temperature reduction) and PLUOOS allowed at anypoint during the cycle in Dual Loop mode.Dual Loop OperationRod Block Monitor Downscale Trip SetpointEquipment Out of ServiceEnd of Rated, the cycle exposure at which reactor power is equal to rated thermalpower with recirculation system flow equal to 100%, all control rods fullywithdrawn, all feedwater heating in service and equilibrium Xenon.t Final Feedwater Temperature ReductionOS Feedwater Heaters Out of ServiceRod Block Monitor High Trip SetpointIncreased Core FlowRod Block Monitor Intermediate Trip SetpointOff-rated power dependent OLMCPR multiplierLinear Heat Generation RateFAC(F) ARTS LHGR thermal limit flow dependent multipliersFAC(P) ARTS LHGR thermal limit power dependent multipliersRod Block Monitor Low Trip SetpointAC(F) Off-rated flow dependent MAPLHGR multiplierAC(P) Off-rated power dependent MAPLHGR multiplierHGR Maximum Average Planar Linear Heat Generation RateMinimum Critical Power Ratio(F) Off-rated flow dependent OLMCPR multiplier(P) Off-rated power dependent OLMCPR multiplierPage 4 of 18 Exelon Nuclear -Nuclear FuelsCore Operating Limits Report COLR Limerick 2 Rev. 9MELLLA Maximum Extended Load Line Limit AnalysisMSIVOOS Main Steam Isolation Valve Out of ServiceOLMCPR Operating Limit Minimum Critical Power RatioOPRM Oscillation Power Range MonitorOOS Out of ServicePBDA Period Based Detection AlgorithmPLUOOS Power Load Unbalance Out of ServicePROOS Pressure Regulator Out of ServiceRBM Rod Block MonitorRPTOOS Recirculation Pump Trip Out of ServiceRWE Rod Withdrawal ErrorSLO Single Loop OperationTBSOOS Turbine Bypass System Out of ServiceTCV Turbine Control ValveTIPOOS Traversing In core Probe Out of ServiceTSV Turbine Stop ValvePage 5 of 1.8 Exelon Nuclear- Nuclear FuelsCore Operating Limits Report COLR Limerick 2 Rev. 92.0 General InformationThis report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 2Cycle 14:" Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)" Minimum Critical Power Ratio (MCPR)* Single Loop Operation (SLO) OLMCPR adjustment* Off-rated OLMCPR adjustments (MCPR(P) or MCPR(F))" Off-rated OLMCPR multipliers (Kp)* Off-rated LHGR multipliers (LHGRFAC(P) or LHGRFAC(F))* Rod Block Monitor (RBM) setpoints" MAPLHGR single loop operation multiplier" LHGR single loop operation multiplier* Linear Heat Generation Rate (LHGR)" Turbine Bypass Valve parameters" Reactor Coolant System Recirculation Flow Upscale Trips* Oscillation Power Range Monitor Period Based Detection Algorithm (OPRM PBDA) Trip SetpointsThis report is prepared in accordance with Technical Specification 6.9.1.9 of Reference 1. Preparation of thisreport was performed in accordance with Exelon Nuclear, Nuclear Fuels T&RM NF-AB-120-3600.The data presented in this report is valid for all licensed operating domains on the operating map, including:" Maximum Extended Load Line Limit down to 82.9% of rated core flow during full power operation* Increased Core Flow (ICF) up to I 10% of rated core flow* Final Feedwater Temperature Reduction (FFWTR) up to 105°F during cycle extension operation" Feedwater Heater Out of Service (FWHOOS) up to 60*F feedwater temperature reduction at any timeduring the cycle prior to cycle extension.Further information on the cycle specific analyses for Limerick 2 Cycle 14 and the associated operatingdomains discussed above is available in Reference 2.Page 6 of 18 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportCOLR Limerick 2 Rev. 93.0 MAPLHGR Limits3.1 Technical SpecificationSection 3.2.13.2 DescriptionThe limiting MAPLHGR value for the most limiting lattice (excluding natural uranium) of each fueltype as a function of average planar exposure is given in Table 3-1. For single loop operation, amultiplier is used, which is shown in Table 3-2. The power and flow dependent multipliers forMAPLHGR have been removed and replaced with LHGRFAC(P) and LHGRFAC(F); therefore,MAPFAC(P) and MAPFAC(F) are equal to 1.0 for all power and flow conditions (Reference 2).LHGRFAC(P) and LHGRFAC(F) are addressed in Section 5.0.TABLE 3-1MAPLHGR versus Average Planar Exposure -All Fuel Types(Reference 2)Average Planar Exposure MAPLHGR Limit(GWDIST) (kW/ft)0.0 13.7817.52 13.7860.78 7.5063.50 6.69TABLE 3-2MAPLHGR Single Loop Operation (SLO) Multiplier -All Fuel Types(Reference 2)SLO Multiplier 0.80Page 7 of 18 Exelon Nuclear -Nuclear FuelsCore Operating Limits Report COLR Limerick 2 Rev. 94.0 MCPR Limits4.1 Technical SpecificationSection 3.2.34.2 DescriptionTable 4-1 is derived from Reference 2 and is valid for all fuel types and all operating domains. Table4-1 includes treatment of these MCPR limits for all conditions listed in Section 9.0, Modes ofOperation.ARTS provides for power and flow dependent thermal limit adjustments and multipliers, whichallow for a more reliable administration of the MCPR thermal limit. The flow dependent adjustmentMCPR(F) is sufficiently generic to apply to all fuel types and operating domains. The powerdependent adjustment MCPR(P) is independent of recirculation pump trip operability. MCPR(P)and MCPR(F) are independent of Scram Time Option. In addition, there are ten sets of powerdependent MCPR multipliers (Kp) for use with BASE, TBSOOS, RPTOOS, PROOS, DLO andSLO conditions, and PROOS+TBSOOS, PROOS+RPTOOS, DLO only. The PLUOOS conditionis included in the BASE MCPR(P) and MCPR(F) limits and Kp multipliers and is bounded by theTBSOOS limits and multipliers; therefore, no additional adjustments are required for PLUOOS inthose operating conditions. The PLUOOS condition has not been analyzed concurrent with theRPTOOS operating condition. Operation in the PLUOOS condition concurrent with the RPTOOScondition requires core thermal power < 55% of rated (Reference 3). Section 7.0 contains theconditions for Turbine Bypass Valve Operability. MCPR(P) and MCPR(F) adjustments areprovided in Tables 4-2 and 4-3. The OLMCPR is determined for a given power and flow conditionby evaluating the power dependent MCPR and the flow dependent MCPR and selecting the greaterof the two.Page 8 of 18 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportCOLR Limerick 2 Rev. 9TABLE 4-1Operating Limit Minimum Critical Power Ratio (OLMCPR) -All Fuel Types(References 2 and 8)SCRAM Cycle Ex posureTime < EOR -2542 _ EOR -2542EOOS Combination MWd/ST MWd/STB 1.36(2) 1.36A 1.41 1.44BASE SLO(3 B 1.58 1.58A 1.58 1.58B 1.37 1.39A 1.46 1.48TBSOOS SLO(3 B 1.58 1.58A 1.58 1.58B 1.37 1.39A 1.54 1.56RPTOOS SLO3) B 1.58 1.58A 1.58 1.59B 1.36,2) 1.36A 1.41 1.47PROOS SLO(3) B 1.58 1.58A 1.58 1.58PROOS+TBSOOS B 1.37 1.39PROOS+RPTOOS B 1.37 1.391 When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation. For PROOS+TBSOOSand PROOS+RPTOOS, only Option B is allowed.2 Value is adjusted to obtain an OPRM amplitude setpoint of 1.12.3 For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed two loop value.However, a minimum value of 1.58 is required to obtain an OLMCPR limit set by the Single LoopOperation Recirculation Pump Seizure Event.Page 9 of 18 Exelon Nuclear- Nuclear FuelsCore Operating Limits ReportCOLR Limerick 2 Rev. 9TABLE 4-2Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp -All Fuel Types(References 2 and 8)Core Core Thermal Power (% of rated)EOOS Flow 0 25 < 30 >30 65 85 100Combination (% ofCombinatin rated% MCPR(P) Operating Limit MCPR Multiplier, Kp< 60 2.50 2.50 2.40Base >60 2.5 2.5 2.55 1.340 1.131 1.067 1.000> 60 2.75 2.75 2.55Base SLO >560 2.53 2.53 2.43 1.340 1.131 1.067 1.000> 60 2.78 2.78 2.58L< 60 3.25 3.25 2.75TBSOOS >60 3.75 3.75 3.25 1.340 1.131 1.067 1.000> 60 3.75 3.75 3.25TBSOOS SLO <560 3.28 3.28 2.78 1.340 1.131 1.067 1.000> 60 3.78 3.78 3.28RPTOOS -60 2.50 2.50 2.40 1.340 1.131 1.067 1.000> 60 2.75 2.75 2.55R<OS L 60 2.53 2.53 2.43RPTOOS SLO 5 60 2.78 2.78 2.58 1.340 1.131 1.067 1.000> 60 2.78 2.78 2.58PROOS <560 2.50 2.50 2.40 1.367 1.236 1.160 1.000> 60 2.75 2.75 2.55PROOS SLO >560 2.53 2.53 2.43 1.367 1.236 1.160 1.000> 60 2.78 2.78 2.58PROOS+TBSOOS >560 3.25 3.25 2.75 1 .367 1.236 1.160 1.000> 60 3.75 3.75 3.25PROOS+RPTOOS > 60 2.50 2.50 2.40 1.367 1.236 1.160 1.000__________ > >60 2.75 2.75 2.55 _________TABLE 4-3Flow Dependent MCPR Limits MCPR(F) -All Fuel Types(Reference 2)Flow MCPR(F)(% rated) Limit0.0 1.7030.0 1.5379.0 1.25110.0 1.25Page 10 of 18 Exelon Nuclear-Nuclear FuelsCore Operating Limits Report COLR Limerick 2 Rev. 95.0 LHGR Limits5.1 Technical SpecificationSection 3.2.45.2 DescriptionThe LHGR limit is the product of the exposure dependent LHGR limit (from Table 5-1 for U02 fuelrods and Table 5-2 for Gadolinia fuel rods) and the minimum of: the power dependent LHGR Factor,LHGRFAC(P), and the flow dependent LHGR Factor, LHGRFAC(F). For single loop operation, amultiplier is used, which is shown in Table 5-3 and applied in Table 5-5. No further Single LoopOperating multipliers need to be applied to the values in Tables 5-4 and 5-5.ARTS provides for power and flow dependent thermal limit multipliers, which allow for a morereliable administration of the LHGR thermal limits. There are two sets of flow dependent LHGRmultipliers for dual-loop and single-loop operation. In addition, there are ten sets of powerdependent LHGR multipliers for use with the BASE, TBSOOS, RPTOOS, PROOS, DLO and SLOconditions, and PROOS+TBSOOS and PROOS+RPTOOS, DLO only. The PLUOOS condition isincluded in the BASE LHGRFAC(P) and LHGRFAC(F) multipliers and is bounded by the TBSOOSmultipliers; therefore, no additional adjustments are required for PLUOOS in those operatingconditions. The PLUOOS condition has not been analyzed concurrent with the RPTOOS operatingcondition. Operation in the PLUOOS condition concurrent with the RPTOOS condition requires corethermal power < 55% of rated (Reference 3). Section 7.0 contains the conditions for Turbine BypassValve Operability. The ARTS LHGR multipliers are shown in Tables 5-4 and 5-5. Linearinterpolation should be used for points not listed in Reference 7.Thermal limit monitoring must be performed with the more limiting LHGR limit resulting from thepower and flow biased calculation. The LHGRFAC(P) curves are independent of recirculation pumptrip operability.TABLE 5-1Linear Heat Generation Rate Limits -U02 Rods(References 5 and 7)I Fuel Type I LHGR IGNF2 See Table B-I of Reference 7TABLE 5-2Linear Heat Generation Rate Limits -Gad Rods(References 5 and 7)Fuel Type LHGRGNF2 See Table B-2 of Reference 7Page 11 of 18 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportCOLR Limerick 2 Rev. 9TABLE 5-3LHGR Single Loop Operation (SLO) Multiplier -All Fuel Types(Reference 2)SLO Multiplier' 0.80TABLE 5-4Power Dependent LHGR Multiplier LHGRFAC(P) -All Fuel Types(References 2 and 8)Core Core Thermal Power (% of rated)Flow _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _EOOS Combination (%of 0 25 <130 1 301 65 85 100rated) LHGRFAC(P) Multiplier =BASE 60 0.485 0.485 0.490 .750 0.817 0.922 1.000_ _ _ _ > 60 0.434 0.434 0.473BASE SLO > 60 0.485 0.485 0.490 0.750 0.817 0.922 1.000> 60 0.434 0.434 0.473TBSOOS 60 043 043 .90.0750 0.817 0.922 i.000<5 6 0.463 0.463 0.490____________ > 60 0.352 0.352 0386 0.750_ 0.817_ 1 0.22 .00TBSOOS SLO 60 0.463 0.463 0.490 0.750 0.817 0.922 1.000> 60 0.352 0.352 0.386 60 0.485 0.485 0.490RPTOOS 0.434 0.434 0.473 0.750 0.817 0.922 1.000S 60 0.434 0.434 0.4973* 60 0.485 0.485 0.497RPTOOS SLO 60 0.45 0.45 0.40 0.750 0.817 0.922 1.000> 60 0.434 0.434 0.473PROOS :L 60 0.485 0.485 0.490 0.750 0.817 0.922 1.000> 60 0.434 0.434 0.473 60 0.434 0.434 0.473PROOS+TBSOOS < 60 0.463 0.463 0.490 0.750 0.817 0.922 1.000> 60 0.352 0.352 0.386 0.750 0.817 0.2 _.0PROOS+RPTOOS s60 0.485 0.485 0.490 0.750 0.817 0.922 1.000I O O > 60 0.434 0.434 0.473 = -1 Applied through Table 5-5Page 12 of 18 Exelon Nuclear- Nuclear FuelsCore Operating Limits ReportCOLR Limerick 2 Rev. 9TABLE 5-5Flow Dependent LHGR Multiplier LHGRFAC(F) -All Fuel Types(Reference 2)Core Flow (% of rated)EOOS Combination 0 30 44.1 70 80 110LHGRFAC(F) MultiplierDual Loop 0.506 0.706 0.973 1.000 1.000Single Loop 0.506 0.706 0.800 0.800S. ._ , .; ~ ,:.080Page 13 of 18 Exelon Nuclear- Nuclear FuelsCore Operating Limits ReportCOLR Limerick 2 Rev. 9.6.0 Control Rod Block Setpoints6.1 Technical SpecificationSections 3.1.4.3 and 3.3.66.2 DescriptionThe ARTS Rod Block Monitor provides for power-dependent RBM trips. Technical Specification3.3.6 states control rod block instrumentation channels shall be OPERABLE with their trip setpointsconsistent with the values shown in the Trip Setpoint column of Technical Specification Table 3.3.6-2. The trip setpoints/allowable values and applicable RBM signal filter time constant data are shownin Table 6-1. The Reactor Coolant System Recirculation Flow Upscale Trip is shown in Table 6-2.These setpoints are set high enough to allow full utilization of the enhanced ICF domain up to 110%of rated core flow.TABLE 6-1Rod Block Monitor Setpointsi(References 2 and 4)Power Level Analytical Allowable Nominal TripLimit Value SetpointLTSP 123.0% 121.5% 121.5%ITSP 118.0% 116.5% 116.5%HTSP 113.2% 111.7% 111.0%DTSP No Limitation 2.0% 5.0%TABLE 6-2Reactor Coolant System Recirculation Flow Upscale Trip(Reference 4)Analytical Limit N/AAllowable Value 115.6%Nominal Trip Setpoint 113.4%'These setpoints (with Rod Block Monitor filter time constant between 0. 1 seconds and 0.55 seconds) arebased on a cycle-specific rated RWE MCPR limit of 1.32, which is less than the minimum cycleOLMCPR.Page 14 of 18 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportCOLR.Liierick.2 Rev. 97.0 Turbine Bypass Valve Parameters7.1 Technical SpecificationSection 3.7.8 and 4.7.8.c7.2 DescriptionThe operability requirements for the steam bypass system are found in Tables 7-1 and 7-2. If theserequirements cannot be met, the MCPR, MCPR(P) and LHGRFAC(P) limits for inoperable SteamBypass System, known as Turbine Bypass System Out Of Service (TBSOOS), must be used.Additional information on the operability of the turbine bypass system can be found in Reference 6.TABLE 7-1Turbine Bypass System Response Time(Reference 3)Maximum delay time before start of bypass valve opening 0.11 sfollowing initial turbine inlet valve movement'Maximum time after initial turbine inlet valve movement' forbypass valve position to reach 80% of full flow (includes the 0.31 secabove delay time) IIFirst movement of any TSV or any TCV or generation of the turbine bypass valve flow signal (whicheveroccurs first)TABLE 7-2Minimum Required Bypass Valves To Maintain System Operability(References I and 3)Reactor Power No. of Valves in ServiceP > 25% 7Page 15 of 18 Exelon Nuclear- Nuclear FuelsS. .Core Operating Iinits ReportCOLR Limerick 2 Rev. 98.0 Stability Protection Setpoints8.1 Technical SpecificationSection 2.2.18.2 DescriptionThe Limerick 2 Cycle 14 OPRM PBDA Trip Setpoints for the OPRM System are found in Table 8-1. These values are based on the cycle specific analysis documented in Reference 2. The setpointsprovided in Table 8-1 are bounding for all modes of operation shown in Table 9-1. The setpointsprovided in Table 8-2 are acceptable for use in Single Loop Operation. The standard two loopoperation OPRM Setpoints specified in Table 8-1 must be implemented prior to restarting the idlepump when exiting the SLO condition.TABLE 8-1OPRM PBDA Trip Setpoints(Reference 2)TABLE 8-2SLO OPRM PBDA Trip Setpoints(Reference 2)Page 16 of 18 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportCOLR Limerick 2 Rev. 99.0 Modes of Operation9.1 DescriptionThe allowable modes of operation are found in Table 9-1. Operation with I MSIVOOS, or ITCVITSV OOS is supported in all modes of operation, provided the restrictions identified in theapplicable station procedures are met. All EOOS options also support the allowance of I TIPOOS.TABLE 9-1Modes of Operation(References 2 and 8)EOOS Options Operating Region'BASE, Option A or B Yes2BASE SLO, Option A or B Yes2TBSOOS, Option A or B Yes2TBSOOS SLO, Option A or B Yes2RPTOOS, Option A or B Yes3RPTOOS SLO, Option A or B Yes3TBSOOS and RPTOOS, Option A or B NoTBSOOS and RPTOOS SLO, Option A or B NoPROOS, Option A or B Yes'PROOS SLO, Option A or B YesePROOS+TBSOOS, Option A NoPROOS+TBSOOS, Option B Yes2PROOS+TBSOOS SLO, Option A or B NoPROOS+RPTOOS, Option A NoPROOS+RPTOOS, Option B Yes3PROOS+RPTOOS SLO, Option A or B No'Operating Region refers to operation on the Power to Flow map with or without FFWTR/FWHOOS.2 The PLUOOS condition is supported in this mode of operation with no power reduction required.3 The PLUOOS condition requires core thermal power level < 55% of rated (Reference 3).Page 17 of 18 Exelon Nuclear -Nuclear FuelsCore Operating Limits Report COLR Limerick 2 Rev. 910.0 MethodologyThe analytical methods used to determine the core operating limits shall be those previously reviewed andapproved by the NRC, specifically those described in the following document:1. "General Electric Standard Application for Reactor Fuel", Global Nuclear Fuel Document, NEDE-2401 I-P-A-2 1, May 2015 and the U.S. Supplement NEDE-2401 I-P-A-21-US, May 2015.2. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for ReloadApplications", GENE Document, NEDO-32465-A, August 1996.11.0 ReferencesI. "Technical Specifications and Bases for Limerick Generating Station Unit 2", Docket No. 50-353,License No. NPF-85, Exelon Document.2. "Supplemental Reload Licensing Report for Limerick Unit 2 Reload 13 Cycle 14", Global Nuclear FuelDocument No. 000N9396-SRLR, Rev. 0, February 2015.3. "Final Resolved OPL-3 Parameters for Limerick Unit 2 Cycle 14", Exelon TODI ES1400022 Rev. 0,October 30,2014.4. "GE NUMAC PRNM Setpoint Study", Exelon Design Analysis LE-0107, Rev. 2, February 23, 2012.5. "Fuel Bundle Information Report for Limerick 2 Reload 13 Cycle 14", Global Nuclear Fuel DocumentNo. 000N9397-FBIR, Rev. 0, February 2015.6. "Tech Eval Stop Valve Load Limit Documentation", Exelon Document IR 917231 Assignment 7,November 11, 2009.7. "GNF2 Advantage Generic Compliance with NEDE-2401 1-PA (GESTAR IlI)", Global Nuclear FuelDocument No. NEDC-33270P, Rev. 5, May 2013.8. "Limerick Generating Station (LGS) Units I and 2 TRACG Cycle-Independent PROOS AnalysisReport", GE Hitachi Nuclear Energy Document No. 002N4397, Rev. 0, February 24, 2015.Page 18 of 18