ML12291A505

Core Operating Limits Report for Reload 19, Cycle 20, Revision 8

ML12291A505
Person / Time
Site:	Peach Bottom
Issue date:	09/25/2012
From:	Henry P Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML12291A505 (58)

Text

ATTACHMENT 2 Core Operating Limits Report for Reload 19, Cycle 20, Revision 8 Non-Proprietary Version

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 2 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table of Contents Page 1.0 Terms and Definitions 5 2.0 General Information 6 3.0 MAPLHGR Limits 7 4.0 MCPR Limits 8 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 24 12.0 Methodology 24 13.0 References 24 Appendix A 26

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 3 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure - GEl4 7 Table 3-2 MAPLHGR Versus Average Planar Exposure - GNF2 7 Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier - GE14 and GNF2 7 Table 4-1 Operating Limit Minimum Critical Power Ratio- GE14 9 Table 4-2 Operating Limit Minimum Critical Power Ratio- GNF2 10 Table 4-3 Power Dependent MCPR(P) Limit Adjustments and Multipliers 11 Table 4-4 Flow Dependent MCPR Limits MCPR(F) 11 Table 4-5 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 - GE14 30F < FWT DELTA < 55F 20 Table 10-5 AFTO Operating Limit Minimum Critical Power Ratio - GNF2 30F < FWT DELTA < 55F 21 Table 10-6 AFTO Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) 30F < FWT DELTA <55F 22

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 4 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 10-7 AFTO Flow Dependent MCPR Limits MCPR(F) 30F < FWT DELTA < 55F 22 Table 10-8 AFTO SLO Flow Dependent MCPR Limits MCPR(F) 30F < FWT DELTA <55F 22 Table 10-9 AFTO MAPLHGR Reduction Factor 23 Table 10-10 AFTO MAPLHGR Single Loop Operation (SLO) Multiplier 23 Table 11-1 Modes of Operation 24

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 5 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 1.0 Terms and Definitions AFTO Asymmetric Feedwater Temperature Operation ARTS APRM and RBM Technical Specification Analysis BASE Defines two (2) loop operation with at least seven turbine bypass valves in service and the reactor recirculation pump trip system in service.

BOC Beginning Of Cycle DTSP Rod Block Monitor Downscale Trip Setpoint EOC End of Cycle EOOS Equipment Out of Service. An analyzed option that assumes certain equipment to be non-operational EOR 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.

FFWTR Final Feedwater Temperature Reduction FWHO( )S Feedwater Heaters Out of Service FWT Feedwater Temperature HTSP Rod Block Monitor High Trip Setpoint ICF Increased Core Flow ITSP Rod Block Monitor Intermediate Trip Setpoint LHGR Linear Heat Generation Rate LHGRF AC(F) ARTS LHGR thermal limit flow dependent adjustments and multipliers LHGRF AC(P) ARTS LHGR thermal limit power dependent adjustments and multipliers LTSP Rod Block Monitor Low Trip Setpoint MAPL- IGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(]P) ARTS MCPR thermal limit power dependent adjustments and multipliers MCPR(]*F) ARTS MCPR thermal limit flow dependent adjustments and multipliers MELLL A Maximum Extended Load Line Limit Analysis OLMCT PR Operating Limit Minimum Critical Power Ratio OPRM PBDA Oscillation Power Range Monitor Period Based Detection Algorithm RPTOO 'S Recirculation Pump Trip Out of Service RWE Rod Withdrawal Error SLMCP *R Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation TBVOC )S Turbine Bypass Valves Out of Service

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 6 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 2.0 General Information This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 2 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:

• 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 90' F temperature reduction maintaining < 100% load line ( 40t and 5h 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 2 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.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 7 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 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 f MAPLHGR Limit (GWD/ST) (kW/ft) 0.0 [ 12.82 19.13 12.82 57.61 1 8.00 63.50 5.00 TABLE 3-2 MAPLHGR Versus Average Planar Exposure-GNF2 (Reference 2)

Average Planar Exposure MAPLHGR Limit (GWD/ST)I (kW/ft) 0.0 13.78 17.52 1 13.78 60.78 7.50 63.50 1 6.69 TABLE 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier - GE14 and GNF2 (Reference 2)

SLO Multiplier 0.73

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 8 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 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, 4-2, and 4-3. 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 OLIMCPR value if Tau is between 0.0 (Tau Option B) and 1.0 (Tau Option A).

Separate OLMCPR values are presented in Tables 4-1 and 4-2 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 4-3. Table 4-3 is valid for a maximum temperature reduction of 90 'F for FFWTR operation. The flow-dependent MCPR limits are provided in Tables 4-4 and 4-5. Table 4-4 is valid for dual loop operating conditions with symmetric feedwater temperature operation and Table 4-5 is valid for single loop operating conditions with symmetric feedwater temperature operation. The impact of AFTO on MCPR is addressed in Section 10. Tables 4-3, 4-4, and 4-5 are applicable to both GE14 and GNF2 fuel type.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 9 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 TABLE 4-1 Operating Limit Minimum Critical Power Ratio-GE14 (Reference 2)

SCRAM Cycle Exposure Time < EOR - 4773 > EOR - 4773 EOOS Combination Option() MWd/ST MWd/ST B 1.37(2) 1.37(3)

BASE A 1.37 1.43 B 1.38 1.39 BASE SLO(4 ) A 1.41 1.47 B 1.37(') 1.39 TBVOOS A 1.40 1.48 B 1.38 1.43 TBVOOS SLO (41 A 1.44 1.52 B 1.37(6) 1.39 RPTOOS A 1.52 1.56 B 1.39 1.43 RPTOOS SLO(4) A 1.56 1.60 (1) When Tau does not equal 0 or 1, use linear interpolation.

(2) Analyzed DLO Option B OLMCPR is 1.29 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.

(3) Analyzed DLO Option B OLMCPR is 1.35 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.

(4) For single-loop operation, the MCPR operating limit is 0.04 greater than the analyzed limiting two loop value. However a minimum value of 1.37 is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).

(5) Analyzed DLO Option B OLMCPR is 1.31 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.

(6) Analyzed DLO Option B OLMCPR is 1.35 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 10 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 TABLE 4-2 Operating Limit Minimum Critical Power Ratio- GNF2 (Reference 2)

SCRAM Cycle Exposure Time < EOR - 4773, > EOR- 4773 EOOS Combination Option(t ) MWd/ST MWd/ST B 1.37(2) 1.37(3)

BASE A 1.37 1.43 B 1.44 1.44 BASE SLO(4) A 1.44 1.47 B 1.37(5) 1.39 TBVOOS A 1.40 1.48 B 1.44 1.44 TBVOOS SLO (4) A 1.44 1.52 B 1.37(6) 1.39 RPTOOS A 1.52 1.56 B 1.44 1.44 RPTOOS SLO(4) A 1.56 1.60 (1)

(i) When Tau does not equal 0 or 1, use linear interpolation.

(2) Analyzed DLO Option B OLMCPR is 1.29 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.

(3) Analyzed DLO Option B OLMCPR is 1.35 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.

(4) For single-loop operation, the MCPR operating limit is 0.04 greater than the analyzed limiting two loop value. 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).

(5) Analyzed DLO Option B OLMCPR is 1.31 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.

(6) Analyzed DLO Option B OLMCPR is 1.35 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 11 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 TABLE 4-3 Power Dependent MCPR(P) Limit Adjustments And Multipliers (Symmetric Feedwater Heating)

(Reference 2)

Core Core Thermal Power (% of rated)

EOOS Combination Flow (% 0 I 25 1: 30 >30 40 55 65 85 100 of rated) Operating Limit MCPR EOperating Limit MCPR Multiplier, Kp Base <60 2.52 2.52 2.43 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.78 2.78 2.57

< 60 2.56 2.56 2.47 Base SLO 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.82 2.82 2.61

< 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

< 60 2.56 2.56 2.47 RPTOOS SLO 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.82 2.82 2.61

< 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 3.32 3.32 2.82 TBVOOS SLO 1.614 1.479 1.373 1.155 1.082 1.000

> 60 3.82 3.82 3.34 TABLE 4-4 Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating)

(Reference 2)

Core Flow MCPR(F)

(% rated) Limit 0.0 1.701 79.0 1.250 110.0 1.250 TABLE 4-5 SLO Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating)

(Reference 2)

Core Flow MCPR(F)

(% rated) Limit 0.0 1.741 79.0 1.290 110.0 1.290

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 12 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 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 5-1 and 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 900 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 GEl4 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 GE 14 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

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 13 of 57 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)

- -Core Thermal Power (% of rated)

EOOSCominaionCore Flow ___________________________

EOOSCombination of rated) 0 25 1 <30 1_>30 F-40 55 65 85 1 100 LHGRFAC(P) Multiplier Base <60 0.516 0.516 0.535 0.750 0.756 0.771 0.817 0.959 1.000

>60 0.516 0.516 0.535 Base SLO <60 0.516 0.516 0.535 0.750 0.756 0.771 0.817 0.959 1.000

>60 0.516 0.516 0.535 RPTOOS 0.516 0.516 0.535 760 0.756 0.771 0.817 0.959 1.000

>60 0.516 0.516 0.535 RPTOOS SLO *60 0.516 0.516 0.535 0.750 0.756 0.771 0.817 0.959 1.000

>60 0.516 0.516 0.535 TBVOOS <60 0.421 0.421 0.482 0.640 0.655 0.714 0.817 0.930 1.000

> 60 0.414 0.414 0.424

< 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 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)

(Symmetric Feedwater Heating)

(Reference 2)

Core Flow (% of rated)

EOOS Combination 0 30 33.6 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

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 14 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 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 Limit(') Allowable Value(t) MCPR Limit 123.0% 121.2% < 1.70 (2)

LTSP

< 1.40 (3)

ITSP 118.0% 116.2% < 1.70(2)

< 1.40 (3)

HTSP 113.2% 111.4% < 1.70 (2)

< 1.40 (3)

N/A N/A < 1.70 (2)

INOP < 1.40 (3)

(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).

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 15 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 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 full flow 0.30 sec (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

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 16 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 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. 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.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 17 of 57 Non-Proprietary Information Submitted in Accordance with 10CFR 2.390 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-234 through 237 (Unit-2).

TABLE 9-1 OPRM PBDA Trip Settings (Valid for All Conditions)

(Reference 2)

PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting I1.11 14 TABLE 9-2 OPRM PBDA Trip Settings - SLO(1)

(Valid For SLO Conditions Only)

(Reference 2)

PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting

.1.18 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.

Extlon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 18 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 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 P2C20 COLR Rev. 8 is the first COLR 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 AFrO 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 GE 14 and GNF2 fuel type per References 2 and 10.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 19 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 TABLE 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTA < 55F (Asymmetric Feedwater Heating)

(References 2 and 10)

Core Flow Core Thermal Power (% of rated)

EOOS Combination (%of rated) 0 25 <30 1>30 140 55 165 185 95 100 LHGRFAC(P) Multiplier Base < 60 0.495 0.495 0.514 0.720 0.726 0.740 0.784 0.921 0.947 0.960

> 60 0.495 0.495 0.514 Base SLO 0.516 0.516 0.535 .60 0.756 0.771 0.817 0.959 0.986 1.000

>60 0.516 0.516 0.535

< 60 0.495 0.495 0.514 RPTOOS 0.720 0.726 0.740 0.784 0.921 0.947 0.960

> 60 0.495 0.495 0.5 14 RPTOOS SLO <60 0.516 0.516 0.535 0.750 0.756 0.771 0.817 0.959 0.986 1.000

>60 0.516 0.516 0.535

< 60 0.404 0.404 0.463 TBVOOS - 60 0 0.614 0.629 0.685 0.784 0.893 0.938 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 0.977 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 irated)

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

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 20 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 MCPR LIMITS The OLMCPR during asymmetric feedwater temperature operation with a feedwater temperature difference greater then 30 'F are provided in Tables 10-4 and 10-5. The ARTS-based power-dependent MCPR limits for use during AFTO conditions are provided in Table 10-6. The flow-dependent MCPR limits for AFTO are provided in Tables 10-7 and 10-8. 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 10-6, 10-7, and 10-8 are applicable to both GE14 and GNF2 fuel type per References 2 and 10.

TABLE 10-4 AFTO Operating Limit Minimum Critical Power Ratio-GE14 30F < FWT DELTA < 55F (Asymmetric Feedwater Heating)

(References 2 and 10)

SCRAM Cycle ]Exposure Time < EOR - 4773; > EOR- 4773 EOOS Combination Option(" MWd/ST MWd/ST B 1.40 1.40 BASE A 1.40 1.46 B 1.38 1.39 BASE SLO A 1.41 1.47 B 1.40 1.42 TBVOOS A 1.43 1.51 B 1.38 1.43 TBVOOS SLO A 1.44 1.52 B 1.40 1.42 RPTOOS A 1.55 1.59 B 1.39 1.43 RPTOOS SLO A 1.56 1.60 (1) When Tau does not equal 0 or 1, use linear interpolation.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 21 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 TABLE 10-5 AFTO Operating Limit Minimum Critical Power Ratio -GNF2 30F < FWT DELTA < 55F (Asymmetric Feedwater Heating)

(Reference 2 and 10)

SCRAM Cycle Exposure Time < EOR - 4773 > EOR - 4773 EOOS Combination Option(t) MWd/ST MWd/ST B 1.40 1.40 BASE A 1.40 1.46 B 1.44 1.44 BASE SLO A 1.44 1.47 B 1.40 1.42 TBVOOS A 1.43 1.51 B 1.44 1.44 TBVOOS SLO A 1.44 1.52 B 1.40 1.42 RPTOOS A 1.55 1.59 B 1.44 1.44 RPTOOS SLO A 1.56 1.60 (1) When Tau does not equal 0 or 1, use linear interpolation.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 22 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 TABLE 10-6 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 (% 0 125 <30 > 1 40 55 65 85 100 of rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp Base < 60 2.57 2.57 2.48 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.84 2.84 2.62

< 60 2.56 2.56 2.47 Base SLO 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.82 2.82 2.61

< 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 2.56 2.56 2.47 RPTOOS SLO 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.82 2.82 2.61

< 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 3.32 3.32 2.82 TBVOOS SLO 1.614 1.479 1.373 1.155 1.082 1.000

> 60 3.82 3.82 3.34 TABLE 10-7 AFTO Flow Dependent MCPR Limits MCPR(F) 30F < FWT DELTA < 55F (BOC to EOC)(Asymmetric Feedwater HBeating)

(References 2 and 10)

Flow MCPR(F)

(% rated) Limit 0.0 1.735 79.0 1.275 110.0 1.275 TABLE 10-8 AFTO SLO Flow Dependent MCPR Limits MCPR(F) 301F < FWT DELTA < 55F (BOC to EOC)(Asymmetric Feedwater Heating)

(References 2 and 10)

Flow MCPR(F)

(% rated) Limit 0.0 1.741 79.0 1.290 110.0 1.290

Exelon Nuclear- Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 23 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 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 10-9 and 10-10 are applicable to both GE14 and GNF2 fuel type per References 2 and 10.

TABLE 10-9 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)

Valid For All Conditions Except SLO (References 2 and 10)

AFTO Reduction Factor 20F < FWT DELTA < 55F 1 0.960 TABLE 10-10 AFrO MAPLHGR Single Loop Operation (SLO) Multiplier (Asymmetric Feedwater Heating)

(References 2 and 10)

SLO AFTO Multiplier 1 1 20F < FWT DELTA <55F 1 0.730

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 24 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 11.0 MODES OF OPERATION TABLE 11-1 Modes of Operation (Reference 2)

EOOS Options Operating Region)

Base, 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 Yes TBVOOS and RPTOOS, Option A or B No TBVOOS and RPTOOS SLO, Option A or B No 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-2401 I -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 2", Docket No. 50-277, Appendix A to License No. DPR-44.

2. "Supplemental Reload Licensing Report for Peach Bottom Unit 2, Reload 19, Cycle 20", GNF Document No.

0000-0139-5156-SRLR, Revision 0, August 2012.

3. General Electric Document "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.

(1) Operating Region refers to operation on the Power to Flow map with or without FFWTR or AFTO.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 25 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390

4. Not Used

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. General Electric Hitachi Document GEH-0000-0107-7348, "GNF2 Fuel Design Cycle-Independent Analyses For Exelon Peach Bottom Atomic Power Station Units 2 and 3", Revision 3, March 2012.

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 IE 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 0000-0139-5156-FBIR-NP, "Fuel Bundle Information Report for Peach Bottom Unit 2 Reload 19 Cycle 20", Revision 0, August 2012.

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# ES1200006, Rev. 0, Final Resolved OPL-3 Parameters for Peach Bottom Unit 2 Cycle 20, March 29, 2012.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 8 P2C20 Core Operating Limits Report Page 26 of 57 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Global Nuclear Fuel Global Nuclear Fuel A Joint Venture of GEToshiba, & Hitachi 0000-0139-5156-FBIR-NP Revision 0 August 2012 Non-ProprietaryInformation - Class I (Public)

Fuel Bundle Information Report for Peach Bottom Unit 2 Reload 19 Cycle 20 Copyright 2012 Global NuclearFuel - Americas, LLC All Rights Reserved COLR Page 27 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-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 2 (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 0000-0139-5156-FB[R-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 (( )).

Page 2 COLR Page 28 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-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 2 for Cycle 20. These LHGR limits are obtained from thermal-mechanical considerations only.

Approved GNF-A calculation models documented in Reference I 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 COLR Page 29 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Ndo-Proprietary Information Submitted in Accordance with 10CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0

2. References

1. General Electric StandardApplicationfor Reactor Fuel, NEDE-240 11-P-A-i19, May 2012; and the U.S. Supplement, NEDE-2401 1-P-A-19-US, May 2012.

Page 4 COLR Page 30 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-51 56-FBIR-NP Reload 19 Class I (Public) Revision 0 Appendix A UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P I 0DG2B406-12G6.0- 100T2-150-T6-3337 (GNF2)

Bundle Number: 3337 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft

((l Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((

Page 5 COLR Page 31 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-Pl 0DG2B393-15GZ- 100T2-150-T6-3334 (GNF2)

Bundle Number: 3334 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia 2

LHGR Limit GWd/MT (GWd/ST) kW/ft

((E 2 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((

]I].

Page 6 COLR Page 32 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB420-13 GZ- IOOT- 150-T6-3097 (GE 14C)

Bundle Number: 3097 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 3 GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 3 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 7 COLR Page 33 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-PI ODNAB416-15GZ- 1OOT- 150-T6-3098 (GE 14C)

Bundle Number: 3098 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 4 GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 4 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 8 COLR Page 34 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE14-P 1ODNAB416-15GZ- 1OOT- 150-T6-2911 (GE 14C)

Bundle Number: 2911 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia 5

LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 5 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 9 COLR Page 35 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance With 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE14-PI ODNAB411-15GZ- 1OOT- 150-T6-3099 (GE 14C)

Bundle Number: 3099 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 6 GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 6 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 10 COLR Page 36 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE14-PIODNAB409-15GZ-lOOT-150-T6-2913 (GE14C)

Bundle Number: 2913 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limiit 7 GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 7Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page II COLR Page 37 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P10DG2B388-6G8.0/6G7.0/2G6.0-100T2-150-T6-3336 (GNF2)

Bundle Number: 3336 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia 8

LHGR Limit GWd/MT (GWd/ST) kW/ft

(( _____________________

' Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((

Page 12 COLR Page 38 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-PI 0DG2B392-15GZ-100T2-150-T6-3335 (GNF2)

Bundle Number: 3335 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 9Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (( I].

Page 13 COLR Page 39 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P10DG2B392-15GZ-100T2-150-T6-3332 (GNF2)

Bundle Number: 3332 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit'o GWd/MT (GWd/ST) kW/ft

((I 10 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (( ]I].

Page 14 COLR Page 40 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10DG2B399- 11 G7.0/2G6.0- I00T2-150-T6-4130 (GNF2)

Bundle Number: 4130 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Er Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit" GWd/MT (GWd/ST) kW/ft Er

_________________________________ I))

" Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design I[

Page 15 COLR Page 41 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10DG2B397-14GZ- 100T2-150-T6-4128 (GNF2)

Bundle Number: 4128 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia 2

LHGR Limit '

GWd/MT (GWd/ST) kW/ft 12 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (( fl.

Page 16 COLR Page 42 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10DG2B403-12GZ- 100T2-150-T6-4129 (GNF2)

Bundle Number: 4129 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 13 GWd/MT (GWd/ST) kW/ft

((

13 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((

Page 17 COLR Page 43 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 Appendix B Fuel Bundle Information Table B-1 Bundle Specific Information Weight Weight Max Exposure Fuel Bundle Enrichment Of U0 2 Of U k. at at Max k.

Bundle Number (wt% U-235) (kg) (kg) 200C '4 GWd/MT (GWd/ST)

GNF2-P10DG2B406-12G6.0- 37 100T2-150-T6-3337 (GNF2)

GNF2-P 10DG2B393-15GZ-100T2-150-T6-3334 (GNF2)

GE 14-P 10DNAB420-13 GZ-100T-150-T6-3097 (GE14C)

GEl 4-PI0DNAB416-15GZ.-

100T-150-T6-3098 (GE14C)

GE14-P1ODNAB416-15GZ-IOOT-150-T6-2911 (GE14C)

GE14-P1ODNAB411-15GZ-100T-150-T6-3099 (GE14C)

GE 14-P 1ODNAB409-15GZ-IOOT-150-T6-2913 (GE14C)

GNF2-P10DG2B388-6G8.0/6G7.0/2G6.0-100T2-150- 3336 T6-3336 (GNF2)

GNF2-P 10DG2B392-15GZ-100T2-150-T6-3335 (GNF2)

GNF2-P 10DG2B392-15GZ.-

100T2-150-T6-3332 (GNF2)

GNF2-P10DG2B399-S11G7.0/2G6.0-100T2-150- 4130 T6-4130 (GNF2)

GNF2-P10DG2B397-14GZ-100T2-150-T6-4128 (GNF2)

GNF2-P 10DG2B403-12GZ-100T2-150-T6-4129 (GNF2) ]

14 Maximum lattice k~. for the most reactive uncontrolled state plus a (( )) adder for uncertainties.

Page 18 COLR Page 44 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0

((

1]

Figure B-1 Enrichment and Gadolinium Distribution for EDB No. 3337 Fuel Bundle GNF2-P1ODG2B406-12G6.0-100T2-150-T6-3337 (GNF2)

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Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 3334 Fuel Bundle GNF2-P10DG2B393-15GZ-100T2-150-T6-3334 (GNF2)

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Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0

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Figure B-3 Enrichment and Gadolinium Distributiion for EDB No. 3097 Fuel Bundle GE14-PIODNAB420-13GZ-100T-150-T6-3097 (GE14C)

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Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-51 56-FBIR-NP Reload 19 Class I (Public) Revision 0 Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 3098 Fuel Bundle GE14-P1ODNAB416-15GZ-100T-150-T6-3098 (GE14C)

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Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 Figure B-5 Enrichment and Gadolinium Distribution for EDB No. 2911 Fuel Bundle GE14-P1ODNAB416-15GZ-100T-150-T6-2911 (GE14C)

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Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 3099 Fuel Bundle GE14-PIODNAB411-15GZ-100T-15;0-T6-3099 (GE14C)

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Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 I((

Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 2913 Fuel Bundle GE14-P1ODNAB409-15GZ-100T-150-T6-2913 (GE14C)

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Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-51 56-FBIR-NP Reload 19 Class I (Public) Revision 0 Figure B-8 Enrichment and Gadolinium Distribution for EDB No. 3336 Fuel Bundle GNF2-P10DG2B388-6G8.0/6G7.0/2G6.0-100T2-150-T6-3336 (GNF2)

Page 26 COLR Page 52 of 57

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 3335 Fuel Bundle GNF2-P10DG2B392-15GZ-100T2-150-T6-3335 (GNF2)

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Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-01 39-5156-FBIR-NP Reload 19 Class I (Public) Revisinn 0

[1 Figure B-10 Enrichment and Gadolinium Distribution for EDB No. 3332 Fuel Bundle GNF2-P10DG2B392-15GZ-100T2-150-T6-3332 (GNF2)

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Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 Figure B-11 Enrichment and Gadolinium Distribution for EDB No. 4130 Fuel Bundle GNF2-PIODG2B399-11G7.0/2G6.0-100T2-150-T6-4130 (GNF2)

COLR Page 55 of 57 Page 29

Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-51 56-FBIR-NP Reload 19 Class I (Public) Revision 0

))1 Figure B-12 Enrichment and Gadolinium Distribution for EDB No. 4128 Fuel Bundle GNF2-P10DG2B397-14GZ-100T2-1sO-T6-4128 (GNF2)

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Exelon Nuclear - Nuclear Fuels P2C20 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 8 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Peach Bottom Unit 2 Non-Proprietary Information 0000-0139-5156-FBIR-NP Reload 19 Class I (Public) Revision 0 0

Revision Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 4129 Fuel Bundle GNF2-P1ODG2B403-12GZ-100T2-150-T6-4129 (GNF2)

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