ML102790129

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To Core Operating Limits Report Reload 18, Cycle 19, Attachment 2, Non-Proprietary Version
ML102790129
Person / Time
Site: Peach Bottom 
Issue date: 09/28/2010
From: Becknell G
Exelon Generation Co, Exelon Nuclear
To:
Office of Nuclear Reactor Regulation
References
Download: ML102790129 (65)
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ATTACHMENT 2 Core Operating Limits Report for Reload 18, Cycle 19, Revision 6 Non-Proprietary Version

Fielos Nudes - Nudesr Fuel.

P2C19 Caor Opeating Limits Repoat Non-Proprietary Inftmaatmo Submitted in Accordance with 10 CFR 2.390 COLR PEACH BO'rrOM 2 Rev. 6 Page 1 of 64 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 2 RELOAD 18, CYCLE 19 (This is a Complete Re-write)

Prepared By:

Date:

G. Becknell Reviewed By:.

6 '~ i Reactor Engineering Reviewed By:

Engineering Safety Analysis Date:

2/78/0 Date: q/1/10 Date:

/2 Independent Review By:

M.

Holmes M. Holmes Approved By:

J. J. Tusar Date:

!?/Z 7/0 Date: __/'_0/_

Reviewer.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 6 P2C 19 Core Operating Limits Report Page 2 of 64 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 26 12.0 Methodology 26 13.0 References 26 Appendix A 28

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 6 P2C19 Core Operating Limits Report Page 3 of 64 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure - GE14 7

Table 3-2 MAPLHGR Versus Average Planar Exposure - GNF2 7

Table 3-3 MAPLHGR Single Loop Operation (SLO) Reduction Factor - GE14 and GNF2 7

Table 4-1 Operating Limit Minimum Critical Power Ratio - GE 14 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 < 30F 19 Table 10-3 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 30F < FWT DELTA_< 40F 19 Table 10-4 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 40F < FWT DELTA < 55F 20 Table 10-5 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTA _ 30F 21 Table 10-6 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 30F < FWT DELTA <40F 21 Table 10-7 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 40F < FWT DELTA _ 55F 21

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTT(

P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 10-8 AFTO Operating Limit Minimum Critical Power Ratio - GE14 > 30F FWT DELTA Table 10-9 AFTO Operating Limit Minimum Critical Power Ratio - GNF2 > 30F FWT DELTA Table 10-10 AFTO Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) > 30F FWT DELTA Table 10-11 AFTO Flow Dependent MCPR Limits MCPR(F) > 30F FWT DELTA Table 10-12 AFTO SLO Flow Dependent MCPR Limits MCPR(F) > 30F FWT DELTA Table 10-13 AFTO MAPLHGR Reduction Factor Table 10-14 AFTO MAPLHGR Single Loop Operation (SLO) Reduction Factor Table 11-1 Modes of Operation

)M 2 Rev. 6 Page 4 of 64 22 23 24 24 24 25 25 26

Exelon Nuclear - Nuclear Fuels P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 1.0 Terms and Definitions COLR PEACH BOTTOM 2 Rev. 6 Page 5 of 64 AFTO ARTS BASE BOC DTSP EOOS EOR FFWTR FWHOOS FWT HTSP ICF ITSP LHGR LHGRFAC(F)

LHGRFAC(P)

LTSP MAPLHGR MCPR MCPR(P)

MCPR(F)

MELLLA OLMCPR OPRM PBDA RPTOOS SLMCPR SLO TBVOOS 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 Rod Block Monitor Downscale Trip Setpoint 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 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 ARTS LHGR thermal limit flow dependent adjustments and multipliers ARTS LHGR thermal limit power dependent adjustments and multipliers Rod Block Monitor Low Trip Setpoint Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio ARTS MCPR thermal limit power dependent adjustments and multipliers ARTS MCPR thermal limit flow dependent adjustments and multipliers Maximum Extended Load Line Limit Analysis Operating Limit Minimum Critical Power Ratio Oscillation Power Range Monitor Period Based Detection Algorithm Recirculation Pump Trip Out of Service Safety Limit Minimum Critical Power Ratio Single Loop Operation Turbine Bypass Valves Out of Service

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 6 P2C19 Core Operating Limits Report Page 6 of 64 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 19 (RELOAD 18):

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 82.9% 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 (4 th and 5 th 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 I 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 19.

The "BASE" thermal limit values shown in tables are for normal two loop operation with at least seven turbine bypass valves operable and the reactor recirculation pump trip system operable.

Exelon Nuclear - Nuclear Fuels P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 7 of 64 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) Reduction Factor - GE14 and GNF2 (Reference 2)

SLO Reduction Factor j 0.73

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 6 P2C 19 Core Operating Limits Report Page 8 of 64 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-land 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 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 GEl4 and GNF2 fuel type.

Exelon Nuclear - Nuclear Fuels P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.3 90 COLR PEACH BOTTOM 2 Rev. 6 Page 9 of 64 TABLE 4-1 Operating Limit Minimum Critical Power Ratio-GE14 (Reference 2)

SCRAM Cycle Exposure Time

< EOR - 3400

> EOR - 3400 EOOS Combination Option(")

MWd/ST MWd/ST B

1.48(2) 1.48(')

BASE A

1.48 4) 1.48()

B 1.48 1.48 BASE SLO(6)

A 1.48 1.48 B

1.48(7) 1.48(8)

TBVOOS A

1.48(9) 1.50 B

1.48 1.51 TBVOOS SLO (6)

A 1.48 1.54 B

1.48(0) 1.48 RPTOOS A

1.51 1.65 B

1.48 1.52 RPTOOS SLO(6)

A 1.55 1.69 (1) When Tau does not equal 0 or 1, use linear interpolation.

(2)

Analyzed DLO Option B OLMCPR is 1.35 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

(3)

Analyzed DLO Option B OLMCPR is 1.41 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

(4) Analyzed DLO Option A OLMCPR is 1.38 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

(5)

Analyzed DLO Option A OLMCPR is 1.44 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

(6)

For single-loop operation, the MCPR operating limit is 0.04 greater than the analyzed two loop value with a minimum value of 1.48 to obtain a corresponding DLO OPRM amplitude setpoint of 1.13.

(7)

Analyzed DLO Option B OLMCPR is 1.41 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

(8)

Analyzed DLO Option B OLMCPR is 1.47 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

(9)

Analyzed DLO Option A OLMCPR is 1.44.per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

(10) Analyzed DLO Option B OLMCPR is 1.40 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

Exelon Nuclear - Nuclear Fuels P2CI 9 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 10 of 64 TABLE 4-2 Operating Limit Minimum Critical Power Ratio-GNF2 (Reference 2)

SCRAM Cycle Exposure Time

< EOR - 3400

> EOR - 3400 EOOS Combination Option(")

MWd/ST MWd/ST B

1.48(2) 1.48 BASE A

1.48(3) 1.53 B

1.48 1.52 BASE SLO14)

A 1.49 1.57 B

1.48(')

1.52 TBVOOS A

1.50 1.57 B

1.49 1.56 TBVOOS SLO (4)

A 1.54 1.61 B

1.48(6) 1.51 RPTOOS A

1.52 1.61 B

1.48 1.55 RPTOOS SLO(4)

A 1.56 1.65 (1) When Tau does not equal 0 or 1, use linear interpolation.

(2)

Analyzed DLO Option B OLMCPR is 1.40 per Reference 2, value is adjusted to obtain an oPRM amplitude setpoint of 1.13.

(3)

Analyzed DLO Option A OLMCPR is 1.45 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

(4)

For single-loop operation, the MCPR operating limit is 0.04 greater than the analyzed two loop value with a minimum of 1.48 to obtain a corresponding DLO OPRM setpoint of 1.13.

(5)

Analyzed DLO Option B OLMCPR is 1.45 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

(6)

Analyzed DLO Option B OLMCPR is 1.42 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

Exelon Nuclear - Nuclear Fuels P2CI 9 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 11 of 64 TABLE 4-3 Power Dependent MCPR(P) Limit Adjustments And Multipliers (Symmetric Feedwater Heating)

(Reference 2)

Core Core Thermal Power (% of rated)

EOOS Combination Flowf(%

0 re25

<30 MP 30 40 55 1 65 1 85T 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 2.56 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 1.131 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 1.131 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 P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 12 of 64 5.0 LINEAR HEAT GENERATION RATE LIMTS 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 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 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

Exelon Nuclear - Nuclear Fuels P2CI 9 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 13 of 64 TABLE 5-3 Power Dependent LHGR Multiplier LHGRFAC(P)

(Symmetric Feedwater Heating)

(Reference 2)

Core Thermal Power (% of rated)

Core Flow iiii EOOS Combination (% of rated) 0

[25 1 <3 0 I1 3 0 1 4 0 5 5 6 5 I 8 5 1 0 0 LHGRFAC(P) Multiplier

<_>60 0.516 0.516 0.53511 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

< 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 1

<60 0.516 0.516 0.535 RPTOOSSLO 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 TBVOOS SLO 0.640 0.655 0.7 14 0.8 17 0.930 1.000

> 60 0.414 0.414 0.424 TABLE 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)

(Symmetric Feedwater Heating)

(References 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 P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 14 of 64 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(')

MCPR Limit LTSP 125.8%

124.0%

< 1.70 (2)

< 1.403 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 (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 P2C1 9 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 15 of 64 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. 6 P2C19 Core Operating Limits Report Page 16 of 64 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 P2C1 9 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 17 of 64 9.0 STABILITY PROTECTION OSCILLATION POWER RANGE MONITOR (OPRM) 9.1 Technical Specification Section 3.3.1, Table 3.3.1.1 -1 Function 2.f 9.2 Description The CYCLE 19 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)

Corresponding Maximum PBDA Trip Amplitude Confirmation Count Trip Setting 1.13 15 TABLE 9-2 OPRM PBDA Trip Settings - SLO"t)

(Valid For SLO Conditions Only)

(Reference 2)

PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting 1.15 16 (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.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 6 P2C19 Core Operating Limits Report Page 18 of 64 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. 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).

LHGR LIMITS The ARTS-based LHGR power-dependent multipliers for AFTO operation are provided in Tables 10-2, 10-3, and 10-

4. The flow-dependent multipliers for AFTO are provided in Tables 10-5, 10-6, and 10-7 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. The SLO multiplier and the AFTO multiplier must be simultaneously applied. The maximum feedwater temperature difference allowed without a thermal limit penalty is 20 'F. Once the temperature difference exceeds 20 'F the graduated penalties from Table 10-1 are applied to the thermal limits. Tables 10-2 through 10-7 are applicable to both GE14 and GNF2 fuel type per References 8 and 10.

TABLE 10-1 AFTO Thermal Limit Penalties (Asymmetric Feedwater Heating)

(Reference 10)

MFLCPR MFLPD/MAPRAT 40F < FWT DELTA5 <55F 2%

4%

30F < FWT DELTA: <40F 2%

3%

20F < FWT DELTA < 30F No Penalty 2%

OF < FWT DELTA < 20F No Penalty No Penalty

Exelon Nuclear - Nuclear Fuels P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 19 of 64 TABLE 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTA <30F (Asymmetric Feedwater Heating)

(References 2 and 10)

Core Thermal Power (% of rated)

Core Flow ______________________________

EOOS Combination (% of rated) 0 25 1 <30 1>30 140 55 165 185 95 100 LHGRFAC(P) Multiplier

!S 60 0.506 0.506 0.524 Base 0.735 0.741 0.756 0.801 0.940 0.967 0.980

> 60 0.506 0.506 0.524

< 60 0.506 0.506 0.524 Base SLO 0.735 0.741 0.756 0.801 0.940 0.967 0.980

> 60 0.506 0.506 0.524 T 60 0.506 0.506 0.524 RPTOOS 60 0.506 0.506 0.524 0.735 0.741 0.756 0.801 0.940 0.967 0.980

> 60 0.506 0.506 0.524

< 60 0.506 0.506 0.5247 TBVOOS S60 0.627 0.642 0.700 0.801 0.911 0.957 0.980

> 60 0.406 0.406 0.416

< 60 0.413 0.413 0.472 TBVOOSSLO 0.627 0.642 0.700 0.801 0.911 0.957 0.980

> 60 0.406 0.406 0.4-16 TABLE 10-3 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 30F < FWT DELTA <40F (Asymmetric Feedwater Heating)

(References 2 and 10)

Core Thermal Power (% of rated)

Core Flow ________________________________

EOOS Combination (% of rated) 0 25 1 <30 1>30 40 155 165 85 195 100 LHGRFAC(P) Multiplier Base

60 0.501 0.501 0.519 0.728 0.733 0.748 0.792 0.930 0.957 0.970

> 60 0.501 0.501 0.519 BaeSL 60 0.501 0.501 0.519 Base60 0.501 0.501 0.519 0.728 0.733 0.748 0.792 0.930 0.957 0.970

> 60 0.501 0.501 10.5191 1

RPOS<60 0.501 0.501 0.519 RPTOOS 60 0.501 0.501 0.519

.728 0.733 0.748 0.792 0.930 0.957 0.970

> 60 0.501 0.501 0.519

< 60 0.501 0.501 0.519 RPTOOS SLO

-t II0.72810.733 0.748 0.792 10.930 10.957 0.970

> 60 0.501 0.501 0.519 TBVOOS

  • 60 0.408 0.408 0.468

> 60 0.402 0.402 0.411

< 60 0.408 0.408 0.468 TBVOOS SLO 0.402 1 0.40 1.

> 60 0.402 0.402 0.411

Exelon Nuclear - Nuclear Fuels P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 20 of 64 TABLE 10-4 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 40F < FWT DELTA <55F (Asymmetric Feedwater Heating)

(References 2 and 10)

Core Thermal Power (% of rated)

Core Flow ______________________________

EOOS Combination (% of rated) 0 25 1 <30 1_>30 140 55 165 85 195 1 00 LHGRFAC(P) Multiplier

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

> 60 0.495 0.495 0.514

_< 60 0.495 0.495 0.5 14 Base SLO 0.720 0.726 0.740 0.784 0.921 0.947 0.960

> 60 0.495 0.495 0.514

< 60 0.495 0.495 0.5 14 RPTOOS 0.720 0.726 0.740 0.784 0.921 0.947 0.960

> 60 0.495 0.495 0.514

< 60 0.495 0.495 0.5 14 RPTOOS SLO 0.720 0.726 0.740 0.784 0.921 0.947 0.960

> 60 0.495 0.495 0.514 TBVOOS

<60 0.404 0.404 0.463 0.614 0.629 0.685 0.784 0.893 0.938 0.960

> 60 0.397 0.397 0.407

< 60 0.404 0.404 0.463 TBVOOS SLO 0.614 0.629 0.685 0.784 0.893 0.938 0.960

> 60 0.397 0.397 0.407

Exelon Nuclear - Nuclear Fuels P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 21 of 64 TABLE 10-5 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTA < 30F (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 0.496 0.692 0.715 0.954 0.980 0.980 Single Loop 0.496 0.692 0.715 0.715 0.715 0.715 TABLE 10-6 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 30F < FWT DELTA < 40F (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 0.491 0.685 0.708 0.944 0.970 0.970 Single Loop 0.491 0.685 0.708 0.708 0.708 0.708 TABLE 10-7 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 40F < 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 0.486 0.678 0.701 0.701 0.701 0.701

Exelon Nuclear - Nuclear Fuels P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 22 of 64 MCPR LIMITS The OLMCPR for GE14 and GNF2 during asymmetric feedwater temperature operation with a feedwater temperature difference greater then 30 'F are provided in Tables 10-8 and 10-9. The ARTS-based power-dependent MCPR limits for use during AFTO conditions are provided in Table 10-10. The flow-dependent MCPR limits for AFTO are provided in Tables 10-11 and 10-12.

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.

Tables 10-10, 10-11, and 10-12 are applicable to both GE14 and GNF2 fuel type per References 8 and 10.

TABLE 10-8 AFTO Operating Limit Minimum Critical Power Ratio-GE14 > 30F FWT DELTA (Asymmetric Feedwater Heating)

(References 2 and 10)

SCRAM Cycle Exposure Time

<EOR-3400

> EOR -3400 EOOS Combination Option(1 MWd/ST

- MWd/ST B

1.48(2) 1.48(3)

BASE A

1.48(4) 1.48(')

B 1.48 1.48 BASE SLO(6)

A 1.48 1.51 B

1.48(7) 1.50 TBVOOS A

1.48(8) 1.53 B

1.48 1.54 TBVOOS SLO 16)

A 1.51 1.57 B

1.48(9) 1.51 RPTOOS A

1.54 1.68 B

1.48 1.55 RPTOOS SLO(6)

A 1.58 1.72 (1)

(1)

(2)

(3)

(4)

(5)

(6)

(7)

(8)

(9)

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

Analyzed DLO Option B OLMCPR is 1.38 per References 2 and 10, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

Analyzed DLO Option B OLMCPR is 1.44 per References 2 and 10, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

Analyzed DLO Option A OLMCPR is 1.41 per References 2 and 10, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

Analyzed DLO Option A OLMCPR is 1.47 per References 2 and 10, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

For single-loop operation, the MCPR operating limit is 0.04 greater than the analyzed two loop value with a minimum value of 1.48 to obtain a corresponding DLO OPRM amplitude setpoint of 1.13.

Analyzed DLO Option B OLMCPR is 1.44 per References 2 and 10, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

Analyzed DLO Option A OLMCPR is 1.47 per References 2 and 10, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

Analyzed DLO Option B OLMCPR is 1.43 per References 2 and 10, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

Exelon Nuclear - Nuclear Fuels P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 23 of 64 TABLE 10-9 AFTO Operating Limit Minimum Critical Power Ratio-GNF2 > 30F FWT DELTA (Asymmetric Feedwater Heating)

References 2, 8, and 10)

SCRAM Cycle Ex posure Time

< EOR - 3400

> EOR - 3400 EOOS Combination Option(")

MWd/ST MWd/ST B

1.48(2) 1.51 BASE A

1.48 1.56 B

1.48 1.55 BASE SLO(3)

A 1.52 1.60 B

1.48 1.55 TBVOOS A

1.53 1.60 B

1.52 1.59 TBVOOS SLO(3)

A 1.57 1.64 B

1.48(41 1.54 RPTOOS A

1.55 1.64 B

1.49 1.58 RPTOOS SLO(3)

A 1.59 1.68 (1) When Tau does not equal 0 or 1, use linear interpolation.

(2)

Analyzed DLO Option B OLMCPR is 1.43 per References 2 and 10, value is adjusted to obtain a corresponding OPRM amplitude setpoint of 1.13.

(3)

For single-loop operation, the MCPR operating limit is 0.04 greater than the analyzed two loop value with a minimum of 1.48 to obtain an OPRM amplitude setpoint of 1.13.

(4)

Analyzed DLO Option B OLMCPR is 1.45 per References 2 and 10, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.

Exelon Nuclear - Nuclear Fuels P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 24 of 64 TABLE 10-10 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) > 30F FWT DELTA (Asymmetric Feedwater Heating)

(References 2 and 10)

Core Core Thermal Power (% of rated)

EOOS Combination Flow(%

0

Ž25

<30

>30 40 65 5

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 2.61 2.61 2.52 Base SLO 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.88 2.88 2.66

< 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 2.61 2.61 2.52 RPTOOS SLO 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.88 2.88 2.66

< 60 3.35 3.35 2.84 TBVOOS 1.614 1.479 1.373 1.131 1.082 1.000

> 60 3.86 3.86 3.37

< 60 3.39 3.39 2.88 TBVOOS SLO 1.614 1.479 1.373 1.131 1.082 1.000

> 60 3.90 3.90 3.41 TABLE 10-11 AFTO Flow Dependent MCPR Limits MCPR(F) > 30F FWT DELTA (BOC to EOC)(Asymmetric Feedwater Heating)

(References 2 and 10)

Flow MCPR(F)

(%rated)

Limit 0.0 1.735 79.0 I

1.275 110.0 1.275 TABLE 10-12 AFTO SLO Flow Dependent MCPR Limits MCPR(F) > 30F FWT DELTA (BOC to EOC)(Asymmetric Feedwater Heating)

(References 2 and 10)

Flow MCPR(F)

(% rated)

Limit 0.0 1.775 79.0 1.315 110.0 1.315

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 6 P2C 19 Core Operating Limits Report Page 25 of 64 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. For single-loop operation, the AFTO multiplier is also applied to the MAPLHGR limits. The SLO multiplier in Table 3-3 and the AFTO multiplier in Table 10-13 must be simultaneously applied. Therefore, the SLO MAPLHGR multiplier is clamped at the value shown in Table 10-14 to ensure peak clad temperatures are maintained within the limits of the cycle-specific LOCA analysis for single recirculation loop and asymmetric feedwater temperature operation. Tables 10-13 and 10-14 are applicable to both GE14 and GNF2 fuel type per References 8 and 10.

TABLE 10-13 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)

Valid For All Conditions Except Single Loop (References 2 and 10)

AFTO Reduction Factor 20F < FWT DELTA < 30F 0.980 30F < FWT DELTA _< 40F 0.970 40F < FWT DELTA < 55F 0.960 TABLE 10-14 AFTO MAPLHGR Single Loop Operation (SLO) Reduction Factor (Asymmetric Feedwater Heating)

(References 2 and 10)

SLO AFTO Reduction Factor 20F < FWT DELTA < 30F 0.715 30F < FWT DELTA < 40F 0.708 40F < FWT DELTA _< 55F 0.701A

Exelon Nuclear - Nuclear Fuels P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 11.0 MODES OF OPERATION COLR PEACH BOTTOM 2 Rev. 6 Page 26 of 64 TABLE 11-1 Modes of Operation (Reference 2)

EOOS Options Operating Regionm t )

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-24011-P-A-16, October 2007 and U.S.

Supplement NEDE-240 11-P-A-16-US, October 2007.

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 2, RELOAD 18, CYCLE 19", GNF Document No.

0000-01 10-4769-SRLR, Revision 1, August 2010.

3. General Electric Document "General Electric Standard Application for Reactor Fuel", NEDE-2401 I-P-A-16, October 2007 and U.S. Supplement NEDE-2401 1-P-A-16-US, October 2007.

(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. 6 P2CI19 Core Operating Limits Report Page 27 of 64 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 1, September 2010.
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 ic dated 9/8/10.
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 0000-0110-4769-FBIR, "Fuel Bundle Information Report for Peach Bottom 2 RELOAD 18 CYCLE 19", Revision 1, August 2010.
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 # ES1000004, Rev. 0, Final Resolved OPL-3 Parameters for Peach Bottom Unit 2 Cycle 19 dated 4/21/10.

Exelon Nuclear - Nuclear Fuels P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Page 28 of 64 Appendix A

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 6 Non-Proprietary Information Submitted in Appendix A Accordance with 10 CFR 2.390 Global Nuclear Fuel - Americas LLC AFFIDAVIT I, Andrew A. Lingenfelter, state as follows:

(1) 1 am Vice President, Fuel Engineering, of Global Nuclear Fuel - Americas, LLC (GNF-A),

and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is contained in the GNF-A proprietary report, 0000-01 10-4769-FBIR Revision 1, Fuel Bundle Information Report for Peach Bottom Unit 2, Reload 18 Cycle 19, Class III, (GNF-A Proprietary Information), dated August 2010. GNF-A proprietary information in 0000-01 10-4769-FBIR Revision I is identified by a dark red dotted underline inside double square brackets. ((This sentence is an examp.e...] Figures and large equation objects containing GNF-A proprietary information are identified with double square brackets before and after the object. In each case, the superscript notation 131 refers to Paragraph (3) of this affidavit that provides the basis for the proprietary determination.

(3)

In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Proiect v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F2d 1280 (DC Cir. 1983).

(4) The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. Some examples of categories of information that fit into the definition of proprietary information are:

a.

Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over GNF-A and/or other companies.

b.

Information that, if used by a competitor, would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.

c.

Information that reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, that may include potential products of GNF-A.

GNF-0000-0 110-4769-RI Affidavit Page I of 3 COLR Page 29 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 6 Non-Proprietary Information Submitted in Appendix A Accordance with 10 CFR 2.390

d.

Information that discloses trade secret and/or potentially patentable subject matter for which it may be desirable to obtain patent protection.

(5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to the NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary and/or confidentiality agreements that provide for maintaining the information in confidence. The initial designation of this information as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure are as set forth in the following paragraphs (6) and (7).

(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, who is the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or who is the person most likely to be subject to the terms under which it was licensed to GNF-A. Access to such documents within GNF-A is limited to a "need to know" basis.

(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary and/or confidentiality agreements.

(8) The information identified in paragraph (2) above is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology for the Boiling Water Reactor (BWR). Development of these methods, techniques, and information and their application for the design, modification, and analyses methodologies and processes was achieved at a significant cost to GNF-A. The development of the evaluation process along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GNF-A asset.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The fuel design and licensing methodology is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.

GNF-0000-0 110-4769-RI Affidavit Page 2 of 3 COLR Page 30 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Appendix A The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GNF-A. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial. GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.

The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.

I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.

Executed on this 11 th day of August, 2010 W4'41_117ý ~1 Andrew A. Lingenfelter Vice President, Fuel Engineering Global Nuclear Fuel - Americas LLC GNF-0000-0 110-4769-R I Affidavit Page 3 of 3 COLR Page 31 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 6 Appendix A Global Nuclear Fuel A Joint Venture of GE, Toshiba, & Hitachi 0000-0110-4769-FBIR-NP Revision 1 Class I August 2010 Non-Proprietary Information Fuel Bundle Information Report for Peach Bottom Unit 2 Reload 18 Cycle 19 COLR Page 32 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 6 Non-Proprietary Information Submitted in Appendix A Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Non-Proprietary Information 0000-01 10-4769-FBIR-NP Reload 18 Class I Revision 1 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

("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 Infonnation 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.

Proprietary Information Notice This document is the non-proprietary version of the GNF-A proprietary report.

From the GNF-A proprietary version, the information denoted as GNF-A proprietary (enclosed in double brackets) was deleted to generate this version.

COLR Page 33 of 64 Page 2

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 6 Non-Proprietary Information Submitted in Appendix A Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Non-Proprietary Information 0000-01 10-4769-FBIR-NP Reload 18 Class I Revision I

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 19. 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 taro 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.

Reference 2 limits GNF2 peak pellet exposure (PPE) to ((

i!.

Page 3 COLR Page 34 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Class I

2. References
1. General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-16, October 2007; and the U.S. Supplement, NEDE-2401 I-P-A-16-US, October 2007.

2 GNF2 Advantage Generic Compliance with NEDE-2401JI-P-A (GESTAR I1), NEDC-33270P, Revision 3, March 2010.

Page 4 COLR Page 35 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Class 1 Appendix A UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 10 DNAB416-15GZ-lOOT-150-T6-2908 (GE 14C)

Bundle Number: 2908 Peak Pellet Exposure U0 2 LH.GR 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 Limitt 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

'Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 5 COLR Page 36 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Irformation Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Classq I UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1 ODNAB417-13G6.0- I OOT-150-T6-2909 (GE 14C)

Bundle Number: 2909 Peak Pellet Exposure U0 2 LHGR Limit GWdIMT (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 2 GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 12.26 13.53 (12.28) 12.26 60.63 (55.00) 7.32 67.07 (60.84) 4.57 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (6.0% Gd).

Page 6 COLR Page 37 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-0110-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I eload 18 Class 1.

UOIGd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-PI ODNAB415-15GZ-100T-150-T6-2910 (GE 14C)

Bundle Number: 2910 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 GWdiMT (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 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).

Page 7 COLR Page 38 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 1 0-4769-FBLR-NP Revision I Non-Proprietary Information Class I UO 21Gd Thermal-Mechanical LHGR Limits Bundlc Type: GE 14-P 1 ODNAB416-15GZ-I OOT-150-T6-29 11 (GE I4C)

Bundle Number: 2911 Peak Pellet Exposure U0 2 LHIGR 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 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).

Page 8 COLR Page 39 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I UO 21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P1ODNAB416-15GZ-1OOT-150-T6-2912 (GE 14C)

Bundle Number: 2912 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 5 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 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).

Page 9 COLR Page 40 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-011.0-4769-FBIR-NP

.Revision I Non-Proprietary Information Class I UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1 ODNAB409-15GZ-lOOT-150-T6-2913 (GE 14C)

Bundle Number: 2913 Peak Pellet Exposure UO 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 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 Bounding gadolinia LHGR limit for all gadolinium conccntrations occurring in this bundle design ( 8.0% Gd).

Page 10 COLR Page 41 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Class I UO 2 Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10DG2B406-12G6.0-1 00T2-150-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 7 GWd/MT (GWd/ST) kW/ft

____________[ __________I

. Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [l IH.

Page 11 COLR Page 42 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I eload 18 Revision I UO 21Gd Thermal-Mechanical LHGR Limits Bundle TNpe: GNF2-P 10DG2B393-15GZ-100T2-150-T6-3334 (GNF2)

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

____________________________________ ].

s Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [1 II.

Page 12 COLR Page 43 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-0110-4769-FBIR-NP Revision I Non-Proprietary Information Class I UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-PlODNAB420-13GZ-IOOT-150-T6-3097 (GEI4C)

Bundle Number: 3097 Peak Pellet Exposure UO2 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 9 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 9 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle dcsign ( 8.0% Gd).

Page 13 COLR Page 44 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Class I UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-PI 0DNAB416-1 5GZ-lOOT-1 50-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'o 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 "o Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).

Page 14 COLR Page 45 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 1.8 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-0110-4769-FBIR-NP Revision I Non-Proprietary Information Class I UO 21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-PIODNAB411-15GZ-1OOT-150-T6-3099 (GE 14C)

Bundle Number: 3099 Peak Pellet Exposure U0 2 LHiGR 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" GWd/MT (GWdIST) 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 t Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).

Page 15 COLR Page 46 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision 1 Non-Proprietary Information Class 1.

UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Ty*e: GNF2-P I 0DG2B388-6G8.0/6G7.0/2G6.0- 100T2-150-T6-3336 (GNF2)

Bundle Number: 3336 Peak Pellet Exposure U02 LHGR Limit GWd/MT (GWd/ST) kW/ft I1 11 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit" GWd/MT (GWd/ST) kW/ft II

_____________________________________ 1 32 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((

i].

Page 16 COLR Page 47 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Class I UO 2lGd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10DG2B392-15GZ-100T2- ! 50-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 13 GWd/MT (GWd/ST) kW/ft Ir____________________

__________________________________]I 13 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design If 11.

Page 17 COLR Page 48 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP

.Revision I Non-Proprietary Information Class I UO 2/Gd Thermal-Mechanical LHGR Limits Bundle T'.pe: GNF2-P I 0DG2B392-I 5GZ-I 00T2-150-T6-3332 (GNF2)

Bundle Number: 3332 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft

[i Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 14 GWd/MT (GWd/ST) kW/ft I[I 14 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ([

fl.

Page 18 COLR Page 49 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Class I Appendix B Fuel Bundle Information Table BI-I Bundle Specific Information Fuel Bundle Enrichment Weight Weight Max Exposure Of U0 2 ofU k,, at at Max k.

Bundle Number (wt% U-235) og (kg 2f UWd/MT (kg)

(kg) 20 0 C1 G

dM (GWd/ST)

GE14-PlODNAB416-I15GZ-IOOT-150-T6-2908 (GE14C)

GE 14-P ODNAB417-13G6.0-1OOT-150-T6-2909 (GE 14C)

GE14-PI ODNAB415-15GZ-1 OOT I 50T6-2910 (G 14C GE14-P)I1ODNAB4I6-15GZ-2911 1 OT-150-T6-29 11(GE 14C)

GEl4-PlODNAB416-15GZ-1OOT-150-T6-2912 (GE 14C)

GE14-PIODNAB419-15GZ-100T-150-T6-2913 (GEI4C)

GN F2-P I0DG2B406-1 2G6.0-100T2-150-T6-3337 (GNF2)

GNF2-P l0DG2B393-15GZ-100T2-150-T6-3334 (GNF2)

GE14-P l ODNAB42--13GZ-100T-150-T6-3097 (GEI14C)

GE 14-P 1 ODNAB4216-15GZ-100T-150-T6-3098 (GE14C)

GE14-PIODNAB416-15GZ-100T-150-T6-3099 (GE I4C)

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

GNF2-P I 0DG2B392-15GZ-100T2-150-T6-3335 (GNF2)

GNF2-P I 0DG2B392-15GZ-3332 100T2-150-T6-3332 (GNF2) 15 Maximum lattice k,, for the most reactive uncontrolled state plus a ((

II adder for uncertainties.

Page 19 COLR Page 50 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I Reload 18 Revision 1

[I 1]

Figure B-1 Enrichment and Gadolinium Distribution for EDB No. 2908 Fuel Bundle GEI4-PIODNAB416-15GZ-10OT-IS0-T6-2908 (GE14C)

Page 20 COLR Page 51 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 1.8 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP

.Revision I Non-Proprietary Information Class I

[I Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 2909 Fuel Bundle GE14-PIODNAB417-13G6.0-100T-150-T6-2909 (GE14C)

Page 21 COLR Page 52 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I

[I Figure B-3 Enrichment and Gadolinium Distribution for EDB No. 2910 Fuel Bundle GEI4-PIODNAB415-15GZ-IOOT-150-T6-2910 (GEl4C)

Page 22 COLR Page 53 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Class I

[I Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 2911 Fuel Bundle GE14-PI ODNAB416-15GZ-IOOT-150-T6-2911 (GE14C)

Page 23 COLR Page 54 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-0110-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I.

1[

1]

Figure B-5 Enrichment and Gadolinium Distribution for EDB No. 2912 Fuel Bundle GE14-PIODNAB416-15GZ-1OOT-150-T6-2912 (GEI4C)

Page 24 COLR Page 55 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Class I

((i Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 2913 Fuel Bundle GEI4-PIODNAB409-15GZ-IOOT-150-T6-2913 (GE14C)

Page 25 COLR Page 56 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I Reload 18 Revision I

[I 1]

Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 3337 Fuel Bundle GNF2-PIODG2B406-12G6.0-100T2-150-T6-3337 (GNF2)

Page 26 COLR Page 57 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I Class I

[1 1]

Figure "-8 Enrichment and Gadolinium Distribution for EDB No. 3334 Fuel Bundle GNF2-P10DG2B393-15GZ-100T2-150-T6-3334 (GNF2)

Page 27 COLR Page 58 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP

.Revision I Non-Proprietary Information Class I 11 Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 3097 Fuel Bundle GEI4-PIODNAB420-13GZ-10OT-150-T6-3097 (GEl4C)

Page 28 COLR Page 59 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 1 0-4769-FBIR-NP Revision I Non-Proprietary Information Class I R[

))

Figure B-10 Enrichment and Gadolinium Distribution for EDB No. 3098 Fuel Bundle GEI4-P1ODNAB416-15GZ-1.OOT-l50-T6-3098 (GEI4C)

Page 29 COLR Page 60 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I It

))

Figure B-I I Enrichment and Gadolinium Distribution for EDB No. 3099 Fuel Bundle GEI4-PI ODNAB411-I 5GZ-IOOT-150-T6-3099 (GE14C)

Page 30 COLR Page 61 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Class I

((

))

Figure B-12 Enrichment and Gadolinium Distribution for EDB No. 3336 Fuel Bundle GNF2-PIODG2B388-6G8.0/6G7.0/2G6.0-100T2-150-T6-3336 (GNF2)

Page 31 COLR Page 62 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-0110-4769-FBIR-NP Revision I Non-Proprietary Information Class I It

))

Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 3335 Fuel Bundle GNF2-P10DG2B392-15GZ-100T2-150-T6-3335 (GNF2)

Page 32 COLR Page 63 of 64

Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 6 Appendix A 0000-01 10-4769-FBIR-NP Revision l Non-Proprietary Information Class I eload 18 Revision I

[!

))

Figure B-14 Enrichment and Gadolinium Distribution for EDB No. 3332 Fuel Bundle GNF2-P1ODG2B392-15GZ-100T2-150-T6-3332 (GNF2)

Page 33 COLR Page 64 of 64

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