ML11272A204

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Issuance of the Core Operating Limits Report for Reload 18, Cycle 19, Revision 6
ML11272A204
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 09/30/2011
From: Armstrong J
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CCN: 11-82
Download: ML11272A204 (65)
v • d • e


Text

Exelon Nuclear www.exeloncorp.com Exelon. Nuclear Peach Bottom Atomic Power Station 1848 Lay Rd.

Delta, PA 17314 TS 5.6.5.d September 30, 2011 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555-0001 Peach Bottom Atomic Power Station, Unit 3 Renewed Facility Operating License No. DPR- 56 NRC Docket No. 50-278

Subject:

"\.Issuance of the Core Operating Limits Report for Reload 18, Cycle 19, Revision 6 Enclosed is a copy of Revision 6 of the Core Operating Limits Report (COLR) for Peach Bottom Atomic Power Station (PBAPS), Unit 3 for Reload 18, Cycle 19. Revision 6 of this report incorporates the revised cycle specific parameters resulting from the new core configuration implemented during the PBAPS, Unit 3 refueling outage.

This COLR is being submitted to the NRC as required by the PBAPS, Unit 3 Technical Specifications (TS)

Section 5.6.5.d. contains information proprietary to Global Nuclear Fuel. Global Nuclear Fuel requests that the document be withheld from public disclosure in accordance with 10 CFR 2.390(a)(4). An affidavit supporting this request is also contained in Attachment 1. Attachment 2 contains a non-proprietary version of the Global Nuclear Fuel document.

Should you have any questions concerning this letter, please contact Dave Foss at (717) 456-4311.

James M. Armstrong Regulatory Assurance Manager Peach Bottom Atomic Power Station CCN: 11-82 Attachments:

1. Core Operating Limits Report for Reload 18, Cycle 19, Revision 6 (including Affidavit and Proprietary Version
2. Core Operating Limits Report for Reload 18, Cycle 19, Revision 6 (Non-Proprietary Version) cc: Regional Administrator, Region I, USNRC (without attachments)

USNRC Senior Resident Inspector, PBAPS (without attachments)

Project Manager- PBAPS, USNRC (with attachments)

R. R. Janati, Pennsylvania Bureau of Radiation Protection (without attachments)

S. T. Gray, State of Maryland (without attachments)

ATTACHMENT 2 Core Operating Limits Report for Reload 18, Cycle 19, Revision 6 Non-Proprietary Version

£Eiloo Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limite Report Non-Proprietary Information Submitted In Page I of 63 Accordance with 10 CFR 2.390 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 3 RELOAD 18, CYCLE 19 (This revision Iaa complete re-writm, no annotations are used)

Prpeafd By: -- T. Stratw, Date:

ESA Reviewer. Ac::

.In A.( 3lsoa Dale: Itq44I RE Reviewer.

cvt ~ Date!

A. Psaws Independent Reviewer. If Date:

Independent Reviewer. Date:

Approved By:

Station Qualified J.THolley Reviewer Date:*" C./i I

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 2 of 63 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 LHGR LIMITS 12 6.0 ROD BLOCK MONITOR SETPOINTS 15 7.0 TURBINE BYPASS VALVE PARAMETERS 16 8.0 EOC RECIRCULATION PUMP TRIP (EOC-RPT) OPERABILITY 17 9.0 STABILITY PROTECTION OSCILLATION POWER RANGE MONITOR (OPRM) 18 10.0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION (AFTO) 19 11.0 MODES OF OPERATION 26 12.0 METHODOLOGY 26

13.0 REFERENCES

27 Appendix A 28

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 3 of 63 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 7 Table 4-1 Operating Limit Minimum Critical Power Ratio 9 Table 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers 10 Table 4-3 Flow Dependent MCPR Limits MCPR(F) 10 Table 4-4 SLO Flow Dependent MCPR Limits MCPR(F) 11 Table 5-1 Linear Heat Generation Rate Limits - GEl4 Bundle U02 rods 12 Table 5-2 Linear Heat Generation Rate Limits - GNF2 Bundle U02 rods 12 Table 5-3 Linear Heat Generation Rate Limits - GE14 Bundle Gadolinia rods 13 Table 5-4 Linear Heat Generation Rate Limits - GNF2 Bundle Gadolinia rods 13 Table 5-5 Power Dependent LHGR Multiplier LHGRFAC(P) 14 Table 5-6 Flow Dependent LHGR Multiplier LHGRFAC(F) 14 Table 6-1 Rod Block Monitor Setpoints 15 Table 7-1 Turbine Bypass System Response Time 16 Table 7-2 Minimum Required Bypass Valves to Maintain System Operability 16 Table 9-1 OPRM PBDA Trip Settings 18 Table 9-2 OPRM PBDA Trip Settings - SLO 18 Table 10-1 AFTO Thermal Limit Penalties 19 Table 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20 OF < FWT DELTA < 30 OF 20 Table 10-3 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 30 OF < FWT DELTA <40 OF 20 Table 10-4 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 40 OF < FWT DELTA <55 OF 21 Table 10-5 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20 OF < FWT DELTA <30 OF 22 Table 10-6 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 30 OF < FWT DELTA <40 OF 22

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 4 of 63 Accordance with 10 CFR 2.390 Table 10-7 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 40 OF < FWT DELTA <55 OF 22 Table 10-8 AFTO Operating Limit Minimum Critical Power Ratio 30 'F < FWT DELTA < 55 OF 23 Table 10-9 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 30 OF < FWT DELTA < 55 OF 24 Table 10-10 AFTO Flow Dependent MCPR Limits MCPR(F) 30 OF < FWT DELTA <55 OF 24 Table 10-11 AFTO SLO Flow Dependent MCPR Limits MCPR(F) 30 OF < FWT DELTA < 55 OF 25 Table 10-12 AFTO MAPLHGR Reduction Factor 25 Table 10-13 AFTO MAPLHGR Single Loop Operation (SLO) Reduction Factor 25 Table 11-1 Modes of Operation 26

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 5 of 63 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 EOOS Equipment Out of Service. An analyzed option that assumes certain equipment to be non-operational.

EOC End of Cycle EOR End of Rated. The cycle exposure at which reactor power is equal to 100% (3514 MWth) with recirculation system flow equal to 100% of rated, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.

FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service HTSP Rod Block Monitor High Trip Setpoint ICF Increased Core Flow ITSP Rod Block Monitor Intermediate Trip Setpoint LHGR Linear Heat Generation Rate LHGRFAC(F) ARTS LHGR thermal limit flow dependent adjustments and multipliers LHGRFAC(P) ARTS LHGR thermal limit power dependent adjustments and multipliers LTSP Rod Block Monitor Low Trip Setpoint MAPLHGR 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 MELLLA Maximum Extended Load Line Limit Analysis OLMCPR Operating Limit Minimum Critical Power Ratio OPRM PBDA Oscillation Power Range Monitor Period Based Detection Algorithm RPTOOS Recirculation Pump Trip Out of Service SLO Single Loop Operation TBVOOS Turbine Bypass Valves Out of Service

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 6 of 63 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 3 Cycle 19 (Reload 18):

  • Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
  • 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)
  • Single Loop Operation (SLO) LHGR multipliers
  • Rod Block Monitor (RBM) Analytical Limits, Allowable Values and MCPR Limits
  • 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 methodologies 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%
  • Final Feedwater Temperature Reduction (FFWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) to 90 'F temperature reduction maintaining < 100% load line
  • 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 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 for feedwater temperature as a function of thermal power for both FWHOOS and FFWTR are specified in the appropriate Peach Bottom procedures and Reference 2.

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 is 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 Analyses (ARTS/MELLLA) for Peach Bottom Unit 3 Cycle 19.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 7 of 63 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 are provided for 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 are loaded in the process computer databank. The SLO MAPLHGR reduction factor is applied as shown in Table 3-3 per Reference 2. This value is applicable to the GE14 and GNF2 product lines. The impact of AFTO on MAPLHGR is addressed in Section 10. MAPFAC(P) and MAPFAC(F) are 1.0 for all conditions.

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 All Fuel Types (Reference 2)

SLO Reduction Factor 0.73::

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 8 of 63 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 MCPRs (OLMCPRs) are provided in Table 4-1. Table 4-1 is valid for all fuel types in the core. OLMCPRs are the maximum values obtained from analysis of pressurization events, non-pressurization events, and Option III stability evaluation. MCPR values are determined by the cycle-specific fuel reload analyses in Reference 2. Control rod scram time verification is required 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), per Methodology Reference 1.

Separate OLMCPR values are presented in Table 4-I for the following domains:

" TBVs In-Service (seven or more in-service) and RPT In-Service, maximum FWTR of 90'F "TBVs Out-of-Service (six or less in-service) and RPT In-Service, maximum FWTR of 90'F "TBVs In-Service (seven or more in-service) and RPT Out-of-Service, maximum FWTR of 90'F The ARTS-based power-dependent MCPR limits and multipliers are provided in Table 4-2. Table 4-2 is valid for a maximum temperature reduction of 90 'F for FWTR operation. The flow-dependent MCPR limits are provided in Table 4-3. Flow-dependent MCPR limits for single loop operation (SLO) are provided in Table 4-4. Tables 4-2, 4-3, and 4-4 are valid for all fuel types in the core. The impact of AFTO on MCPR is addressed in Section 10.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 9 of 63 Accordance with 10 CFR 2.390 TABLE 4-1 Operating Limit Minimum Critical Power Ratio All Fuel Types (Symmetric Feedwater Heating)

(Reference 2)

SCRAM Cycle Exposure Time < EOR - 5167 > EOR - 5167 EOOS Combination Option(') MWd/ST MWd/ST B 1.42(2) 1.42(2)

BASE A 1.42(2) 1.43 B 1.44 1.44 BASE SLO(3) A 1.44 1.46 B 1.4212) 1.42(2)

TBVOOS A 1.42(2) 1.48 B 1.44 1.44 TBVOOS SLO(') A 1.44 1.51 B 1.42(2) 1.43 RPTOOS A 1.47 1.60 B 1.44 1.46 RPTOOS SLO(3) A 1.50 1.63 (1) When Tau does not equal 0 or 1, use linear interpolation.

(2) OLMCPR is set to reflect two loop operation OPRM amplitude setpoint of 1.12.

(3) For single loop operation, the OLMCPR is 0.03 greater than the two loop limit (with the exception of the OPRM based OLMCPR, which remains the same). However, a minimum value of 1.44 is required to obtain an OLMCPR set by the Single Loop Operation Recirculation Pump Seizure event (Reference 2).

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 10 of 63 Accordance with 10 CFR 2.390 TABLE 4-2 Power Dependent MCPR(P) Limit Adjustments And Multipliers (Symmetric Feedwater Heating)

(Reference 2)

Core Core Thermal Power (% of rated)

EOOS Combination Flow 0 25 <30 >30 40 55 65 85 100 rated) Operating Limit MCPR Operating 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 2.55 2.55 2.46 Base SLO 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.81 2.81 2.60

< 60 2.52 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 2.55 2.55 2.46 RPTOOS SLO 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.81 2.81 2.60

< 60 3.28 3.28 2.78 TBVOOS 1.614 1.479 1.373 1.155 1.082 1.000

> 60 3.78 3.78 3.30

< 60 3.31 3.31 2.81 TBVOOS SLO 1.614 1.479 1.373 1.155 1.082 1.000

> 60 3.81 3.81 3.33 TABLE 4-3 Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating)

(Reference 2)

Core Flow MCPR(F)

(% rated) Limit 0.0 1.701 30.0 1.530 79.0 1.250 110.0 1.250

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 11 of 63 Accordance with 10 CFR 2.390 TABLE 4-4 SLO Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating)

(Reference 2)

Core Flow MCPR(F)

(% rated) Limit 0.0 I 1.731 30.0 j 1.560 79.0 1.280 110.0 1 1.280

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 12 of 63 Accordance with 10 CFR 2.390 5.0 LHGR 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 Tables 5-1 through 5-4 and Appendix A. The ARTS-based LHGR power-dependent multipliers are provided in Table 5-5. Table 5-5 is valid for a maximum temperature reduction of 90 'F for FWTR operation. The flow-dependent multipliers are provided in Table 5-6 as a function of the number of recirculation loops in operation. The SLO LHGR multiplier of 0.73 is accounted for in Table 5-6. The power-and flow-dependent LHGR multipliers were obtained from Reference 2. The impact of AFTO on LHGR is addressed in Section 10.

TABLE 5-1 Linear Heat Generation Rate Limits - GE14 Bundle U02 rods (Reference 13)

Peak Pellet Exposure LHGR Limit (GWd/ST) (kW/ft)

GE14 See Appendix A TABLE 5-2 Linear Heat Generation Rate Limits - GNF2 Bundle U02 rods (Reference 13)

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 13 of 63 Accordance with 10 CFR 2.390 TABLE 5-3 Linear Heat Generation Rate Limits - GE14 Bundle Gadolinia rods (Reference 13)

Peak Pellet Exposure LHGR Limit (GWd/ST) (kW/ft)

GE14 See Appendix A TABLE 5-4 Linear Heat Generation Rate Limits - GNF2 Bundle Gadolinia rods (Reference 13)

Peak Pellet Exposure LHGR Limit (GWd/ST) (kW/ft)

GNF2 See Appendix A

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 14 of 63 Accordance with 10 CFR 2.390 TABLE 5-5 Power Dependent LHGR Multiplier LHGRFAC(P)

(Symmetric Feedwater Heating)

(Reference 2)

Core Thermal Power (% of rated)

EOOS Combination (%of rated) 0F 25 1 <30 1 _>30 40 1 55 65 85 100 LHGRFAC(P) Multiplier Base ~ ~60

<60 0.516 0.516 0.516 0.516 0.5350.5 0.535 0.5 071087 099 100 Base SLO 0.750 0.756 0.771 0.817 0.959 1.000

> 60 0.516 0.516 0.535 RPTOOS <560 0.516 0.516 10.535 0.750 0.756 0.771 0.817ý, 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

<60 0.421 0.421 0.421 0.421 0.482 0.482 0.640 0.655 0.714 0.817 0.930 1.000

>60 0.414 0.414 0.424 TBVOOSSLO 0.640 0.655 0.714 0.817 0.930 1.000

> 60 0.414 0.414 0.424 TABLE 5-6 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 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 15 of 63 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, Nominal Trip Setpoints, and MCPR Limits are provided in Table 6-1 with supporting documentation from References 2 and 10.

TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 10) llwaleVaue'~

Limt~~ Nominal Trip MCPR Analytical Limit(p) Allowable Valueol) Nointrip Limit Power Level 124.0% 123.0% < 1.70(2)

LTSP 125.8%

< 1.40 (3)

ITSP 121.0% 119.2% 117.0% < 1.70(2)

< 1.40 )

HTSP 116.0% 114.2% 111.0% < 1.70(2)

< 1.40 (3)

N/A N/A N/A < 1.70 (2)

INOP < 1.40 (')

{I) 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 specified in Table 4-1.

(2) This is the MCPR limit (given THERMAL POWER is >28.4% and < 90%) below which the RBM is required to be OPERABLE (see 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 Reference 2 and TS Table 3.3.2.1-1).

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 16 of 63 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. The OLMCPR for TBVOOS must also 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 18.

TABLE 7-1 Turbine Bypass System Response Time (Reference 18)

Maximum delay time before start of bypass valve opening 0.10 sec following generation of the turbine bypass valve flow signal 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 18)

Reactor Power No. of Valves in Service P > 25% 7

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 17 of 63 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 3.3.4.2. If the requirements cannot be met, the appropriate power and flow dependent limits for EOC Recirculation Pump Trip (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 for both trips and is defined as the time from the turbine valves (TCV or TSV) start to close until complete arc suppression of the EOC-RPT circuit breakers. Reference 8 provides the basis for the RPT response time.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 18 of 63 Accordance with 10 CFR 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 19 OPRM Period Based Detection Algorithm (PBDA) Trip Settings are provided in Tables 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 (Methodology Reference 9). 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 (SPIDs) G-080-VC-174 through 177 (Unit-3).

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

(Reference 2)

PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting 1.12 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 1.15 16 (I 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 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 19 of 63 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. 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 11.

The threshold values are incorporated in the station procedures that govern AFTO.

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 per Reference 11. The SLO multiplier and the AFTO multiplier must be simultaneously applied. The maximum feedwater temperature difference allowed without a thermal limit penalty is 20 OF. Once the temperature difference exceeds 20 OF, the graduated penalties from Table 10-1 are applied to the thermal limits. Tables 10-2 through 10-7 are applicable for all fuel types in the core.

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

(Reference 11)

MFLCPR MFLPD/MAPRAT 40 OF FWT DELTA* 55 OF 2% 4%

30 OF < FWT DELTA* 40 OF 2% 3%

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

0 OF < FWT DELTA _< 20 OF No Penalty No Penalty

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 20 of 63 Accordance with 10 CFR 2.390 TABLE 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20 OF < FWT DELTA <30 OF (Asymmetric Feedwater Heating)

(References 2 and 11)

Core Thermal Power (% of rated)

Core Flow_____________________________

EOOS Combination (% of rated) 0 25 1<30 I-3o 1 40 155 165 85 100 LHGRFAC(P) Multiplier

> 60 0.506 0.506 0.524 Base SLO 0.735 0.741 0.756 0.801 0.940 0.980

> 60

<*60 0.506 0.506 0.506 0.506 0.524 0.524 RPTOOS < 0.735 0.741 0.756 0.801 0.940 0.980

> 60 0.506 0.506 0.524 RPTOOS L S > 60 0.506 0.506 0.524 0.524 0.735 0.741 0.756 0.801 0.940 0.980 RPTOOSSLO *60 0.506 0.506 0.52 0.735 0.741 0.756 0.801 0.940 0.980

> 60 0.506 0.506 0.524 TBVOOS *60 0.413 0.627 0.642 0.700 0.801 0.911 0.980

S60

> 60 0.406 10.4130.7 0.406 0.416

<60 0.413 0.413 0.472 TBVOOS SLO 0.627 0.642 0.700 0.801 0.9 11 0.980

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

(References 2 and 11)

Thermal Power (% of rated)

Core Flow r _____________________________

FCore EOOS Combination %ofratd) 0 25 <30 >30 40 55 65 85 100 LHGRFAC(P) Multiplier

<60 0.501 0510.519 Base 0.728 0.733 0.748 0.792 0.930 0.970

>60 0.501 0.501 0.519

<60 0.501 0.501 0.519 0.733 0.748 0.792 0.930 0.970 Base SLO > 60 0.501 0.501 0.519 0.728

_________ < 60 0.501 0.501 0.519 RPTOOS *60 0.501 0.501 0.519 0.728 0.733 0.748 0.792 0.930 0.970

> 60 0.501 0.501 0.519 RPTOOS SLO *560 0.501 0.501 0.5 19 0.728 0.733 0.748 0.792 0.930 0.970

>60 0.501 0.501 0.519 TBVOOS *>*60 60 0.408 0.408 0.408 0.408 0.468 0.468 0.621 0.635 0.693 0.792 0.902 0.970 60 0.402 0.402 0.411 TBVOOS SLO 0.621 0.635 0.693 0.792 0.902 0.970

> 60 0.402 0.402 0.411

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 21 of 63 Accordance with 10 CFR 2.390 TABLE 10-4 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 40 OF < FWT DELTA <55 OF (Asymmetric Feedwater Heating)

(References 2 and 11)

Core Flow Core Thermal Power (% of rated)

EOOS Combination (% of rated) 0 25 1<30 1 30 1 40 55 165 185 1 100 LHGRFAC(P) Multiplier

<160 0.495 0.495 0.514 Base 0.720 0.726 0.740 0.784 0.921 0.960

> 60 0.495 0.495 0.514

<160 0.495 0.495 0.514 Base SLO 0.720 0.726 0.740 0.784 0.921 0.960

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

> 60 0.495 0.495 0.514 RPTOOS SLO ><60 0.495 0.495 0.514 0.720 0.726 0.740 0.784 0.92 1 0.960

_________ > 60 0.495 0.495 0.514 TBVOOS 5160 0.404 0.404 0.463 0.614 0.629 0.685 0.784 0.893 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 0.960

> 60 0.397 0.397 0.407 __

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 22 of 63 Accordance with 10 CFR 2.390 TABLE 10-5 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20 OF < FWT DELTA <30 OF (Asymmetric Feedwater Heating)

(References 2 and 11)

Core Flow (% of rated)

EOOS Combination 0 30 33.6 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) 30 OF < FWT DELTA <40 OF (Asymmetric Feedwater Heating)

(References 2 and 11)

Core Flow (% of rated)

EOOS Combination 0 30 33.6 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) 40 OF < FWT DELTA < 55 OF (Asymmetric Feedwater Heating)

(References 2 and 11)

Core Flow (% of rated)

EOOS Combination 0 30 33.6 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 COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 23 of 63 Accordance with 10 CFR 2.390 MCPR LIMITS The OLMCPRs for all fuel types in the core during asymmetric feedwater temperature operation with a feedwater temperature difference greater then 30 OF are provided in Table 10-8. Per Table 10-1, a 2% penalty was applied to MCPR values for a feedwater temperature difference greater than 30 OF. The ARTS-based power-dependent MCPR limits for use during AFTO conditions are provided in Table 10-9. The flow-dependent MCPR limits for AFTO are provided in Table 10-10. Flow-dependent MCPR limits for AFTO and SLO are provided in Table 10-

11. The power and flow-dependent OLMCPR curves were obtained from Reference 2 and were adjusted with a 2% penalty for feedwater temperature difference greater than 30 OF as displayed in Table 10-1 per Reference 11.

No MCPR penalties are required for asymmetric temperature differentials less than or equal to 30 °F. Tables 10-8 through 10-11 are valid for all fuel types in the core.

TABLE 10-8 AFTO Operating Limit Minimum Critical Power Ratio 30 OF < FWT DELTA _55 OF All Fuel Types (Asymmetric Feedwater Heating)

(References 2 and 11)

SCRAM Cycle Exposure Time < EOR - 5167 > EOR - 5167 EOOS Combination Option(l) MWd/ST MWd/ST B 1.45(2) 1.45(2)

BASE A 1.45(2) 1.46 B 1.47 1.47 BASE SLO(3 ) A 1.47 1.49 B 1.45(2) 1.45(2)

TBVOOS A 1.45(2) 1.51 B 1.47 1.47 3

TBVOOS SLO( ) A 1.47 1.54 B 1.45(2) 1.46 RPTOOS A 1.50 1.63 B 1.47 1.49 RPTOOS SLO(3 ) A 1.53 1.66 (1) When Tau does not equal 0 or 1, use linear interpolation.

(2)

OLMCPR is set to reflect two loop operation OPRM amplitude setpoint of 1.12.

(3) For single loop operation, the OLMCPR is 0.03 greater than the two loop limit (with the exception of the OPRM based OLMCPR, which remains the same). However, a minimum value of 1.44 is required to obtain an OLMCPR set by the Single Loop Operation Recirculation Pump Seizure event (Reference 2).

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 24 of 63 Accordance with 10 CFR 2.390 TABLE 10-9 AFTO Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) 30 OF < FWT DELTA < 55 OF (Asymmetric Feedwater Heating)

(References 2 and 11)

Core Core Thermal Power (% of rated)

EOOSCombination Flow

(% of 0 25 1 <30 >30 40 55 65 85 100 :

rated) Operating Limit MCP 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 2.60 2.60 2.51 Base SLO 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.87 2.87 2.65

< 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 2.60 2.60 2.51 RPTOOS SLO 1.352 1.352 1.317 1.131 1.082 1.000

> 60 2.87 2.87 2.65

< 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 3.38 3.38 2.87 TBVOOS SLO 1.614 1.479 1.373 1.155 1.082 1.000

> 60 3.89 3.89 3.40 TABLE 10-10 AFTO Flow Dependent MCPR Limits MCPR(F) 30 OF < FWT DELTA <55 OF (BOC to EOC)

(Asymmetric Feedwater Heating)

(References 2 and 11)

Core Flow MCPR(F)

(% rated) Limit 0 1.735 30.0 1.561 79.0 1.275 110 1.275

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 25 of 63 Accordance with 10 CFR 2.390 TABLE 10-11 AFTO SLO Flow Dependent MCPR Limits MCPR(F) 30 OF < FWT DELTA <55 OF (BOC to EOC)

(Asymmetric Feedwater Heating)

(References 2 and 11)

Core Flow MCPR(F)

(% rated) Limit 0 1.766 30 1.591 79.0 1.306 110 1.306 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 per Reference 11. 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 10-12 must be simultaneously applied. Therefore, the SLO MAPLHGR multiplier is clamped at the value shown in Table 10-13 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 10-12 and 10-13 are valid for all fuel types in the core.

TABLE 10-12 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)

Valid for all Conditions except Single Loop (References 2 and 11)

AFTO Reduction Factor 20 OF < FWT DELTA:< 30 OF 0.980 30 OF < FWT DELTA < 40 OF 0.970 40 OF < FWT DELTA < 55 OF 0.960 TABLE 10-13 AFTO MAPLHGR Single Loop Operation (SLO) Reduction Factor (Asymmetric Feedwater Heating)

(References 2 and 11)

SLO AFTO Reduction Factor 20 OF < FW DELTA:< 30 OF 0.715 30 OF < FWT DELTA <40 OF 0.708 40 OF < FWT DELTA <55 OF 0.701

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 26 of 63 Accordance with 10 CFR 2.390 11.0 MODES OF OPERATION TABLE 11-1 Modes of Operation (Reference 2)

EOOS Options Operating Region(1 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 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 documents:

1. "General Electric Standard Application for Reactor Fuel," NEDE-2401 I-P-A-18, April 2011; and the U.S.

Supplement, NEDE-240 11-P-A- I 8-US, April 2011.

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. PECo-FMS-0001-A, "Steady-State Thermal Hydraulic Analysis of Peach Bottom Units 2 and 3 using the FIB WR Computer Code"
4. PECo-FMS-0002-A, "Method for Calculating Transient Critical Power Ratios for Boiling Water Reactors (RETRAN-TCPPECo)"
5. PECo-FMS-0003-A, "Steady-State Fuel Performance Methods Report"
6. PECo-FMS-0004-A, "Methods for Performing BWR Systems Transient Analysis"
7. PECo-FMS-0005-A, "Methods for Performing BWR Steady-State Reactor Physics Analysis"
8. PECo-FMS-0006-A, "Methods for Performing BWR Reload Safety Evaluations"
9. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications,"

NEDO-32465-A, August 1996.

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

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 27 of 63 Accordance with 10 CFR 2.390

13.0 REFERENCES

1. "Technical Specifications for Peach Bottom Atomic Power Station Unit 3," Docket No. 50-278, Appendix A to License No. DPR-56.
2. "Supplemental Reload Licensing Report for Peach Bottom Unit 3 Reload 18 Cycle 19," GNF Document No. 0000-0127-1963-SRLR, Revision 1, August 2011.
3. DELETED
4. DELETED
5. DELETED
6. DELETED
7. DELETED
8. Exelon Calculation PE-0173, Revision 1, "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."
9. DELETED
10. Exelon Calculation PE-0251, Revision IE, "PRNMS Setpoint Calculation."
11. "Peach Bottom Asymmetric Feedwater Temperature Operation Fuel Thermal Limits Evaluation Update,"

GENE Document No. GE-NE-0000-0057-0522-RO, January 2007.

12. DELETED
13. "Fuel Bundle Information Report for Peach Bottom Unit 3 Reload 18 Cycle 19," GNF Document No. 0000-0127-1963-FBIR-NP, Revision 0, August 2011.
14. DELETED
15. DELETED
16. DELETED
17. DELETED
18. Exelon Engineering Safety Analysis TODI ES 1100005 Revision 0, "Final Resolved OPL-3 Parameters for Peach Bottom Unit 3 Cycle 19," June 6, 2011.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in Page 28 of 63 Accordance with 10 CFR 2.390 Appendix A

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 29 of 63 Accordance with 10 CFR 2.390 Global Nuclear Fuel Global Nuclear Fuel A Joint Venture of GEToshibo, & Hitachi 0000-0127-1963-FBIR-NP Revision 0 August 2011 Non-ProprietaryInformation - Class I (Public)

Fuel Bundle Information Report for Peach Bottom Unit 3 Reload 18 Cycle 19 Copyright 2011 Global Nuclear Fuel - Americas, LLC All Rights Reserved

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 30 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF-A) solely for use by Exelon Corporation ("Recipient") in support of the operating license for Peach Bottom Unit 3 (the "Nuclear Plant"). The information contained in this report (the "Information") is believed by GNF-A to be an accurate and true representation of the facts known by, obtained by or provided to GNF-A at the time this report was prepared.

The only undertakings of GNF-A respecting the Information are contained in the contract between Recipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") and nothing contained in this document shall be construed as amending or modifying the Fuel Contract. The use of the Information for any purpose other than that for which it was intended under the Fuel Contract, is not authorized by GNF-A. In the event of any such unauthorized use, GNF-A neither (a) makes any representation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness of the Information or that such unauthorized use may not infringe privately owned rights, nor (b) assumes any responsibility for liability or damage of any kind which may result from such use of such information.

Information Notice This is a non-proprietary version of the document 0000-0127-1963-FBIR-P, Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( fl.

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 31 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0

1. Introduction and Summary This report, which supplements the Supplemental Reload Licensing Report, contains thermal-mechanical linear heat generation rate (LHGR) limits for the GNF-A fuel designs to be loaded into Peach Bottom Unit 3 -for Cycle 19. These LHGR limits are obtained from thermal-mechanical considerations only.

Approved GNF-A calculation models documented in Reference 1 were used in performing this analysis.

LHGR limits as a function of exposure for each bundle of the core design are given in Appendix A. The LHGR values provided in Appendix A provide upper and lower exposure dependent LHGR boundaries which envelope the actual gadolinia dependent LHGR limits. The LHGRs reported have been rounded to two places past the decimal.

Appendix B contains a description of the fuel bundles. Table B-1 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.

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 32 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0

2. References
1. General Electric StandardApplication for Reactor Fuel, NEDE-240 11-P-A- 18, April 2011; and the U.S. Supplement, NEDE-24011-P-A-18-US, April 2011.

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 33 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload I R - Class I (Puhlic) Revision 0 Appendix A UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB416-15GZ- I00T- I50-T6-2908 (GE 14C)

Bundle Number: 2908 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 1

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 concentrations occurring in this bundle design (8.0% Gd).

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 34 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Pihlic) Revision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 1ODG2B400-13GZ- I00T2-150-T6-2850-LUA (GNF2)

Bundle Number: 2850 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft

((I Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 2 GWd/MT (GWd/ST) kW/ft I'l _((j

______________________________))

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

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 35 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 UO2lGd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB414-14GZ- IOOT- 150-T6-3200 (GE 14C)

Bundle Number: 3200 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 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3Cl9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 36 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB417-15GZ- IOOT- 150-T6-3199 (GE I4C)

Bundle Number: 3199 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).

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 37 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 UO2iGd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-PI ODNAB408-15GZ- IOOT- 150-T6-3213 (GE 14C)

Bundle Number: 3213 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).

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 38 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE14-PIODNAB420-13GZ-IOOT-150-T6-3198 (GE14C)

Bundle Number: 3198 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).

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- Class I (Public) Revision 0 Reload 18 UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P I0DG2B395-14GZ- 100T2-150-T6-3991 (GNF2)

Bundle Number: 3991 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 7 GWd/MT (GWd/ST) kW/ft 7 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 40 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 1 - Class I (Public) Revision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB414-14GZ- IOOT-I 50-T6-3002 (GE 14C)

Bundle Number: 3002 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 8

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

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 41 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0 127-1963-FBIR-NP Reload 1 - Class I (Public) Revision 0 UO2lGd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB409-15GZ- I OT- 150-T6-2913 (GE 14C)

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 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 design (8.0% Gd).

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Bundle Number: 3003 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 Limit0 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 10 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C!9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 43 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB418-12GZ- IOOT- 150-T6-3005 (GE 14C)

Bundle Number: 3005 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" 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).

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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3Cl9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 44 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 0

Revision UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB412-14GZ- IOOT- 150-T6-3004 (GE 14C)

Bundle Number: 3004 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 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 12 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 16

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 45 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10DG2B399-13GZ- I 00T2-150-T6-3993 (GNF2)

Bundle Number: 3993 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' 3 GWd/MT (GWd/ST) kW/ft

((I

_________________________________ I))

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

Page 17

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 46 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P I0DG2B390-4G8.0/8G7.0/2G6.0- 100T2-150-T6-3992 (GNF2)

Bundle Number: 3992 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 14 GWd/MT (GWd/ST) kW/ft I((

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

Page 18

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 47 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P I 0DG2B404-13GZ- 100T2-150-T6-3994 (GNF2)

Bundle Number: 3994 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia 5

LHGR Limit '

GWd/MT (GWd/ST) kW/ft

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

Page 19

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 48 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 Appendix B Fuel Bundle Information Table B-1 Bundle Specific Information Bundle Enrichment Weight Weight Max Exposure Fuel Fuel Bundle Nm Enricmn (wtU of UO2 of U kaat G ad/MT Bundle Number (wt% U-235) (kg) (kg) 20 0 C 16 GWd/MT (GWd/ST)

GE 14-P 1ODNAB416-15GZ-IOOT- 150-T6-2908 (GE I4C)

GNF2-P10DG2B400-13GZ-100T2-150-T6-2850-LUA 2850 (GNF2)

GE 14-P1ODNAB414-14GZ-IOOT-150-T6-3200 (GE14C)

GE14-P1ODNAB417-15GZ-100T-150-T6-3199 (GEI4C)

GEI4-PIODNAB408-15GZ-1OOT- 150-T6-3213 (GE 14C)

GE14-P1ODNAB420-13GZ-100T-150-T6-3198 (GEI4C)

GNF2-P10DG2B395-14GZ-100T2-150-T6-3991 (GNF2)

GE 14-P 1ODNAB414-14GZ-IOOT-150-T6-3002 (GE14C)

GE 14-P 1ODNAB409-15GZ-100T-150-T6-2913 (GEI4C)

GE 14-P 1ODNAB403-15GZ-IOOT-150-T6-3003 (GE14C)

GEI4-PIODNAB418-12GZ-IOOT-150-T6-3005 (GE14C)

GE14-PIODNAB412-14GZ-100T-150-T6-3004 (GE14C)

GNF2-PI0DG2B399-13GZ-100T2-150-T6-3993 (GNF2)

GNF2-PI0DG2B390-4G8.0/8G7.0/2G6.0- I00T2-150- 3992 T6-3992 (GNF2)

GNF2-P1 0DG2B404-13GZ-100T2-150-T6-3994 (GNF2) I 16 Maximum lattice ko.for the most reactive uncontrolled state plus a (( 1] adder for uncertainties.

Page 20

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 49 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 11 Figure B-1 Enrichment and Gadolinium Distribution for EDB No. 2908 Fuel Bundle GE14-P1ODNAB416-15GZ-100T-150-T6-2908 (GE14C)

Page 21

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 50 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Puhlic) Revision 0 Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 2850 Fuel Bundle GNF2-P1ODG2B400-13GZ-100T2-150-T6-2850-LUA (GNF2)

Page 22

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 51 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 1 - Class I (Public) Revision 0

((

Figure B-3 Enrichment and Gadolinium Distribution for EDB No. 3200 Fuel Bundle GE14-P10DNAB414-14GZ-100T-150-T6-3200 (GE14C)

Page 23

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3Cl9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 52 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0

((

I]

Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 3199 Fuel Bundle GE14-P1ODNAB417-15GZ-100T-150-T6-3199 (GE14C)

Page 24

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 53 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0

((

Figure B-5 Enrichment and Gadolinium Distribution for EDB No. 3213 Fuel Bundle GE14-P1ODNAB408-15GZ-100T-150-T6-3213 (GE14C)

Page 25

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 54 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 11 Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 3198 Fuel Bundle GE14-PIODNAB420-13GZ-100T-150-T6-3198 (GE14C)

Page 26

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 55 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 3991 Fuel Bundle GNF2-P1ODG2B395-14GZ-100T2-150-T6-3991 (GNF2)

Page 27

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 56 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 Figure B-8 Enrichment and Gadolinium Distribution for EDB No. 3002 Fuel Bundle GE14-P1ODNAB414-14GZ-100T-150-T6-3002 (GE14C)

Page 28

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 57 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0

((

Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 2913 Fuel Bundle GE14-P1ODNAB409-15GZ-100T-150-T6-2913 (GE14C)

Page 29

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 58 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 1 - Class I (Public) Revision 0 Figure B-10 Enrichment and Gadolinium Distribution for EDB No. 3003 Fuel Bundle GE14-P1ODNAB403-15GZ-100T-150-T6-3003 (GE14C)

Page 30

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 59 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0

((

Figure B-11 Enrichment and Gadolinium Distribution for EDB No. 3005 Fuel Bundle GE14-PIODNAB418-12GZ-10OT-150-T6-3005 (GE14C)

Page 31

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 60 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 Figure B-12 Enrichment and Gadolinium Distribution for EDB No. 3004 Fuel Bundle GE14-P1ODNAB412-14GZ-100T-150-T6-3004 (GE14C)

Page 32

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 61 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 18 - Class I (Public) Revision 0 Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 3993 Fuel Bundle GNF2-P10DG2B399-13GZ-100T2-150-T6-3993 (GNF2)

Page 33

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3C19 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 62 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload 1X - Class I (Public* Revision 0 Reload 18 Revision 0 1[

1]

Figure B-14 Enrichment and Gadolinium Distribution for EDB No. 3992 Fuel Bundle GNF2-P1ODG2B390-4G8.0/8G7.0/2G6.0-100T2-150-T6-3992 (GNF2)

Page 34

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 6 P3CI9 Core Operating Limits Report Non-Proprietary Information Submitted in COLR Page 63 of 63 Accordance with 10 CFR 2.390 Peach Bottom Unit 3 Non-Proprietary Information 0000-0127-1963-FBIR-NP Reload IR - Class I (Public) Revision 0 Figure B-15 Enrichment and Gadolinium Distribution for EDB No. 3994 Fuel Bundle GNF2-P1ODG2B404-13GZ-100T2-150-T6-3994 (GNF2)

Page 35

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