ML13295A453

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Attachment 3, Core Operating Limits Report for Reload 19, Cycle 20, Revision 7
ML13295A453
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 10/02/2013
From: Barry Miller
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML13295A453 (60)
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-Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 Table of Contents Page 1.0 Terms and Definitions 5 2.0 General Information 7 3.0 MAPLHGR Limits 8 4.0 MCPR Limits 9 5.0 Linear Heat Generation Rate Limits 12 6.0 Rod Block Monitor Setpoints 14 7.0 Turbine Bypass Valve Parameters 15 8.0 EOC Recirculation Pump Trip (EOC-RPT) Operability 16 9.0 Stability Protection Oscillation Power Range Monitor (OPRM) 17 10.0 Asymmetric Feedwater Temperature Operation (AFTO) 18 11.0 Modes of Operation 23 12.0 Methodology 23 13.0 References 23 Appendix A 25 Page 2 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure -GEl4 8 Table 3-2 MAPLHGR Versus Average Planar Exposure -GNF2 8 Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier -GEl4 and GNF2 8 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) -All Fuel Types 10 Table 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers 10 Table 4-3 Flow Dependent MCPR Limits MCPR(F) 11 Table 4-4 SLO Flow Dependent MCPR Limits MCPR(F) 11 Table 5-1 Linear Heat Generation Rate Limits -U02 rods 12 Table 5-2 Linear Heat Generation Rate Limits -Gad rods 12 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 13 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) 13 Table 6-1 Rod Block Monitor Setpoints 14 Table 7-1 Turbine Bypass System Response Time 15 Table 7-2 Minimum Required Bypass Valves To Maintain System Operability 15 Table 9-1 OPRM PBDA Trip Settings 17 Table 9-2 OPRM PBDA Trip Settings -SLO 17 Table 10-1 AFTO Thermal Limit Penalties 18 Table 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTA < 55F 19 Table 10-3 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTA < 55F 19 Table 10-4 AFTO Operating Limit Minimum Critical Power Ratio -All Fuel 30F < FWT DELTA < 55F 20 Table 10-5 AFTO Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) 30F < FWT DELTA < 55F 21 Table 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 30F < FWT DELTA < 55F 21 Table 10-7 AFTO SLO Flow Dependent MCPR Limits MCPR(F) 30F < FWT DELTA < 55F 21 Table 10-8 AFTO MAPLHGR Reduction Factor 22 Page 3 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 10-9 AFTO MAPLHGR Single Loop Operation (SLO) Multiplier Table 11-1 Modes of Operation COLR Peach Bottom 3 Rev. 7 22 23 Page 4 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 1.0 AFTO ARTS BASE BOC EOC EOOS EOR FFWTI FWHO FWT HTSP ICF ITSP LHGR LHGRJ LHGR]LTSP MAPL.MCPR MCPRI MCPR MELLI OLMC OPRM PLUO(PROO RPTO(RBM RWE Terms and Definitions Asymmetric Feedwater Temperature Operation APRM and RBM Technical Specification Analysis Defines two (2) loop operation with at least seven turbine bypass valves in service and the reactor recirculation pump trip system in service.Beginning Of Cycle End of Cycle Equipment Out of Service. An analyzed option that assumes certain equipment to be non-operational End of Rated. The cycle exposure at which reactor power is equal to 100% (3514 MWth)with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.Final Feedwater Temperature Reduction OS Feedwater Heaters Out of Service Feedwater Temperature Rod Block Monitor High Trip Setpoint Increased Core Flow Rod Block Monitor Intermediate Trip Setpoint Linear Heat Generation Rate FAC(F) ARTS LHGR thermal limit flow dependent adjustments and multipliers FAC(P) ARTS LHGR thermal limit power dependent adjustments and multipliers Rod Block Monitor Low Trip Setpoint HGR Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio (P) ARTS MCPR thermal limit power dependent adjustments and multipliers (F) ARTS MCPR thermal limit flow dependent adjustments and multipliers LA Maximum Extended Load Line Limit Analysis PR Operating Limit Minimum Critical Power Ratio PBDA Oscillation Power Range Monitor Period Based Detection Algorithm OS Power Load Unbalance Out of Service S Pressure Regulator Out of Service)s Recirculation Pump Trip Out of Service Rod Block Monitor Rod Withdrawal Error Page 5 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 SLO TBVOOS Single Loop Operation Turbine Bypass Valves Out of Service Page 6 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 2.0 General Information This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 3 CYCLE 20 (RELOAD 19):* Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)* Single Loop Operation (SLO) MAPLHGR multipliers

  • Operating Limit Minimum Critical Power Ratio (OLMCPR)* ARTS MCPR thermal limit adjustments and multipliers
  • Single Loop Operation (SLO) MCPR adjustment
  • Linear Heat Generation Rate (LHGR)* ARTS LHGR thermal limit multipliers
  • Single Loop Operation (SLO) LHGR multipliers
  • Rod Block Monitor (RBM) Analytical Limits, Allowable Values and MCPR Limits* Turbine Bypass Valve Parameters
  • EOC Recirculation Pump Trip (EOC-RPT)

Parameters

  • Dual Loop Stability Protection

-Oscillation Power Range Monitor (OPRM) Trip Setpoints* Single Loop Stability Protection -Oscillation Power Range Monitor (OPRM) Trip Setpoints* Asymmetric Feedwater Temperature Operation (AFTO) thermal limit penalties These values have been determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysis are met.This report provides cycle-specific Operating Limit MCPR, LHGR, MAPLHGR thermal limits, and related information for the following conditions: 0 All points in the operating region of the power/flow map including Maximum Extended Load Line Limit (MELLL) down to 82.8% of rated core flow during full power (3514 MWt) operation* Increased Core Flow (ICF), up to 110% of rated core flow* End-of-Cycle Power Coastdown to a minimum power level of 40%* Feedwater Heaters Out of Service (FWHOOS) to 550 F temperature reduction* Final Feedwater Temperature Reduction (FFWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) to 900 F temperature reduction maintaining < 100% load line (4th and 5th stage FFWTR)* Asymmetric Feedwater Temperature Operation (AFTO)ARTS provides for power- and flow-dependent thermal limit adjustments and multipliers that allow for a more reliable administration of the MCPR and LHGR thermal limits. The OLMCPR for each fuel type is determined by the cycle-specific reload analyses in Reference

2. Rated LHGR values are obtained from the bundle-specific thermal-mechanical analysis.

Supporting documentation for the ARTS-based limits is provided in Reference

2. The Allowable Values, documented in Reference 5, for feedwater temperature as a function of thermal power for both FWHOOS and FFWTR are specified in the appropriate Peach Bottom procedures.

Also note that the following description of MAPLHGR, LHGR and MCPR limits pertain to NON -AFTO conditions. A separate description of AFTO limits and their associated ARTS tables are located in Section 10.Preparation of this report was performed in accordance with Exelon Nuclear procedures. This report is submitted in accordance with Technical Specification 5.6.5 of Reference 1 and contains all thermal limit parameters related to the implementation of the ARTS Improvement Program and Maximum Extended Load Line Limit Analysis (ARTS/MELLLA) for Peach Bottom Unit 3 CYCLE 20.The "BASE" thermal limit values shown in tables are for normal two loop operation with at least seven turbine bypass valves in service and the reactor recirculation pump trip system in service.Page 7 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 3.0 MAPLHGR LIMITS 3.1 Technical Specification Section 3.2.1, 3.3.4.2, 3.4.1 and 3.7.6 3.2 Description The MAPLHGR limits (kW/ft) obtained from the emergency core cooling system (ECCS) analysis are provided in Tables 3-1 and 3-2. The MAPLHGR limits comprise a given fuel type as a function of average planar exposure. The MAPLHGR tables are used when hand calculations are required. All MAPLHGR values for each fuel type as a function of axial location and average planar exposure shall be less than or equal to the applicable MAPLHGR limits for the respective fuel and lattice types. These MAPLHGR limits are specified in Reference 2 and the process computer databank. The SLO MAPLHGR multiplier is applied as shown in Table 3-3 per Reference

2. The impact of AFTO on MAPLHGR is addressed in Section 10.TABLE 3-1 MAPLHGR Versus Average Planar Exposure-GE14 (Reference 2)Average Planar Exposure MAPLHGR Limit (GWD/ST) (kW/ft)0.0 12.82 19.13 12.82 57.61 8.00 63.50 5.00 TABLE 3-2 MAPLHGR Versus Average Planar Exposure-GNF2 (Reference 2)Average Planar Exposure MAPLHGR Limit (GWD/ST) (kW/ft)0.0 13.78 17.52 13.78 60.78 7.50 63.50 6.69 TABLE 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier

-GE14 and GNF2 (Reference 2)SLO Multiplier 0.73 Page 8 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 4.0 MCPR LIMITS 4.1 Technical Specification Section 2.1.1.2, 3.2.2, 3.3.4.2, 3.4.1 and 3.7.6 4.2 Description The Operating Limit MCPR (OLMCPR) for each fuel type is provided in Tables 4-1 and 4-2. These values are determined by the cycle-specific fuel reload analyses in Reference

2. Control rod scram time verification is required as per Technical Specification 3.1.4, "Control Rod Scram Times". Tau, a measure of scram time performance to notch position 36 throughout the cycle, is determined based on the cumulative scram time test results. The calculation of Tau shall be performed in accordance with site procedures.

Linear interpolation shall be used to calculate the OLMCPR value if Tau is between 0.0 (Tau Option B) and 1.0 (Tau Option A).Separate OLMCPR values are presented in Table 4-1 for the following domains: " TBVs In-Service (per section 7.0), RPT In-Service (per section 8.0), and maximum FFWTR of 90 'F" TBVs Out-of-Service (per section 7.0), RPT In-Service (per section 8.0), and maximum FFWTR of 90 'F" TBVs In-Service (per section 7.0), RPT Out-of-Service (per section 8.0), and maximum FFWTR of 90 'F The ARTS-based power-dependent MCPR limits are provided in Table 4-2. Table 4-2 is valid for a maximum temperature reduction of 90 'F for FFWTR operation. The flow-dependent MCPR limits are provided in Tables 4-3 and 4-4. Table 4-3 is valid for dual loop operating conditions with symmetric feedwater temperature operation and Table 4-4 is valid for single loop operating conditions with symmetric feedwater temperature operation. The impact of AFTO on MCPR is addressed in Section 10. Tables 4-1 through 4-4 are applicable to both GE 14 and GNF2 fuel type.Page 9 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)-AII Fuel Types (Reference 2)SCRAM Cycle Exposure Time < EOR -3621 > EOR -3621 EOOS Combination Option(') MWd/ST MWd/ST B 1.41(2) 1.41(2)BASE A 1.41(2) 1.41(2)BASE SLO(3)B 1.44 1.44 A 1.44 1.44 RPTOOS 1.41(2) 1.41(2)A 1.51 1.53 RPTOOS SLO(3) B 1.44 1.44 A 1.54 1.56 B 1.41(2) 1.41(2)______ A 1.41(2) 1.43 TBVOOS SLO (3) B 1.44 1.44_ _ A 1.44 1.46 TABLE 4-2 Power Dependent MCPR(P) Limit Adjustments And Multipliers (Symmetric Feedwater Heating)(Reference 2)Core Core Thermal Power (% of rated)EOOS Combination Flow (% 0 25 1<30 [>30 140 55 65 185 100 of rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp< 60 2.52 2.52 2.43 Base 1.352 1.352 1.317 1.131 1.082 1.000> 60 2.78 2.78 2.57< 60 2.55 2.55 2.46 Base SLOý3) -<60 2. 1.352 1.352 1.317 1.131 1.082 1.000> 60 2.81 2.81 2.60< 60 2.52 2.52 2.43 RPTOOS 1.352 1.352 1.317 1.131 1.082 1.000> 60 2.78 2.78 2.57 0() < 60 2.55 2.55 2.46 RPTOOS SLO(3) <2 1.352 1.352 1.317 1.131 1.082 1.000> 60 2.81 2.81 2.60< 60 3.28 3.28 2.78 TBVOOS 1.614 1.479 1.373 1.155 1.082 1.000> 60 3.78 3.78 3.30< 60 3.31 3.31 2.81 TBVOOS SLO(3) 1.614 1.479 1.373 1.155 1.082 1.000> 60 3.81 3.81 3.33 (1) When Tau does not equal 0 or 1, use linear interpolation. (2) OLMCPR is set to reflect two loop operation OPRM amplitude setpoint of 1.10.(3)For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed limiting two loop value (with the exception of the OPRM based OLMCPR, which remains the same). However a minimum value of 1.44 is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).Page 10 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 TABLE 4-3 Flow Dependent MCPR Limits MCPR(F)(Symmetric Feedwater Heating)(Reference 2)COLR Peach Bottom 3 Rev. 7 Core Flow (% rated) MCPR(F) Limit 0.0 1.701 30.0 1.530 79.0 1.250 110.0 1.250 TABLE 4-4(t SLO Flow Dependent MCPR Limits MCPR(F)(Symmetric Feedwater Heating)(Reference 2)Core Flow (% rated) MCPR(F) Limit 0.0 1.731 30.0 1.560 79.0 1.280 110.0 1.280 (1)For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed limiting two loop value (with the exception of the OPRM based OLMCPR, which remains the same). However a minimum value of 1.44 is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).Page II of25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 5.0 LINEAR HEAT GENERATION RATE LIMITS 5.1 Technical Specification Section 3.2.3, 3.3.4.2, 3.4.1 and 3.7.6 5.2 Description The LHGR values for each fuel type are provided in Table 5-land 5-2. The ARTS-based LHGR power-dependent multipliers are provided in Table 5-3. Table 5-3 is valid for a maximum temperature reduction of 90' F for FFWTR operation. The flow-dependent multipliers are provided in Table 5-4 as a function of the number of recirculation loops in operation. The SLO LHGR multiplier is 0.73 and is accounted for in Table 5-4. The power-and flow-dependent LHGR multipliers were obtained from Reference

2. Tables 5-3 and 5-4 are applicable to both GE14 and GNF2 fuel type. The impact of AFTO on LHGR is addressed in Section 10.TABLE 5-1 Linear Heat Generation Rate Limits -U02 rods (Reference 11)Fuel Type LHGR Limit GE14 See Appendix A GNF2 See Appendix A TABLE 5-2 Linear Heat Generation Rate Limits -Gad rods (Reference 11)Fuel Type LHGR Limit GE14 See Appendix A GNF2 See Appendix A Page 12 of 25 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 TABLE 5-3 Power Dependent LHGR Multiplier LHGRFAC(P)(Symmetric Feedwater Heating)(Reference 2)COLR Peach Bottom 3 Rev. 7 Core Thermal Power (% of rated)EOOS Combination (%of rated) 0 25 <30 >30 1 40 1 55 65 85 [100 LHGRFAC(P) Multiplier _<60 0.516 0.516 0.535 Base 0.750 0.756 0.771 0.817 0.959 1.000>60 0.516 0.516 0.535 1_1<60 0.516 0.516 0.535 Base SLO 0.750 0.756 0.771 0.817 0.959 1.000>60 0.516 0.516 0.535<60 0.516 0.516 0.535 RPTOOS 0.750 0.756 0.771 0.817 0.959 1.000>60 0.516 0.516 0.535<60 0.516 0.516 0.535 RPTOOS SLO 0.750 0.756 0.771 0.817 0.959 1.000>60 0.516 0.516 0.535< 60 0.42 1 0.42 1 0.482 TBVOOS 0.640 0.655 0.714 0.817 0.930 1.000> 60 0.414 0.414 0.424< 60 0.42 1 0.42 1 0.482 TBVOOSSLO 0.640 0.655 0.714 0.817 0.930 1.000> 60 0.414 0.414 0.424 TABLE 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)(Symmetric Feedwater Heating)(Reference 2)Core Flow (% of rated)EOOS Combination 0 30 33.6 1 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.506 0.706 0.730 0.973 1.000 1.000 Single Loop 0.506 0.706 0.730 0.730 0.730 0.730 Page 13 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 6.0 ROD BLOCK MONITOR SETPOINTS 6.1 Technical Specification Section 3.3.2.1 6.2 Description The RBM power-biased Analytical Limits, Allowable Values and MCPR Limits are provided in Table 6-1 with supporting documentation in References 2 and 9.TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 9)Power Level Analytical Limite) Allowable Value(I) MCPR Limit LTSP 125.8% 124.0% < 1.70 (2)< 1.40(2)ITSP 121.0% 119.2% < 1.70(2)< 1.40 )HTSP 116.0% 114.2% < 1.70(2)< 1.40 (3)INOP N/A N/A < 1.70 (2)< 1.40 (')(1) These setpoints (with RBM filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated RWE MCPR limit which is less than or equal to the minimum cycle OLMCPR based on other events (see COLR References 2 and 9).(2) This is the MCPR limit (given THERMAL POWER is >28.4% and < 90%) below which the RBM is required to be OPERABLE (see COLR Reference 2 and TS Table 3.3.2.1-1). (3) This is the MCPR limit (given THERMAL POWER is > 90%) below which the RBM is required to be OPERABLE (see COLR Reference 2 and TS Table 3.3.2.1-1). Page 14 of25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 7.0 TURBINE BYPASS VALVE PARAMETERS

7.1 Technical

Specification Section 3.7.6 7.2 Description The operability requirements for the steam bypass system are governed by Technical Specification 3.7.6.If the requirements cannot be met, the appropriate power and flow dependent limits for Turbine Bypass Valves Out-of-Service (TBVOOS) must be used. Additionally the OLMCPR for TBVOOS must be applied. Table 7-1 includes the Turbine Bypass Valve response time parameters. The minimum number of bypass valves to maintain system operability is provided in Table 7-2 per Reference 14.TABLE 7-1 Turbine Bypass System Response Time (Reference 14)Maximum delay time before start of bypass valve opening following generation of the turbine bypass valve flow signal 0.10 sec Maximum time after generation of a turbine bypass valve flow signal for bypass valve position to reach 80% of rated BPV 0.30 sec flow (includes the above delay time)TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability (Reference 14)Reactor Power No. of Valves in Service P 25% 7 Page 15 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 8.0 EOC RECIRCULATION PUMP TRIP (EOC-RPT) OPERABILITY

8.1 Technical

Specification Section 3.3.4.2 8.2 Description The operability requirements for the EOC Recirculation Pump Trip are governed by Technical Specification 3.3.4.2. If the requirements cannot be met, the appropriate power and flow dependent limits for EOC Recirculation Pump Trip Out Of Service (RPTOOS) must be used. Additionally the OLMCPR for RPTOOS must be applied.A total RPT response time of 0.175 seconds is assumed in the safety analysis and is defined as the time from the turbine valves (turbine control valve or turbine stop valve) start to close until complete arc suppression of the EOC-RPT circuit breakers. Reference 7 provides the basis for the RPT response time.Page 16 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 9.0 STABILITY PROTECTION OSCILLATION POWER RANGE MONITOR (OPRM)9.1 Technical Specification Section 3.3.1.1, Table 3.3.1.1 -1 Function 2.f 9.2 Description The CYCLE 20 OPRM Period Based Detection Algorithm (PBDA) Trip Settings are provided in Table 9-1 and 9-2. These values are based on the cycle specific analysis documented in Reference

2. The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system, Reference
13. The OPRM Growth Rate Algorithm (GRA) and Amplitude Based Algorithm (ABA) trip settings for dual loop and single loop can be found in the Power Range Neutron Monitoring Configuration Control Documents (SPID's) G-080-VC-174 through 177 (Unit-3).TABLE 9-1 OPRM PBDA Trip Settings (Valid for All Conditions)(Reference 2)PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting 1.10 13 TABLE 9-2 OPRM PBDA Trip Settings -SLO(')(Valid For SLO Conditions Only)(Reference 2)PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting 1.17 17 (1) The standard two loop operation OPRM Trip Settings specified in Table 9-1 must be implemented prior to restarting the idle pump when exiting the SLO condition.

Page 17 of125 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 10.0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION (AFTO)Asymmetric feedwater heating (resulting from removing a heater string, or individual feedwater heaters, from operation) is the result of the specific configuration of the feedwater lines at Peach Bottom. A reduction in heating in either the 'A' or the 'C' heater strings will result in a temperature mismatch between the feedwater flows entering the opposite sides of the reactor vessel. This temperature mismatch may result in errors in the thermal limit values calculated by the core monitoring system. Thermal limit values for all conditions and events are impacted by these errors excluding SLO conditions. The P3C20 COLR Rev. 7 is the first COLR for Unit 3 to no longer require implementation of SLO AFTO penalties. Because the station continues to require implementation of AFTO SLO curves the AFTO SLO curves will contain non AFTO SLO (SFTO) values for the same equipment conditions. Asymmetric feedwater temperature operation (AFTO) is defined as operation in a feedwater heater/string configuration that results in a specified threshold difference as described in Reference

10. To simplify the implementation of the AFTO limits, only the maximum AFTO penalties indicated in Table 10-1 will be implemented when the threshold asymmetry temperature (temperature above which a penalty is required) is exceeded.

This will minimize the number of AFTO thermal limit tables in the COLR and core monitoring system.TABLE 10-1 AFTO Thermal Limit Penalties (Asymmetric Feedwater Heating)(Reference 10)MFLCPR MFLPD/MAPRAT 40F < FWT DELTA < 55F 2% 4%30F < FWT DELTA < 40F 2% 3%20F < FWT DELTA < 30F No Penalty 2%OF < FWT DELTA < 20F No Penalty No Penalty LHGR LIMITS The ARTS-based LHGR power-dependent multipliers for AFTO operation are provided in Table 10-2. The flow-dependent multipliers for AFTO are provided in Table 10-3 as a function of the number of recirculation loops in operation only. The power-and flow-dependent LHGR multipliers were obtained from Reference 2 and were adjusted with the appropriate penalties displayed in Table 10-1 as per Reference

10. No LHGR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.

Because the station still requires physical implementation of the AFTO SLO curves non AFTO SLO values have been provided in the curves identified as AFTO SLO condition. The maximum feedwater temperature difference allowed without a thermal limit penalty is 20 'F. Once the temperature difference exceeds 20 'F the maximum penalties from Table 10-1 are applied to the thermal limits. Tables 10-2 and 10-3 are applicable to both GE14 and GNF2 fuel type per References 2 and 10.Page 18 of25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 TABLE 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTA < 55F (Asymmetric Feedwater Heating)(References 2 and 10)Core Thermal Power (% of rated)EOOS Combination Core Flow 0 25 1 <30 1>30 1 40 1 55 65 1 85 1 100 (% of rated)LHGRFAC(P) Multiplier <60 0.495 0.495 0.514 Base 0.720 0.726 0.740 0.784 0.921 0.960> 60 0.495 0.495 0.514<60 0.516 0.516 0.535 Base SLO 0.750 0.756 0.771 0.817 0.959 1.000>60 0.516 0.516 0.535 1 1< 60 0.495 0.495 0.514 RPTOOS 0.720 0.726 0.740 0.784 0.921 0.960> 60 0.495 0.495 0.514< 60 0.516 0.5 16 0.535 RPTOOS SLO 0.750 0.756 0.771 0.817 0.959 1.000>60 0.516 0.516 0.535< 60 0.404 0.404 0.463 TBVOOS 0.614 0.629 0.685 0.784 0.893 0.960> 60 0.397 0.397 0.407< 60 0.421 0.421 0.482 TBVOOS SLO 0.640 0.655 0.714 0.817 0.930 1.000> 60 0.414 0.414 0.424 TABLE 10-3 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTA < 55F (Asymmetric Feedwater Heating)(References 2 and 10)Core Flow (% of rated)EOOS Combination 0 30 33.60 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.486 0.678 0.701 0.934 0.960 0.960 Single Loop 0.506 0.706 0.730 0.730 0.730 0.730 Page 19 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 MCPR LIMITS The OLMCPR during asymmetric feedwater temperature operation with a feedwater temperature difference greater then 30 'F are provided in Table 10-4. The ARTS-based power-dependent MCPR limits for use during AFTO conditions are provided in Table 10-5. The flow-dependent MCPR limits for AFTO are provided in Tables 10-6 and 10-7. The power and flow-dependent OLMCPR curves were obtained from Reference 2 and were adjusted with a 2%penalty for feedwater temperature difference greater then 30 'F as displayed in Table 10-1 as per Reference

10. No MCPR penalties are required for asymmetric temperature differentials less than or equal to 30 'F. Additionally, no MCPR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.

Because the station still requires physical implementation of the AFTO SLO curves non AFTO SLO values have been provided in the curves identified as AFTO SLO condition. Tables 10-4, 10-5, 10-6, and 10-7 are applicable to both GE14 and GNF2 fuel type per References 2 and 10.TABLE 10-4 AFTO Operating Limit Minimum Critical Power Ratio-All Fuel 30F < FWT DELTA < 55F (Asymmetric Feedwater Heating)(References 2 and 10)SCRAM Cycle Exposure Time < EOR- 3621 > EOR -3621 EOOS Combination Option(l) MWd/ST MWd/ST B 1.44 1.44 BASE A 1.44 1.44 B 1.44 1.44 BASE SLO A 1.44 1.44 B 1.44 1.44 TBVOOS A 1.44 1.46 B 1.44 1.44 TBVOOS SLO A 1.44 1.46 B 1.44 1.44 RPTOOS A 1.54 1.56 B 1.44 1.44 RPTOOS SLO A 1.54 1.56 (1) When Tau does not equal 0 or 1, use linear interpolation. Page 20 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 TABLE 10-5 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 30F < FWT DELTA < 55F (Asymmetric Feedwater Heating)(References 2 and 10)Core Core Thermal Power (% of rated)EOOS Combination Flow(% 0 25 1 <30 >30 1 40 55 65 1 85 100 of rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp< 60 2.57 2.57 2.48 Base 1.352 1.352 1.317 1.131 1.082 1.000> 60 2.84 2.84 2.62< 60 2.55 2.55 2.46 Base SLO 1.352 1.352 1.317 1.131 1.082 1.000> 60 2.81 2.81 2.60< 60 2.57 2.57 2.48 RPTOOS 1.352 1.352 1.317 1.131 1.082 1.000> 60 2.84 2.84 2.62< 60 2.55 2.55 2.46 RPTOOS SLO 1.352 1.352 1.317 1.131 1.082 1.000> 60 2.81 2.81 2.60 ____< 60 3.35 3.35 2.84 TBVOOS 1.614 1.479 1.373 1.155 1.082 1.000> 60 3.86 3.86 3.37<60 3.31 3.31 2.81 TBVOOS SLO 1.614 1.479 1.373 1.155 1.082 1.000> 60 3.81 3.81 3.33 TABLE 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 30F < FWT DELTA < 55F (BOC to EOC)(Asymmetric Feedwater Heating)(References 2 and 10)Flow MCPR(F)(% rated) Limit 0.0 1.735 30.0 1.561 79.0 1.275 110.0 1.275 TABLE 10-7 AFTO SLO Flow Dependent MCPR Limits MCPR(F) 30F < FWT DELTA < 55F (BOC to EOC)(Asymmetric Feedwater Heating)(References 2 and 10)Flow MCPR(F)(% rated) Limit 0.0 1.731 30.0 1.560 79.0 1.280 110.0 1.280 Page 21 of25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 MAPLHGR LIMITS An appropriate penalty must be applied to MAPLHGR limits under asymmetric feedwater temperature operation (AFTO) for varying temperature differentials as displayed in Table 10-1 as per Reference

10. No MAPLHGR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.

Because the station still requires physical implementation of the AFTO SLO curves non AFTO SLO values have been provided in the curves identified as AFTO SLO condition. Tables 10-8 and 10-9 are applicable to both GE14 and GNF2 fuel type per References 2 and 10.TABLE 10-8 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)Valid For All Conditions Except SLO (References 2 and 10)AFTO Reduction Factor 20F < FWT DELTA < 55F 0.960 TABLE 10-9 AFTO MAPLHGR Single Loop Operation (SLO) Multiplier (Asymmetric Feedwater Heating)(References 2 and 10)SLO AFTO Multiplier 20F < FWT DELTA < 55F 1 0.730 Page 22 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 11.0 MODES OF OPERATION COLR Peach Bottom 3 Rev. 7 TABLE 11-1 Modes of Operation (Reference 2 and 4)EOOS Options Operating Region t 1)Base, Option A or B Yes_(2,3)Base SLO, Option A or B Yes(2,3)TBVOOS, Option A or B Yes_(2,3)TBVOOS SLO, Option A or B Yes_(2,3)RPTOOS, Option A or B Yes_(2,3)RPTOOS SLO, Option A or B Yes_(2,3)TBVOOS and RPTOOS, Option A or B No TBVOOS and RPTOOS SLO, Option A or B No Operating Region refers to operation on the Power to Flow map with or without FFWTR or AFTO.PLUOOS operation in this region controlled via station procedures. PROOS operation in this region controlled via station procedures. Notes: 1.2.3.12.0 METHODOLOGY The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document: 1. "General Electric Standard Application for Reactor Fuel", NEDE-240 11-P-A- 19, May 2012 and U.S. Supplement NEDE-2401 1-P-A-19-US, May 2012.2. "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Units 2 and 3", NEDC-32162P, Revision 2, March 1995.3. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology And Reload Applications", NEDO-32465-A, Revision 0, August 1996.

13.0 REFERENCES

1. "Technical Specifications for Peach Bottom Atomic Power Station Unit 3", Docket No. 50-278, Appendix A to License No. DPR-56.2. "Supplemental Reload Licensing Report for Peach Bottom Unit 3, Reload 19, Cycle 20", GNF Document No.0000-0153-3109-SRLR, Revision 0, July 2013.3. Not Used 4. General Electric Hitachi Document 0000-0163-9169-RO "Evaluation of Power Load Unbalance Out-of-Service and Pressure Regulator Out-of-Service between 90% and 100% RTP for Peach Bottom Units 2 and 3", Rev. 0 dated 7/29/2013.

Page 23 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 5. General Electric Document NEDC-32707P Supplement 1, "Peach Bottom Atomic Power Station Evaluation for Extended Final Feedwater Temperature Reduction of 900 F", May 1998.6. Not Used 7. PECO Calculation PE-0173, "Determination of Total Time Required to Initiate the Trip Signal to the EOC-RPT Circuit Breakers Trip Coils and to Complete the Recirculation Pump Trip", Rev. 1 dated 12/22/98.8. Not Used 9. PECO Calculation PE-025 1, Revision 1, "Power Range Neutron Monitoring System Setpoint Calculations, Peach Bottom Atomic Power Station Units 2 and 3" dated 10/3/00 including margin revision lE dated 08/25/11.10. General Electric Document GE-NE-0000-0057-0522-RO, "Evaluation Report for Peach Bottom Asymmetric Feedwater Temperature Operation Fuel Thermal Limits Evaluation Update", Revision 0, January 2007.11. Global Nuclear Fuels Document 0000-0153-3109-FBIR-NP, "Fuel Bundle Information Report for Peach Bottom Unit 3 Reload 19 Cycle 20", Revision 0, July 2013.12. Not Used 13. General Electric Document NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications", August 1996.14. Exelon TODI ENSAF ID# ES1300004, Rev. 0, Final Resolved OPL-3 Parameters for Peach Bottom Unit 3 Cycle 20, April 8, 2013.Page 24 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted In Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 Appendix A Page 25 of 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Peach Bottom 3 Rev. 7 Appendix A, Page 1 of 34 Global Nuclear Fuel Global Nuclear Fuel A JointVenture of GE.Thshiba; & Hitachi:.0000-0153-3 109-FBIR-NP Revision 0 July 2013 Non-Proprietary Information -Class I (Public)Fuel Bundle Information Report for Peach Bottom Unit 3 Reload 19 Cycle 20 Copyright 2013 Global Nuclear Fuel-Americas, LLC All Rights Reserved Exelon Generation -Nuclear Fuels Core Operating Limits Report COLR Peach Bottom 3 Rev. 7 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A, Page 2 of 34 Peach Bottom Unit 3 Non-Proprietary Information 0000-0153-3109-FBIR-NP Reload 19 -Class I (Public) Revision 0 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel -Americas, LLC (GNF-A) solely for use by Exelon Corporation ("Recipient") in support of the operating license for Peach Bottom Unit 3 (the "Nuclear Plant"). The information contained in this report (the "Information") is believed by GNF-A to be an accurate and true representation of the facts known by, obtained by or provided to GNF-A at the time this report was prepared.The only undertakings of GNF-A respecting the Information are contained in the contract between Recipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") and nothing contained in this document shall be construed as amending or modifying the Fuel Contract. The use 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 any representation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness of the Information or that such unauthorized use may not infringe privately owned rights, nor (b) assumes any responsibility for liability or damage of any kind which may result from such use of such information. Information Notice This is a non-proprietary version of the document 0000-0153-3109-FBIR-P, Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here [[ I].Page 2 Exelon Generation -Nuclear Fuels Core Operating Limits Report COLR Peach Bottom 3 Rev. 7 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A, Page 3 of 34 Peach Bottom Unit 3 Non-Proprietary Information 0000-0153-3109-FBIR-NP Reload 19 -Class I (Public) Revision 0 1. Introduction and Summary This report, which supplements the Supplemental Reload Licensing Report, contains thermal-mechanical linear heat generation rate (LHGR) limits for the GNF-A fuel designs to be loaded into Peach Bottom Unit 3 for Cycle 20. These LHGR limits are obtained from thermal-mechanical considerations only.Approved GNF-A calculation models documented in Reference 1 were used in performing this analysis.LHGR limits as a function of exposure for each bundle of the core design are given in Appendix A. The LHGR values provided in Appendix A provide upper and lower exposure dependent LHGR boundaries which envelope the actual gadolinia dependent LHGR limits. The LHGRs reported have been rounded to two 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 fuel bundles included in this appendix. These bundles have been approved for use under the fuel licensing acceptance criteria of Reference 1.Page 3 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 4 of 34 0000-01 53-31 09-FBIR-NP Revision 0 2. References

1. General Electric Standard Application for Reactor Fuel, NEDE-240 11-P-A-19, May 2012; and the U.S. Supplement, NEDE-2401 l-P-A-19-US, May 2012.Page 4 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 5 of 34 0000-0153-3109-FBIR-NP Revision 0 Appendix A UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1 ODNAB416-15GZ-I OOT- 150-T6-2908 (GE 14C)Bundle Number: 2908 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft I[[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 design[[]]Page 5 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 6 of 34 0000-0153-3109-FBIR-NP Revision 0 UO=IGd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1 ODNAB414-14GZ-IOOT-1 50-T6-3200 (GEl 4C)Bundle Number: 3200 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 2 GWd/MT (GWd/ST) kW/ft I[[2 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[1 1].Page 6 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 7 of 34 0000-0153-3109-FBIR-NP Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1 ODNAB417-15GZ-lOOT- 150-T6-3199 (GE 14C)Bundle Number: 3199 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 3 GWd/MT (GWd/ST) kW/ft Er 3 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Er 1].Page 7 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 8 of 34 0000-0153-3109-FBIR-NP Revision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P1ODNAB408-15GZ-lOOT- 150-T6-3213 (GE 14C)Bundle Number: 3213 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft I[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 4 GWd/MT (GWd/ST) kW/ft 4 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[1 1].Page 8 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 9 of 34 0000-0153-3109-FBIR-NP Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P I ODNAB420-13GZ-1 OOT- 1 50-T6-3198 (GE 14C)Bundle Number: 3198 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 5 GWd/MT (GWd/ST) kW/ft[[I____________________ 5 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[[ ]]Page 9 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 10 of 34 0000-0153-3109-FBIR-NP Revision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P10DG2B395-14GZ-100T2-150-T6-3991 (GNF2)Bundle Number: 3991 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 6 GWd/MT (GWd/ST) kW/ft 6 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Er 1].Page 10 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 11 of 34 0000-0153-3109-FBIR-NP Revision 0 Reload 19 -Class I (Public) Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1 ODNAB403-15GZ-IOOT- 150-T6-3003 (GE 14C)Bundle Number: 3003 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 7 GWd/MT (GWd/ST) kW/ft[[___________________1 7 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[[ 1].Page I 1 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 12 of 34 0000-0153-31 09-FBIR-NP Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P1ODG2B399-13GZ-10OT2-150-T6-3993 (GNF2)Bundle Number: 3993 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 8 GWd/MT (GWd/ST) kW/ft[[I 8 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[1 1].Page 12 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 13 of 34 0000-0153-3109-FBIR-NP Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P10DG2B390-4G8.0/8G7.0/2G6.0-100T2-150-T6-3992 (GNF2)Bundle Number: 3992 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 9 GWd/MT (GWd/ST) kW/ft 9 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design 1[ 1].Page 13 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 14 of 34 0000-0153-3109-FBIR-NP Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10DG2B404-13GZ-I 00T2-150-T6-3994 (GNF2)Bundle Number: 3994 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit '0 GWd/MT (GWd/ST) kW/ft Er[[__________________ 10 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Er ].Page 14 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 15 of 34 0000-0153-3109-FBIR-NP Revision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 1 ODG2B400-13GZ-1 00T2-150-T6-4232 (GNF2)Bundle Number: 4232 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft[[I Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 1 1 GWd/MT (GWd/ST) kW/ft[E____________________ Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[[]]Page 15 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 16 of 34 0000-0153-3109-FBIR-NP Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P10DG2B393-4G8.0/8G7.0/2G6.0-100T2-150-T6-4233 (GNF2)Bundle Number: 4233 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 1 2 GWd/MT (GWd/ST) kW/ft Er 12 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[[ 1].Page 16 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 17 of 34 0000-0153-3109-FBIR-NP Revision 0 Reload 19 -Class I (Public) Revision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P10DG2B393-15GZ-100T2-150-T6-4235 (GNF2)Bundle Number: 4235 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit'3 GWd/MT (GWd/ST) kW/ft[[I___________________ 13 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design[[ I].Page 17 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 18 of 34 0000-0153-3109-FBIR-NP Revision 0 UO 2 1Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10DG2B403-8G7.0/4G6.0-100T2-150-T6-4236 (GNF2)Bundle Number: 4236 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft[[Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit '4 GWd/MT (GWd/ST) kW/ft E[14 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Er 1].Page 18 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 19 of 34 0000-0153-31 09-FBIR-NP Revision 0 Appendix B Fuel Bundle Information Table B-I Bundle Specific Information Weight Weight Max Exposure Fuel Bundle Enrichment of Wih Mat at Max kI Bundle Number (wt% U-235) of U (g of U k 0 at GWd/MT (kg) (kg) 20oc 15 G~ /M (GWd/ST)GE14-P1ODNAB416-15GZ-1OOT-150-T6-2908 (GE14C)GE14-P10DNAB414-14GZ-100T- 150-T6-3200 (GE 14C)GE14-PlODNAB417-15GZ-10OT-150-T6-3199 (GE14C)GE14-P10DNAB408-15GZ-3213 1OOT-150-T6-3213 (GE14C)GE 14-P1ODNAB420-13GZ-100T-150-T6-3198 (GE14C)GNF2-P10DG2B395-14GZ-100T2-150-T6-3991 (GNF2)GE 14-P 1ODNAB403-15GZ-100T-150-T6-3003 (GE14C)GNF2-P 10DG2B399-13GZ-100T2-150-T6-3993 (GNF2)GNF2-P 10DG2B390-4G8.0/8G7.0/2G6.0-100T2-150-3992 T6-3992 (GNF2)GNF2-P 10DG2B404-13GZ-100T2-150-T6-3994 (GNF2)GNF2-Pl0DG2B400-13GZ-100T2-150-T6-4232 (GNF2)GNF2-P10DG2B393-4G8.0/8G7.0/2G6.0-100T2-150-4233 T6-4233 (GNF2) I"5 Maximum lattice k. for the most reactive uncontrolled state plus a [[]] adder for uncertainties. Page 19 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 20 of 34 0000-0153-3109-FBIR-NP Revision 0 Fuel Bundle Enrichment Weight Weight Max Exposure of U0 2 of U Ik at at Max k, Bundle Number (wt% U-235) (kg) (kg) 200C 16 GWd/MT (GWd/ST)GNF2-P 10DG2B393-15GZ-100T2-150-T6-4235 (GNF2) [[GNF2-P10DG2B403-8G7.0/4G6.0-1 00T2-150-T6-4236 (GNF2)16 Maximum lattice k. for the most reactive uncontrolled state plus a [[]] adder for uncertainties. Page 20 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 21 of 34 0000-0153-31 09-FBIR-NP Revision 0 Figure B-1 Enrichment and Gadolinium Distribution for EDB No. 2908 Fuel Bundle GE14-P1ODNAB416-15GZ-100T-150-T6-2908 (GE14C)Page 21 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 22 of 34 0000-0153-3109-FBIR-NP Revision 0[1 Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 3200 Fuel Bundle GE14-PlODNAB414-14GZ-10OT-150-T6-3200 (GE14C)Page 22 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 23 of 34 0000-0153-3109-FBIR-NP Revision 0[[Figure B-3 Enrichment and Gadolinium Distribution for EDB No. 3199 Fuel Bundle GE14-PIODNAB417-15GZ-100T-150-T6-3199 (GE14C)Page 23 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 24 of 34 0000-0153-3109-FBIR-NP Revision 0[[]]Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 3213 Fuel Bundle GE14-PIODNAB408-15GZ-100T-150-T6-3213 (GE14C)Page 24 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 25 of 34 0000-0 15 3-31 09-FBIR-NP Revision 0 1]Figure B-5 Enrichment and Gadolinium Distribution for EDB No. 3198 Fuel Bundle GE14-P1ODNAB420-13GZ-100T-150-T6-3198 (GE14C)Page 25 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 26 of 34 0000-0153-3109-FBIR-NP Revision 0 Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 3991 Fuel Bundle GNF2-PIODG2B395-14GZ-100T2-150-T6-3991 (GNF2)Page 26 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 27 of 34 0000-0153-3109-FBIR-NP Revision 0 Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 3003 Fuel Bundle GE14-P1ODNAB403-15GZ-100T-150-T6-3003 (GE14C)Page 27 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 28 of 34 0000-0153-3109-FBIR-NP Revision 0[[Figure B-8 Enrichment and Gadolinium Distribution for EDB No. 3993 Fuel Bundle GNF2-P10DG2B399-13GZ-100T2-150-T6-3993 (GNF2)Page 28 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 29 of 34 0000-0153-3 109-FBIR-NP Revision 0 rr Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 3992 Fuel Bundle GNF2-PlODG2B390-4G8.0/8G7.0/2G6.0-100T2-150-T6-3992 (GNF2)Page 29 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 30 of 34 0000-0153-3109-FBIR-NP Revision 0 1[Figure B-10 Enrichment and Gadolinium Distribution for EDB No. 3994 Fuel Bundle GNF2-PlODG2B404-13GZ-100T2-150-T6-3994 (GNF2)Page 30 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 31 of 34 0000-0153-3109-FBIR-NP Revision 0[[1]Figure B-11 Enrichment and Gadolinium Distribution for EDB No. 4232 Fuel Bundle GNF2-PlODG2B400-13GZ-10OT2-150-T6-4232 (GNF2)Page 31 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 32 of 34 0000-0153-3109-FBIR-NP Revision 0 Figure B-12 Enrichment and Gadolinium Distribution for EDB No. 4233 Fuel Bundle GNF2-PIODG2B393-4G8.0/8G7.0/2G6.0-10OT2-150-T6-4233 (GNF2)Page 32 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 33 of 34 0000-0153-3109-FBIR-NP Revision 0[[Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 4235 Fuel Bundle GNF2-P10DG2B393-15GZ-100T2-150-T6-4235 (GNF2)Page 33 Exelon Generation -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information Reload 19 -Class I (Public)COLR Peach Bottom 3 Rev. 7 Appendix A, Page 34 of 34 0000-0153-3109-FBIR-NP Revision 0 Reload 19 -Class I (Public)[[Figure B-14 Enrichment and Gadolinium Distribution for EDB No. 4236 Fuel Bundle GNF2-PIODG2B403-8G7.0/4G6.0-100T2-150-T6-4236 (GNF2)Page 34}}

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