ML14112A582

Limerick, Unit 1 - Core Operating Limits Report for Reload 15 Cycle 16 Fcp ECR Lg 13-00136, Rev. 1

ML14112A582
Person / Time
Site:	Limerick
Issue date:	03/25/2014
From:	Bradish D M, Jurgens T Exelon Generation Co, Exelon Nuclear
To:	Office of Nuclear Reactor Regulation
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ML14113A026	List: LG-14-055, Issuance of the Core Operating Limits Report for Cycle 16 Revision 11 ML14112A582
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LG-14-055
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{{#Wiki_filter:ENCLOSURE 3UNIT 2 COLR FOR CYCLE 13 REV. 8WITH APPENDIX APROPRIETARY CLASS I (PUBLIC) Ezeton Nudesr- Nuclear FuelsCore Operating Limit ReportNon-Propriftary Infonruden Submiettd in Acordance with O CFR 2.390Doe ID: COLR Umerkk I, Rev. IICORE OPERATING LIMITS REPORTFORLIMERICK GENERATING STATIONUNIT 1 RELOAD 15 CYCLE 16FCP ECR LG 13-00136 Rev. 1Prepared By:;2/T Ju>gD. BrmdishtT. JurgeniDate: 03/25/14Reviewed By:Reviewed By:Reviewed By:QRAttfi TI1*k4Pg P9R TLLFC614 /e Dvle: L02I5 LF. TtikurIndepednt ReviewerMOLThonmReactor Elineefng ReviewerL Date: 03/25/14T. BemntEngineering Sfety Analysis ReviewerApproved By:Date:L J.TusarManager -BWR DesignStation Qualified. Review By: tIj lDaoe: -aIZ6L&Page I of 54 ExcI4on Nuiclear -Nuaclear FuelsCore Operating Limits ReportNon-Proprictary Informatiton Submitted in Accordan~ce with~ 10 CFR 2.390Table of Contentts Doc II): COLR Limerick 1, Rev. I IPage1.0 Terms and Definitions 2.0 General Information 3.0 MAPLJIGR Limits4.0 MCPR Limits5.0 LHIGR Limits6.0 Control Rod Block Setpoints 7.0 Turbine Bypass Valve Parameters 8.0 Stability Protection Setpoints 9.0 Modes of Operation 10.0 Methodology 11.0 References Appendix A46781113141516171718Page 2 of 54 Ixel(o Nuclear -Nuclear Fuels Moe !1): C()LI, Limerick I, Rev. I ICore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 101 CFR 2.390List of TablesPageTable 3-1 MAPLI-IGR Versus Average Planar Exposure-GE14 7Table 3-2 MAPLHGR Versus Average Planar Exposurec-GNF2 7Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier-All Fuel Types 7Table 4-I Operating Limit Minimum Critical Power Ratio (OLMCPR) -GE14 9Table 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR).- GNF2 9Table 4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp -All Fuel Types 10Table 4-4 Flow Dependent MCPR Limits MCPR(F) -All Fuie Types 10Table 5-I Linear Heat Generation Rate Limits -U02 Rods 11Table 5-2 Linear Heat Generation Rate Limits- Gadolinia Rods 11Table 5-3 LHIGR Single Loop Operation (SLO) Multiplier-- All Fuel Types 12Table 5-4 Power Dependent LHGR Multiplier LHGRFAC(P) -- All Fuel Types 12Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) -All Fuel Types 12Table 6-1 Rod Block Monitor Setpoints 13Table 6-2 Reactor Coolant System Recirculation Flow Upscale Trip 13Table 7-1 Turbine Bypass System Response Time 14Table 7-2 Minimum Required Bypass Valves To Maintain System Operability 14Table 8-1 OPRM PBDA Trip Setpoints 15Table 8-2 SLO OPRM PBDA Trip Setpoints 15Table 9-I Modes of Operation 16Page 3 of 54 Exclon Nuclear -Nudear Fuels Doc ID: COLR Limerick I, Rev. I I('ore Operating Limits ReportNon-Proprietary Infmiormation Submitted in Accordance with 10 CFR 2.3901.0 Terms and Definitions ARTS APRM and RBM Technical Specification BASE A case analyzed with Turbine Bypass System in service, Recirculation Pump Trip inservice, Feedwater Temperature Reduction allowed (FFWTR includes feedwater heater OOS or final feedwater temperature reduction) and PLUOOS allowed at anypoint in the cycle operation in Dual Loop mode.DLO Dual Loop Operation DTSP Rod Block Monitor Downscale Trip SetpointFOOS Equipment Out of ServiceFEOR End 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.FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of ServiceHTSP Rod Block Monitor High Trp SetpointICF Increased Core FlowITSP Rod Block Monitor Intermediate Trip SetpointKp Off-rated power dependent OLMCPR multiplier LHGR Linear Heat Generation RateLHGRFAC(F) Off-rated LHGR thermal limit flow dependent multipliers LHGRFAC(P) Off-rated LHGR thermal limit power dependent multipliers LTSP Rod Block Monitor Low Trip SetpointMAPFAC(F) Off-rated flow dependent MAPLHGR multiplier MAPFAC(P) Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation RateMCPR Minimum Critical Power RatioMCPR(F) Off-rated MCPR flow dependent thermal limitMCPR(P) Off-rated MCPR power dependent thermal limitPage 4 of 54 Exeloin Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary I nformation Submitted in Accordance with I 0) CFR 2.391)M.ELLLA Maximum Extended Load Line Limit AnalysisMSIVOOS Main Steam Isolation Valve Out of ServiceOLMCPR Operating Limit Minimum Critical Power RatioOOS Out of ServiceOPRM Oscillation Power Range MonitorPBDA Period Based Detection Algorithm PLUOOS Power Load Unbalance Out of ServicePROOS Pressurc Regulator Out of ServiceRBM Rod Block MonitorRPTIS Recirculation Pump Trip in ServiceRPTOOS Recirculation Pump Trip Out of ServiceSLO Single Loop Operation TBVIS Turbine Bypass Valves in ServiceTBVOOS Turbine Bypass Valves Out of ServiceTCV Turbine Control ValveTSV Turbine Stop ValveDoe ID: COLR Limerick I, Rev. I IPage 5 of 54 Exelon Nuclear -Nuclear Fuels Doe II): COLR Limerick 1, Rev. I ICore Operating Limits ReportNon-Proprietary Infirmation Submitted in Accordance with 10 CFR 2.3902.0 General Information This report provides the following cycle-specific paiurneter limits for Limerick Generating Station Unit I Cycle16:* Maximum Average Planar Linear Heat Generation Rate (MAPLIHGR)

• Minimum Critical Power Ratio (MCPR)* Single Loop Operation (SLO) MCPR adjustment
• ARTS MCPR thennal limit adjustmnents and multipliers (MCPR(P) or MCPR(F))* ARTS LH-IGR thermal limit multipliers (LHGRFAC(P) or LHIGRFAC(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) TripSetpoints This report is prepared in accordance with Technical Specification 6.9.1.9 of Reference

1. Power and flowdependent limits are listed for various power and flow levels. Lincar interpolation is to be used to findintermedliate values.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 the minimum licensed core flow (i.e., 82.9% ofrated) during full power operation
• Increased Core Flow (ICF) up to 110% of rated core flow* Final Feedwater Temperature Reduction (FFWTR) up to 105.0'F during cycle extension operation
• Feedwater Heater Out of Service (FWHOOS) up to 60.0°F feedwater temperature reduction at anytime during the cycle prior to cycle extension.

Further information on the cycle-specific analyses for Limerick Unit I Cycle 16 and the associated operating domains discussed above is available in Reference 2 and Reference 7.Page 6 of 54 Eseloni Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Infornmationi Submitted in Accordance with 10 CFR 2.390Doe ID: COLR Limnrcick I, Rev. I I3.0 MAPLHGR Limits3. 1 Technical Specification Section 3.2.13.2 Description The limiting MAPLHGR value for the most limiting lattice (excluding natural uranium) of eachfuel type as a function of average planar exposure is given in Tables 3-1 and 3-2. For single loopoperation, a multiplier is used, which is shown in Table 3-3. The power and flow dependent multipliers for MAPLIIGR have been removed and replaced with LHGRFAC(P) andLI-IGRFAC(F); therefore, MAPFAC(P) and MAPFAC(F) are equal to 1.0 for all power andflow conditions (Reference 2). LHGRFAC(P) and LHIGRFAC(F) are addressed in Section 5.0.Table 3-1MAPLHGR Versus Average Planar Exposure -GE14(Reference 2)Table 3-2MAPLHGR Versus Average Planar Exposure -GNF2(Reference 2)Average Planar Exposure MAPLHGR LimitLGWD/ST[) (kW/ft)0.00 13.7813.24 13.7817.52 13.7860.78 7.5063.50 6.69Table 3-3MAPLHGR Single Loop Operation (SLO) Multiplier -All Fuel Types(Reference 2)I SLO Multiplier 0.80Page 7 of 54 Excloi Nuclear -Nuclear Fuels Doc I): COLR Limerick I, Rev. I ICore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CIR 2.3904.0 MCPR Limits4. I Technical Specification Section 3.2.34.2 Description Tables 4-1 and 4-2 are derived from References 2 and 7 and are valid for all Cycle 16 operating domains. Table 4-1 is valid for GE14 fuel and Table 4-2 is valid for GNF2 fuel. Tables 4-1 and 4-2include treatment of these MCPR limits for all conditions listed in Section 9.0, Modes of Operation. Limerick Unit I Cycle 16 has a mid-cycle MCPR breakpoint, as defined in Tables 4-1 and 4-2. TheBASE, TBVOOS, and RPTOOS MCPR limits include the conservative assumption ofsimultaneous TC.V and TSV closure during a turbine trip, as discussed in Reference

7. Lessrestrictive MCPR limits for the BASE DLO Option B condition are provided for a 100 ins orgreater delay in the start of TCV closure following a turbine trip. The less restrictive limits mayonly be used if it is confirmed that the 100 ins or greater delay exists following Digital EHCmodification.

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 adjustment MCPR(F) is sufficiently generic to apply to all fuel types and operating domains.The power dependent 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 six sets ofpower dependent MCPR multipliers (Kp) for use With the BASE, TBVOOS, and RPTOOSconditions, in DLO and SLO operation. The PLUOOS condition is included in the BASEMCPR(P) and MCPR(F) limits and Kp multipliers and is bounded by the TBVOOS limits andmultipliers; therefore, no additional adjustments are required for PLUOOS in those operating conditions. The PLUOOS condition has not been analyzed concurrent with the RPTOOS operating condition. Operation in the PLUOOS condition concurrent with the RPTOOS condition requirescore thermal power < 55% of rated (Reference 3). Section 7.0 contains the conditions for TurbineBypass Valve Operability. MCPR(P) and MCPR(F) adjustments for all fuel types are provided inTable 4-3 and 4-4, respectively. The OLMCPR is determined for a given power and flowcondition by evaluating the power dependent MCPR and the flow dependent MCPR andselecting the greater of the two.Page 8 of 54 E'xelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitted in Accordanmce with 10 CFR 2.390Doc II): COLR Limerick 1, Rev. I ITable 4-1Operating Limit Minimum Critical Power Ratio (OLMCPR) -GE14(References 2 n(1 7)Cycle ExposureSCRAM Time < EOR -3234 > EOR -3234EOOS Combination Option, MWd/ST MWd/STB 1.39 1.41BASE B (21 1.38 (' 1.41 (2)A 1.47 1.49BASESW B 1.46 1.46BASE__LO_ A 1.50 1.52B 1.42 1.44TBVOOS A 1.51 1.53TBVOOS SLO' B 1.46 1.47A 1.54 1.56B 1.42 1.53A 1.59 1.70RPTOOS SLO3 B 1.46 1.56H A 1.62 1.73Table 4-2Operating Limit Minimum Critical Power Ratio (OLMCPR) -GNF2,(References 2 and 7)Cycle ExposureSCRAM Time < EOR -3234 > EOR -3234EOOS Combination Option1 MWd/ST MWd/STB 1.39 1.41BASE B 2) 1.38 (21 1.41 (2)A 1.47 1.49BASE SLO3 B 1.58 1.58A 1.58 1.58B 1.42 1.44A 1.51 1.53TBVOOS SL03 B 1.58 1.58A 1.58 1.58B 1.42 1.53RPOSA 1.59 1.70RPTOOS SLO3 B 1.58 1.58A 1.62 1.731 When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation. 2 Limit is only applicable if it is confirmed that a 100 ms or greater delay exists in the start of TCV closurefollowing a turbine trip.3 For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed two loop value.However, a minimnum value of 1.46 for GEM4 fuel and 1.58 for GNF2 fuel is required to obtain anOLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).Page 9 of 54 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Inforimation Subimitted in Accordance with 10 CFR 2.390D)oc II): COI.,I Limerick I, Rev. I ITable 4-3Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp -All Fuel Types(References 2 and 7)Core Core Thermal Power (% of Rated)EOOS Flow 0 2S <30 >301 65 185 100Combination (% of Operating Limit MCPR, Operating Limit MCPRrated) MCPR(P) Multiplier, KpBASE 60 2.50 2.50 2.40 1.340 1.131 1.067 1.000> 60 2.75 2.75 2.55< 60 2.53 2.53 2.43BASE SLO >60 2.78 2.78 2.58 1.340 1.131 1.067 1.000TBVOOS < 60 3.25 3.25 2.75 1.340 1.131 1.067 1.000> 60 3.75 3.75 3.25TBVOOS 60 3.28 3.28 2.78 1.340 1.131 1.067 1.000SLO > 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 2.55RPTOOS S 60 2.53 2.53 2.43 1.340 1.131 1.067 1.000SLO > 60 2.78 2.78 2.58 1 1Table 4-4Flow Dependent MCPR Limits MCPR(F) -All Fuel Types(References 2 and 7)Flow MCPR(F)(%rated) Limit0.0 1.7030.0 1.5379.0 1.25110.0 1.25Page 10 of 54 Exelon Nuclear -Nuclear Fuels Doe ID: COIR Limerick 1, Rev. I ICore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2-3905.0 LIFIGR Limits5.1 Technical Specification Section 3.2.45.2 Description The LHGR limit is the product of the exposure dependent LHIGR limit (firom Table 5-1 for U02ftel rods and Table 5-2 for Gad6linia fuel rods) and the minimum of: the power dependent LHIGRFactor, LI-IGRFAC(P), and the flow dependent LFIGR Factor, LI-IGRFAC(F). For single loopoperation, a multiplier is used, which is shown in Table 5-3 and applied in Table 5-5. No furtherSingle Loop Operating 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 LIIGR multipliers for dual-loop and single-loop operation. In addition, there are six sets ofpower dependent LHGR multipliers for use with the BASE, TBVOOS, and RPTOOSconditions, in DLO and SLO operation. The PLUOOS condition is included in the BASELI-IGRFAC(P) and LUIGRFAC(F) multipliers and is bounded by the TBVOOS multipliers; therefore, no additional adjustments are required for PLUOOS in those operating conditions. The PLUOOS condition has not been analyzed concurrent with the RPTOOS operating condition. Operation in the PLUOOS condition concurrent with the RPTOOS condition requires core thermal power <55% of rated (Reference 3). Tables 5-4 and 5-5 forLIIGRFAC(P) and LHGRFAC(F), respectively, are applicable to both GE14 and GNF2 fueltypes. Section 7.0 contains the conditions for Turbine Bypass Valve Operability. Linearinterpolation should be used for points not listed in Appendix A.Thermal limit monitoring must be performed with the more limiting LHGR limit resulting fromthe power and flow biased calculation. The LHGRFAC(P) curves are independent of recirculation pmnp trip operability. Table 5-1Linear Heat Generation Rate Limits -U02 Rods(Reference 5)Fuel Type LHGRGE14 See Appendix AGNF2 See Appendix ATable 5-2Linear Heat Generation Rate Limits -Gadolinia Rods(Reference 5)Fuel Type LHGRGEM4 See Appendix AGNF2 See Appendix APage 11 of 54 IExchlo Nuclear -Nuclear FuelsCore Operating Uinits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390Doe ID: COIR Limerick I, Rev. I ITable 5-3LHGR Single Loop Operation (SLO) Multiplier -All Fuel Types(Reference 2)I SLO Multiplier' 1 0.8()Table 5-4Power Dependent LHGR Multiplier LHGRFAC(P) -All Fuel Types(Reference 2)Core Core Thermal Power (% of rated)E O O S Flow 0_2_,_ <_ 30 _1 _a_30_1_6-5 Combination (% of 0 25 <30 >30 65 85 100rated) LHGRFAC(P) Multiplier BASE 60 0.485 0.485 0.490 0.750 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 0.473TBVOOS : 60 0.463 0.463 0.490 0.750 0.817 0.922 1.000> 60 0.352 0.352 0.386TBVOOS SLO 60 0,463 0.463 0,490 0.750 0.817 0.922 1.000> 60 0.352 0.352 0.386RPTOOS 60 0.485 0.485 0.490 0.750 0.817 0.922 1.000> 60 0.434 0.434 0.473 1< 60 0.485 0.485 0.490RPTOOS SLO 0.750 0.817 0.922 1.000> 60 0.434 0.434 0.473Table 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) Multiplier Dual Loop 0.506 0.706 0.973 1.000 1.000Single Loop 0.506 0.706 0.800 0.8001 Applied through Table 5-5Page 12 of 54 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Intormation Submitted in Accordance with 1) CFR 2.390I)oc ID: COLR Limerick I, Rev. I I6.0 Control Rod Block Sctpoints 6.1 Technical Specification Sections 3.1.4.3 and 3.3.66.2 Description The ARTS Rod Block Monitor provides for power dependent RBM trips. Technical Specification 3.3.6 states control rod block instrumentation channels shall be OPERABLE with their tripselpoints consistent with the values shown in the Trip Sctpoint column of Technical Specification Table 3.3.6-2. The trip setpoints/allowable values and applicable RBM signal filter time constantdata are shown in Table 6-I. The Reactor Coolant System Recirculation Flow Upscale Trip isshown in Table 6-2. These setpoints are set high enough to allow fuill utilization of the enhancedICF domain up to 110% of rated core flow.Table 6-1Rod Block Monitor Setpoints' (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%FITSP 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 1.37, which is less than the minimumr cycle OLMCPR.Page 13 of 54 Exehon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2390Doc I D: COLR Limerick 1, Rev. I I7.0 Turbine Bypass Valve Parameters

7. I Technical Specification Sections 3.7.8 and 4.7.8.c7.2 Description The operability requirements for the steam bypass system are found in Tables 7-I and 7-2. If theserequirements cannot be met, the MCPR, MCPR(P) and LI-IGRFAC(P) limits for inoperable SteamBypass System, known as Turbine Bypass Valve Out Of Service (TBVOOS),

must be used.Additional infonnation 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 secfollowing initial turbine inlet valve movementMaximum time after initial turbine inlet valve movement' forbypass valve position to reach 80% of fill flow (includes the 0,31 secabove delay time)First movement of any TSV or any TCV or generation of the turbine bypass valve flow signal (whichever occurs first)Table 7-2Minimum Required Bypass Valves To Maintain System Operability (Reference 3)Reactor Power No. of Valves in ServiceP > 25% 7Page 14 of 54 Exelon Nuclear -Nuclear FuelsCore Operating Limiits ReportNon-Proprielary hIformation Submitted in Accordance with 10 CFR 2390)D)oe ID: COIAR Limerick I, Rev. I I8.0 Stability Protection Sctpoints

8. I Tcchnical Specification Section 2.2.18.2 Description The Limerick Unit I Cycle 16 OPRM PBDA Trip Setpoints for the OPRM System, are found inTable 8-I. These values are based on the cycle specific analysis documented in Reference

2. Thesetpoints provided in Table 8-I are bounding for all modes of operation shown in Table 9-1. Thesetpoints provided in Table 8-2 are acceptable for use in Single Loop Operation.

The standard twoloop operation OPRM Setpoints specified in Table 8-1 must be implemented prior to restarting theidle pumnp when exiting the SLO condition. Table 8-1OPRM PBDA Trip Setpoints (Reference 2)PBDA Trip Amplitude C Corresponding MaximumConfirmation Count Trip Setting1.12 < 14Table 8-2SLO OPRM PBDA Trip Setpoints (Reference 2)PBDA Trip Amplitude I Con'esponding MaximumiA Confirmation Count Trip Setting 1.15 < 16Page 15 of 54 Exclon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10) CF1Z2.390 Doc I): COLR Limerick 1, Rev. II9.0 Modes of Operation

9. I Description The allowable modes of operation arc found in Table 9-1. Operation with PROOS, I MSIVOOS,or I TCViTSV OOS is supported in all modes of operation, provided the restrictions identified inthe applicable station procedures arc met. All FOOS options also support the allowance of ITIPOOS. A nominal LPRM calibration interval of 2000 EFPH (2500 EFPH maximum) issupported in accordance with Technical Specification 4.0.2 and 4.3.1.1.

All FOOS options allowfor 2 inoperable safety relief valves. The Operating Region in Table 9-1 refers to operation on thePower to Flow map with or without FWI-IOOS/FFWTR. Table 9-1Modes of Operation (Reference 2)EOOS Options Operating RegionBASE, Option A or B Yes,BASE SLO, Option A or B Yes_TBVOOS, Option A or B Yes'TBVOOS SLO, Option A or B Yes_RPTOOS, Option A or B yes_RPTOOS SLO, Option A or B Yes2TBVOOS and RPTOOS, Option A or B NoTBVOOS and RPTOOS SLO, Option A or B No1 The PLUOOS condition is supported in this mode of operation with no power reduction required. 2 The PLUOOS condition requires core thermal power level < 55% of rated (Reference 3).Page 16 of 54 Exehoi Nuclear -Nuclear Fuels Dc II): COLR Limerick I, Rev. I ICore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2.39010.0 Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed andapproved by the NRC, specifically those described in the following documents: I. "General Electric Standard Application for Reactor Fuel," NEDE-2401 I -P-A-20, December 2013 and U.S.Supplement N EDE-2401 I-P-A-20-US, December 2013.2. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for ReloadApplications," NEDO-32465-A, August 1996.11.0 References

1. "Technical Specifications and Bases for Limerick Generating Station Unit I", Docket No. 50-352, LicenseNo. NPF-39.2. "Supplemental Reload Licensing Report for Limerick I Reload 15 Cycle 16", Global Nuclear FuelDocument No. 000N3893-R I-SRLR, Revision I, February 2014.3. "Final Resolved OPL-3 Parameters for Limerick Unit I Cycle 16", Exelon TOD] ES1300017 Rev. 0,October 23, 2013.4. "GE NUMAC PRNM Setpoint Study", Exelon Design Analysis LE-0107, Rev. 2, February 23, 2012.5. "Fuel Bundle Information Report for Limerick I Reload 15 Cycle 16", Global Nuclear Fuel Document No.000N5028-FBIR-NP, Revision 1, February 2014.6. "Tech Eval Stop Valve Load Limit Documentation",

Exelon Document IR 917231 Assignment 7,November 11, 2009.7. "Limerick Unit I Cycle 16 Contingency FWCF Analysis", GE Hitachi Nuclear Energy Document No.000N5273-RO, March 10, 2014.Page 17 of 54 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390Doc II): COI,R limerick I, Rev. IIAppendix APage 18 of 54 Exelon Nuclear -Nuclear FueLsCore Operating Limits RepoilNon-Propiietary Information Submitted in Accordance wilh 10 CFR 2.390Doc ID: COLR Limerick 1, Rev. IIGNCFGlobal Nuclear FuelA Joint Vanloe d OETozhiba, & HitachiGlobal Nuclear Fuel000N5028-FBIR-NP Revision 1February 2014Non-Proprietaiy Information -Class I (Public)Fuel Bundle Information ReportforLimerick 1Reload 15 Cycle 16Copyright 2014 Global Nuclear Fuel -Americas, LLCAll Rights ReservedPage 19 of 54 Exclon Nuclear -Nuclear Fuels Doc ID: COLR iimerick 1, Rev. IICore Operating Limits ReporlNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information 000N5029-FBIR-NP Reload 15 Class I (Public) Revision IImportant Notice Regarding Contents of This ReportPlease Read Carefully This report was prepared by Global Nuclear Fuel -Americas, LLC (GNF-A) solely for use by ExelonCorporation ("Recipient") in support of the operating license for Limerick Unit I (the "Nuclear Plant").The information contained in this report (the "Information") is believed by GNF-A to be an accurate andtrue representation of the licts known by, obtained by or provided to GNF-A at the time this report wasprepared. 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. Information NoticeThis is a non-proprietary version of the document 000N5028-FBIR-P, Revision 1, which has theproprietary information removed. Portions of the document that have been removed are indicated by anopen and closed bracket as shown here A. ]].Page 20 of 54Page 2 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNou-Propiietaity Information Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Limerick 1, Rev. I I000N5028-FBIR-NP Revision II. Introduction and SummaryThis report, which supplements the Supplemential Reload Licensing Report, contains thernmal-nmechanical linear heat generation rate (L-IGR) limits f'or the GNF-A fuel designs to be loaded into Limerick I IfrCycle 16. These LHGR limits are obtained firom thermal-mechanical considerations only. ApprovedGNF-A calculation models documented in Reference I were used in performing this analysis. LHIGR limits as a I'unction of`exposure for each bundle of'the core design are given in Appendix A. TheLI-IGR values provided in Appendix A provide upper and lower exposure dependent LHIGR boundaries which envclope ihe actual gadolinia dependent LHGR limits. The LHGRs reported have been rounded totwo places past the decimal.Appendix B contains a description of the fuel bundles. Table B-I contains a summary of bundle-specific information, and the figures provide the enrichment distribution and gadolinium distribution for the fuelbundles included in this appendix. These bundles have been approved for use under the fuel licensing acceptance criteria of Reference I.Page 21 of 54Page 3 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Infortualion Submitled in Accordance with 10 CFR 2.390Doc ID: COLR Limerick 1, Rev. II000N5028-FBIR-NP Revision ILimerick Unit IReload 15Non-Proprietary inllbrmation Class I (Public)2. References I. Ge.,neral Heei'criw:

• Slcma'd AI lpliccilio~t~fir IR r 1 tl, NEE-2401 I -P-A-20,

[)Dcember 201 31 indthe U.S. N EDE-24() I -I1-A-20-US, Deccmbcr 2013.Page 22 of 54Page 4 Exelon Nuclear -Nuclear FuelsCore Operating Limits RepoilNon-Proprietary Information Submited in Accordance wvilh 10 CFR 2.390Doc ID: COLR Limerick 1, Rev. II00ON5028-FBIR-NP Revision ILimerick Unit IReinad 15Non-Proprietary Information Class I (Puiblic'! Appendix AU02/Gd Thermal-Mechanical LHGR LimitsBundlc Tl'ypc: GE 14-PI OCNA[3394-15IGZ-120T- 150-T6-3271 (GE I14C)Bundle Number: 3271Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ft[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit'GWd/MT (GWd/ST) kW/ft[[Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle designPage 23 of 54Page 5 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitled in Accordance with 10 CFR 2394)Doc ID: COLR Limerick I, Rev. I I000N5028-FBIR-NP Revision ILimerick Unit IReload 15Non-Proprietary Information Class I (Public)UO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GE 14-P 0OCNAB401-13GZ-120T- 150-T'6-3273 (GE 14C)Bundle Number: 3273Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ft[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit2GWd/MT (GWd/ST) kW/ft2 Bounding gadolinia LHGR limit for allR[ I].gadolinium concentrations occurring in this bundle designPage 24 of 54Page 6 Exelon Nuclear -Nuclear Fuels('ore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2390Limerick Unit I Non-Proprictary Inflornation Reload 15 Class I (Public)D)oc ID: COLR Limerick 1, Rev. II000N5028-FBIR-NP Revision IU02/Gd Thermal-Mechanical LHGR Limits3undlC Typc: GF 1 4-P I OCNA [B402-1 3GZ- 1 20T- 1 50-T6-3274 (GE I4C)Bundle Number: 3274Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftrrPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit3GWd/MT (GWd/ST) kW/ft[[ ___________________ Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[[ ]].Page 25 of 54Page 7 Exelon Nuclear -Nuclear FuelsCore Operating L.imits ReporlNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Limerick 1, Rev. I I000N5028-FBIR-NP Revision IUO2/Gd Thermal-Mechanical LHGR LimitsBundle Type: GE 14-P I OCNAB398-12GZ-120"1"- 150-T6-3275 (GE I 4C)Bundle Number: 3275Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit 4SGWd/MT (GWd/ST) kW/ftI_____________________________ 4 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle designR ]I-Page 26 of 54Page 8 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Propiietary Information Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary infornmation Reload 15

• Class I (Public)Doc ID: COLR Linerick I, Rev. I I000N5028-FBI R-NPRevision IUO21Gd Thermal-Mechanical LHGR LimitsBundle Type: iF I4-P10OCNAB394-1I5GZ-1201'- 150-1"6-3272 (GE 14C)Bundle Number: 3272Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit'GWd/MT (GWd/ST) kW/ftS Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[[ ]].Page 27 of 54Page 9 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReporlNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Limerick 1, Rev. 11000N5028-FBIR-NP Revision IUO21Gd Thermal-Mechanical LHGR LimitsBundle Type: ON F2-P I 0CG21B393-I 0G7.0/2G6.0-120T2-1550-T6-4048 (GN F2)Bundle Number: 4048Peak Pellet Exposure UO2 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit6GWd/MT (GWd/ST) kW/ft[[i____________________

_______________________________ ]]6 Bounding gadolinia LHGR limit for all gadolinium conccntrations occurring in this bundle design[1 1].Page 28 of 54Page 10 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Propiietary Information Submitted in Accordance with 10 CFR 2.39.0Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Limerick 1, Rev. II000N5028-FBI R-NPRevision IUO2/Gd Thermal-Mechanical LHGR LimitsBundle Type: GN F2- PI 0CG2B404-12G6.0-1 00'1"2-150--f6-4044 (ON F2)Bundle Number: 4044Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit7GWd/MT (GWd/ST) kW/ft7 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[[ ]I-Page 29 of 54Page I I Exelon Nuclear -Nuclear FuelsCore Operating Limits RepoilNon-Proplietfry Information Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Informnation Reload 15 Class I (Public)Doc ID: COLR L.imerick 1, Rev. 11000N5028-FBI R-NPRevision IUO2/Gd Thermal-Mechanical LHGR LimitsBundle Type: GN F2-P IOCG2B404-12G6.0-120T2-150-T6-3643 (G NF2)Bundle Number: 3643Peak Pellet Exposure U02 LHGR LimitGWd/MNT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit'GWd/MT (GWdtST) kW/ft_____________________ iBounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[[ ]]i.Page 30 of 54Page 12 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390Doc ID: COLR iimerick 1, Rev. I I000N5028-FI3IR-NP Revision ILimerick Unit IReload I 5Non-Proprietary Inlformation (-lass I (Public)U02/Gd Thermal-Mechanical LHGR LimitsB3undlC Typc: GN F2-PI 0CG2B387-15GZ-I 2012-150-1'6-4045 (GNF2)Bundle Number: 4045Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit9GWd/MT (GWd/ST) kW/ft[[______________________________ ]]9 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[I I].Page 31 of 54Page 13 Exclon Nuclear -Nuclear FuelsCove Operating Limits ReporlNon-Proprietai lmnfornmation Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Infonmmation Reload IS Clas.Is I (Public)Doc ID: COI.R L.imerick 1, Rev. II000N5028-FBIR-NP .Revision IU02/Gd Thermal-Mechanical LHGR LimitsBundle Type: GN F2-P I 0C'G2B388-13GZ-(GN F2)Bundle Number: 4046Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit "0GWd/MT (GWd/ST) kW/ft[[10 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle designPage 32 of 54Page 14 E'xelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitled in Accordance with 10 CFR 2.390Limerick Unit 1 Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Limerick 1, Rev. 1000N5029-FBIR-NP Revision IUO2lGd Thermal-Mechanical LHGR LimitsBundle Typc: GNF2-P I 0CG2B392-15GZ-1 20T2-150-T6-4047 (CiNF2)Bundle Number: 4047Peak Pellet Exposure U02 LHGR LimitCWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit'1GWd/MT (GWd/ST) kW/ft[[_____________________________ ]1" Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle designPage 33 of 54Page 15 Exelon Nuclear -Nuclear FuecsCore Operating Limits ReporlNon-Proplietary Information Submitted in Accordance with 10 CFR 2.390Limerick Unit 1 Non-Proprietary Information Reload 15 Class I (Public)Doc [D: COOLR Limerick 1, Rev. II000N5028-FBIR-NP Revision IUO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-1" I 0CG2B386-l46Z-120T2-1 50-T6-4272 (GNF2)Bundle Number: 4272Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit'2GWd/MT (GWd/ST)- kW/ft[[___________________1 32 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle designIf fl.Page 34 of 54Page 16 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprie(ary lnfornation Submitted in Accordance with 10 CFR 2.390Doc ID: COLR Limerick 1, Rev. I I000N5028-FBIR-NP Revision ILimerick Unit IReload IsNon-Proprietary Inlformation Class I (PtbliclUO2/Gd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-P I 0CG2B387-13(i7.0-120T2-150-T'6-4274 (ON F2)Bundle Number: 4274Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/S'T) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit'3GWd/MT (GWd/ST) kW/ftt[[Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle designPage 35 of 54Page 17 Exelon Nuclear -Nuclear Fuels('ore Operating Limits ReportNon-Proprietary Information Submitted in Accordance wifh 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR L.imerick 1, Rev. I I000N5028-FBIR-NP Revision IUO2Gd Thermal-Mechanical LHGR LimitsBundle Type: GN F2-P I OCG2 B400-13Gi7.0-120T2-150-T6-4275 (GN F2)Bundle Number: 4275Peak Pellet Exposure U02 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit 14GWd/MT (GWd/ST) kW/ft[[I14 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design11 1i.Page 36 of 54Page 18 Exeloti Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Inlormation Submitted in Accordance with 10 (FR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Limerick 1, Rev. I I000N5028-FBI R-NPRevision IUO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GN F2- PI 0CG2B387-12G7.0-120'T'2-150-'1"6-4273 (GN F2)Bundle Number: 4273Peak Pellet Exposure UO2 LHGR LimitGWd/MT (GWd/ST) kW/ftPeak Pellet Exposure Most Limiting Gadolinia LHGR Limit'sGWd/MT (GWd/ST) kW/ft[[l'5 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[[ ]].Page 37 of 54Page 19 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submilled in Accordance willh 10 CFR 2.390Limerick Unit 1 Non-Proprictary Inflormation Reload 15 Class I (Public)Doc ID: COLR Limerick 1, Rev. I I000N5028-FIBIR-NP Revision IAppendix B .Fuel Bundle Information Table B-IBundle Specific Information Fuel Bundle Enrichment Weight Weight Max Exposureof U02 of U ky at at Max k,Bundle Number (wt% U-235) 200C GWd/MT(kg) (kg) 16 (GWd/ST)GE14-P IOCNAB394-15GZ-120"1'-150-T6-3271 (GE14C)GEI4-PI 0CNAB40I-I13GZ-120T-150-T6-3273 (GEI4C)GE 14-P I OCNAB402-13GZ-120T- 150-T6-3274 (GE 14C)GEI4-PIOCNAB398-12GZ-3275120T- I 50-T6-3275 (GE I4C)GE I 4-P I OCNAB394-15GZ-120T-150-T6-3272 (GE14C)GNF2-PI0CG2B393-I 0G7.0/2G6.0-120T2-150-T6-40484048 (GNF2)GNF2-P 10CG2B404-12G6 .0-1 00T2-150-T6-4044 (GNF2)GNF2-P 10CG2B404-12G6.0-120T2-150-T6-3643 (GNF2)GNF2-P I 0CG2B387-15GZ-1 20T2-150-T6-4045 (GNF2)GNF2-P1OCG2B388-13GZ-120T2-150-T6-4046 (GNF2)GNF2-PI 0CG2B392-15GZ-120T2-150-T6-4047 (GNF2)GNF2-P 10CG2B386-14GZ-120T2-150-T6-4272 (GNF2)GNF2-Pl0CG2B387-13G7.0-120T2-150-T6-4274 (GNF2)16 Maximum lattice k. for the most reactive uncontrolled state plus a [[]] adder for uncertainties. Page 38 of 54Page 20 FLxelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CI.R 2.390Limerick Unit I Non-Proprietary Inlformation Reload 15 Class I (Public)Doc ID: C'OLR Literick I, Rev. I I000N5028-FBIR-NP Revision ITable B-IBundle Specific Information Fuel Bundle Enrichment Weight Weight Max ExposureFue BudleEnrchmntOf U .02 Of U Ic at at Max kc-,Bundle Number (wt U-235) oU o 200C GWd/MT(kg) (kg) , (GWd/ST)(GN F2-P I OCG2 B400-13M7.0-12012-150-T6-4275 (GNF2)(vNF2-P10CG2B387-12G7.0-120T2-150-T'6-4273 (GNF2)Page 39 of 54Page 21 Exelon Nuclear -Nuclear FuelsCore Operating Lhniis ReportNon-Proprietary Information Submitted in Accoilance %iOlh 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Uinierick

1. Revi. I I000N5028-FBIR-NP Revision Iff]]Figure B-I Enrichment and Gadolinium Distribution for EDB No. 3271Fuel Bundle GE14-PIOCNAB394-15GZ-120T-150-T6-3271 (GE14C)Page 40 of 54Page 22 Exelon Nuclear -Nuclear Fuels('ore Operating Limits ReportNon-Proprietary Inflrmation Submitled in Accordance wvith 10 ('FR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)D)oc ID: COLR Limerick 1, Rev. 11000N5028-FBIR-NP Revision I11Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 3273Fuel Bundle GEl4-PIOCNAB401-13GZ-120T-150-T6-3273 (GE14C)Page 41 of 54Page 23 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReporlNon-Proprietary Informallon Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Limerick 1, Rev. I I000N5028-F'B I R-N PRevision IFigure B-3 Enrichment and Gadolinium Distribution for EDB No. 3274Fuel Bundle GEl4-PIOCNAB402-13GZ-120T-150-T6-3274 (GEl4C)Page 42 of 54Page 24 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReporlNon-Proprielanr Information Submitted in Accordance wvith 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public).Doc ID: COLR Limerick

.1, Rev. II000N5028-FBIR-NP Revision Ii1Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 3275Fuel Bundle GEl4-PIOCNAB398-12GZ-120T-150-T6-3275 (GEl4C)Page 43 of 54Page 25 Exelon Nuclear -Nuclear FuelsCore Operating Limits RepoilNon-Proprietary Inforlmation Submitted iln Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Limerick 1, Rev. 11000N5028-F'BIR-NP Revision I[[]]Figure B-5 Enrichment and Gadolinium Distribution for EDB No. 3272Fuel Bundle GEl4-P1OCNAB394-15GZ-120T-150-T6-3272 (GEl 4C)Page 44 of 54Page 26 Exclon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-l'ropiietary Information Submitted in Accordance with 10 CFR 2.390Doc ID: COLR L.imerick 1, Rev. 100ON5029-FBIR-NP Revision ILimerick Unit IReload ISNon-Proprietary Information Class I (lPublic) ]]Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 4048Fuel Bundle GNF2-PIOCG2B393-10G7.0/2G6.0-120T2-150-T6-4048 (GNF2)Page 45 of 54Page 27 E~xelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc liD: COLR Limerick 1, Rev. II000N5028-FBIR-NP Revision IH[]]Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 4044Fuel Bundle GNF2-PIOCG2B404-12G6.0-100T2-150-T6-4044 (GNF2)Page 46 of 54Page 28 EAelon Nuclear -Nuclear FuelsCore Operating Limits ReporlNon-Proprietary Inlfrmation Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Limerick 1, Rev. II00ONS02-FBIR-NP Revision I[FFigure B-8 Enrichment and Gadolinium Distribution for EDB No. 3643Fuel Bundle GNF2-PI0CG2B404-12G6.0-120T2-150-T6-3643 (GNF2)Page 47 of 54Page 29 Exelon Nuclear -Nuclear Fuels('ore Operating itmits ReportNon-Proprielan" Informalion Submitted in Accordance with 10 CFR 2.390Doc ID: COI.R Limerick 1, Rev. 1I000N5028-FBIR-NP Revision ILimerick Unit IReload 15Non-Proprietary Infonriation Class I (Public)1I11Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 4045Fuel Bundle GNF2-PIOCG2B387-15GZ-1 20T2-150-T6-4045 (GNF2)Page 48 of 54Page 30 xelon Nuclear -Nuclear Fuel%Core Operating Limils ReportNon-Propoietary Informalion Submitted in Accordance nith 10 CFR 2.390Doc ID: COLR Limerick 1, Rev. I I000N5028-FBIR-NP Revision ILimerick Unit IReload 15Non-Proprietary Information Class I (Public)[[1]Figure B-10 Enrichment and Gadolinium Distribution for EDB No. 4046Fuel Bundle GNF2-PI 0CG2B388-13GZ-120T2-150-T6-4046 (GNF2)Page 49 of 54Page 31 Exclon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Inforantion Submitled in Accordance wiith 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Limerick 1, Rev. I I000N5029-FBIR-NP Revision If[1]Figure B-I 1 Enrichment and Gadolinium Distribution for EDB No. 4047Fuel Bundle GN F2-PI 0CG2B392-1 5GZ-120T2-150-T6-4047 (GNF2)Page 50 of 54Page 32 Exclon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprielary Information Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Infornation Reload 15 Class I (Public)Doc ID: COLR Limerick

1. Rev. 11000N5028-FBIR-NP Revision IIf]]Figure B-12 Enrichment and Gadolinium Distribution for EDB No. 4272Fuel Bundle GNF2-PI 0CG2B386-14GZ-I 2OT2-150-T6-4272 (GNF2)Page 51 of 54Page 33 Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Iniormation Submilted in Accordance with 10 (FR 2.390i)oc ID: COLR limerick 1, Rev. 11Limerick Unit 1Reload 15Non-Proprietary Information C(ass I (PulieHh000N5028-FBIR-NP Revision I[11]Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 4274Fuel Bundle GNF2-PIOCG2B387-13G7.0-120T2-150-T6-4274 (GNF2)Page 52 of 54Page 34 Exeloh Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class I (Public)Doc ID: COLR Limnerick 1, Rev. 1100ON5028-FBIR-NP Revision IFigure B-14 Enrichment and Gadolinium Distribution for EDB No. 4275Fuel Bundle GNF2-PI OCG2B400-13G7.0-120T2-150-T6-4275 (GNF2)Page 53 of 54Page 3 5 Exelon Nuclear -Nuclear FuelsCore Operating Linmits RepoilNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390i)oc IID: COLR Limerick

.1, Rev. II000N5028-FBIR-NP Revision ILimerick Unit IReload 15Non-Proprietary Information Class I (Publiel11Figure B-15 Enrichment and Gadolinium Distribution for EDB No. 4273Fuel Bundle GNF2-P10CG2B387-12G7.0-120T2-150-T6-4273 (GNF2)Page 54 of 54Page 36}}