ML11325A389
| ML11325A389 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  (DPR-044) |
| Issue date: | 10/31/2011 |
| From: | Stratton S Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML11325A389 (61) | |
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CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 2 RELOAD 18, CYCLE 19 (Ruisaio bars used to indcate cbangs)
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Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 7 P2C19 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. 7 P2C 19 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 - GEl4 and GNF2 7
Table 4-1 Operating Limit Minimum Critical Power Ratio - GE14 9
Table 4-2 Operating Limit Minimum Critical Power Ratio - GNF2 10 Table 4-3 Power Dependent MCPR(P) Limit Adjustments and Multipliers 1
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 BOTTOM 2 Rev. 7 P2C19 Core Operating Limits Report Page 4 of 64 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 22 Table 10-9 AFTO Operating Limit Minimum Critical Power Ratio - GNF2 > 30F FWT DELTA 23 Table 10-10 AFTO Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) > 30F FWT DELTA 24 Table 10-11 AFTO Flow Dependent MCPR Limits MCPR(F) > 30F FWT DELTA 24 Table 10-12 AFTO SLO Flow Dependent MCPR Limits MCPR(F) > 30F FWT DELTA 24 Table 10-13 AFTO MAPLHGR Reduction Factor 25 Table 10-14 AFTO MAPLHGR Single Loop Operation (SLO) Reduction Factor 25 Table 11-I Modes of Operation 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. 7 Page 5 of 64 II AFTO ARTS BASE BOC DTSP EOOS EOC EOR FFWTR FWHOOS FWT HTSP ICF ITSP LHGR LHGRFAC(F)
LHGRFAC(P)
MCPR(F)
MELLLA OLMCPR OPRM PBDA RPTOOS 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 Cycle 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.
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 Single Loop Operation Turbine Bypass Valves Out of Service
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 7 P2C1 9 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 82.8% of rated core flow during full power (3514 MWt) operation Increased Core Flow (ICF), up to 110% of rated core flow End-of-Cycle Power Coastdown to a minimum power level of 40%
Feedwater Heaters Out of Service (FWHOOS) to 550 F temperature reduction Final Feedwater Temperature Reduction (FFWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) to 900 F temperature reduction maintaining < 100% load line (4th and 5th stage FFWTR)
Asymmetric Feedwater Temperature Operation (AFTO)
ARTS provides for power-and flow-dependent thermal limit adjustments and multipliers that allow for a more reliable administration of the MCPR and LHGR thermal limits. The OLMCPR for each fuel type is determined by the cycle-specific reload analyses in Reference 2. Rated LHGR values are obtained from the bundle-specific thermal-mechanical analysis.
Supporting documentation for the ARTS-based limits is provided in Reference 2.
The Allowable Values 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. 7 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 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 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 I
MAPLHGR Limit (GWD/ST)I (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 0.73
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 7 P2C 19 Core Operating Limits Report Page 8 of 64 Non-Proprietaiy Information Submitted in Accordance with 10 CFR 2.390 4.0 MCPR LIMITS 4.1 Technical Specification Section 2.1.1.2, 3.2.2, 3.3.4.2, 3.4.1 and 3.7.6 4.2 Description The Operating Limit MCPR (OLMCPR) for each fuel type is provided in Tables 4-1 and 4-2. These values are determined by the cycle-specific fuel reload analyses in Reference 2. Control rod scram time verification is required as per Technical Specification 3.1.4, "Control Rod Scram Times". Tau, a measure of scram time performance to notch position 36 throughout the cycle, is determined based on the cumulative scram time test results. The calculation of Tau shall be performed in accordance with site procedures. Linear interpolation shall be used to calculate the OLMCPR value if Tau is between 0.0 (Tau Option B) and 1.0 (Tau Option A).
Separate OLMCPR values are presented in 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 VF
" TBVs Out-of-Service (per section 7.0), RPT In-Service (per section 8.0), and maximum FFWTR of 90 'F
" TBVs In-Service (per section 7.0), RPT Out-of-Service (per section 8.0), and maximum FFWTR of 90 'F The ARTS-based power-dependent MCPR limits are provided in Table 4-3. Table 4-3 is valid for a maximum temperature reduction of 90 'F for FFWTR operation. The flow-dependent MCPR limits are provided in Tables 4-4 and 4-5. Table 4-4 is valid for dual loop operating conditions with symmetric feedwater temperature operation and Table 4-5 is valid for single loop operating conditions with symmetric feedwater temperature operation. The impact of AFTO on MCPR is addressed in Section 10. Tables 4-3, 4-4, and 4-5 are applicable to both GE14 and GNF2 fuel type.
Exelon Nuclear - Nuclear Fuels P2CI 9 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 7 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 13 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(')
TBVOOS A
1.48(9) 1.50 B
A 1.48 1.54 B
1.48(10) 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 P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 7 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 SLO(4)
A 1.49 1.57 B
1.48(')
1.52 TBVOOS A
1.50 1.57 B
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)
(2)
(3)
(4)
(5)
(6)
When Tau does not equal 0 or 1, use linear interpolation.
Analyzed DLO Option B OLMCPR is 1.40 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.
Analyzed DLO Option A OLMCPR is 1.45 per Reference 2, 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 of 1.48 to obtain a corresponding DLO OPRM setpoint of 1.13.
Analyzed DLO Option B OLMCPR is 1.45 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.13.
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 P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 7 Page II 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 Flow (%
0 25 1 <30
>30 1 40 55 1 65 85 100 of 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 2.56 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 TBVOOS
<60 3.28 3.28 2.78 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 P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 7 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 5-1 and 5-2. The ARTS-based LHGR power-dependent multipliers are provided in Table 5-3. Table 5-3 is valid for a maximum temperature reduction of 90' F for FFWTR operation. The flow-dependent multipliers are provided in Table 5-4 as a function of the number of recirculation loops in operation. The SLO LHGR multiplier is 0.73 and is accounted for in Table 5-4. The power-and flow-dependent LHGR multipliers were obtained from Reference 2. Tables 5-3 and 5-4 are applicable to both GE14 and GNF2 fuel type. The impact of AFTO on LHGR is addressed in Section 10.
TABLE 5-1 Linear Heat Generation Rate Limits - U02 rods (Reference 11)
Fuel Type LHGR Limit GE 14 See Appendix A GNF2 See Appendix A TABLE 5-2 Linear Heat Generation Rate Limits - Gad rods (Reference 11)
Fuel Type LHGR Limit GE14 See Appendix A GNF2 See Appendix A
Exelon Nuclear - Nuclear Fuels P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 7 Page 13 of 64 TABLE 5-3 Power Dependent LHGR Multiplier LHGRFAC(P)
(Symmetric Feedwater Heating)
(Reference 2)
Core Thermal Power (% of rated)
EOOSCominaionCore Flow ___________________________
EOOSCombination rated 0
25
<30 I30 1 40 55 65 185 1100 LHGRFAC(P) Multiplier Base
- 60 0.516 0.516 0.535 0.750 0.756 0.771 0.817 0.959 1.000
>60 0.516 0.516 0.535
<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 RPTOOS
- 560 0.516 0.516 0.535 0.750 0.756 0.771 0.817 0.959 1.000
>60 0.516 0.516 0.535 RPTOOS 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
<60 0.4216 0.4216 0.482 TBVOOSSLO 0.640 0.655 0.714 0.817 0.930 1.000
> 60 0.414 0.414 0.442244
<60 0.421 0.421 0.482 TBVOOSSLO 0.640 0.655 0.714 0.817 0.930 1.000
>60 0.414 0.414 0.424 TABLE 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)
(Symmetric Feedwater Heating)
(Reference 2)
Core Flow (% of rated)
EOOS Combination 0
30 33.6 1
70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.506 0.706 0.730 0.973 1.000 1.000 Single Loop 0.506 0.706 0.730 0.730 0.730 0.730 I
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. 7 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(l)
Allowable Value(')
124.0%
< 1.70 (2)
< 1.403 ITSP 121.0%
119.2%
< 1.70 (2)
< 1.40 (3)
HTSP 116.0%
114.2%
< 1.70 (2)
< 1.40 )
MNOP 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 P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 7 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. 7 P2C 19 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 P2CI 9 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 7 Page 17 of 64 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 Table 9-1 and 9-2. These values are based on the cycle specific analysis documented in Reference 2. The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system, Reference 13.
The OPRM Growth Rate Algorithm (GRA) and Amplitude Based Algorithm (ABA) trip settings for dual loop and single loop can be found in the Power Range Neutron Monitoring Configuration Control Documents (SPID's) G-080-VC-234 through 237 (Unit-2).
TABLE 9-1 OPRM PBDA Trip Settings (Valid for All Conditions)
(Reference 2)
PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting 1.13 15 TABLE 9-2 OPRM PBDA Trip Settings - SLO()
(Valid For SLO Conditions Only)
(Reference 2)
PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting 1.15 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. 7 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 (AFRO)
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 (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 Tables 5-3 and 5-4 of Section 5, LHGR Limits, and were adjusted with the appropriate penalties displayed in Table 10-1 as per Reference 10. 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 GEl4 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 DELTA < 55F 2%
4%
30F < FWT DELTA < 40F 2%
3%
20F < FWT DELTA < 30F No Penalty 2%
OF < FWT DELTA < 20F No Penalty No Penalty
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. 7 Page 19 of 64 TABLE 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTA <30F (Asymmetric Feedwater Heating)
Core Thermal Power (% of rated)
Core Flow _____________________________
EOOS Combination (% of rated) 0 25 1 <30 1>30 1 40 55 1 65 1 85 1 95 1 100
____LHGRFAC(P)
Multiplier
< 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
<PTOS60 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 RPTOOS 60 0.506 0.506 0.524
.735 0.741 0.756 0.801 0.940 0.967 0.980
> 60 0.506 0.506 0.5241'
< 60 0.413 0.413 0.472 TBVOOS 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 TBVOOS SLO 0.627 0.642 0.700 0.801 0.911 0.957 0.980
> 60 0.406 0.406 0.416 TABLE 10-3 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 30F < FWT DELTA < 40F (Asymmetric Feedwater Heating)
Core Thermal Power (% of rated)
Core Flow_______________________________
EOOS Combination (% of rated) 0 25 1 <30 1>30 1 40 1 55 1 65 1 85 1 95 1 100
_ 60 0.501 0.5010.519LHGRFAC(P) Multiplier fl 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
<60 0.501 0.501 0.519 Base SLO 0.728 0.733 0.748 0.792 0.930 0.957 0.970
>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 0.957 0.970
>60 0.501 0.501 0.519
<60 0.501 0.501 0.5 19 RPTOOS SLO 0.728 0.733 0.748 0.792 0.930 0.957 0.970
>60 0.501 0.501 0.519 TBVOOS 60 048 048
.680.621 0.635 0.693 0.792 0.902 0.947 0.970
> 60 0.402 0.402 0.411 1
11 1
<*60 0.408 0.408 0.468 TBVOOSSLO 0.621 0.635 0.693 0.792 0.902 0.947 0.970
> 60 0.402 0.402 0.411
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. 7 Page 20 of 64 TABLE 10-4 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 40F < FWT DELTA < 55F (Asymmetric Feedwater Heating)
Core Thermal Power (% of rated)
Core Flow_______________________________
EOOS Combination (% of rated) 0 25 1<30 1>30 140 55 165 85 1 95 100 LHGRFAC(P) Multiplier
<60 0.495 0.495 0.5 14 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 0.514 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 0.514 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 S 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 0.6 14 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. 7 Page 21 of 64 TABLE 10-5 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTA < 30F (Asymmetric Feedwater Heating)
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)
Core Flow (% of rated)
EOOS Combination 0
30 33.60 1
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)
Core Flow (% of rated)
EOOS Combination 0
30 33.60 1
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 P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 7 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 Tables 4-1 through 4-5 of Section 4, MCPR Limits, 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)
SCRAM Cycle Exposure Time
< EOR - 3400
> EOR - 3400 EOOS Combination Option°'
MWd/ST MWd/ST B
1.51 1.51 BASE A
1.51 1.51 B
1.51 1.51 BASE SLO A
1.51 1.51 B
1.51 1.51 TBVOOS A
1.51 1.53 B
1.51 1.54 TBVOOSSLO A
1.51 1.57 B
1.51 1.51 RPTOOS A
1.54 1.68 B
1.51 1.55 RPTOOS SLO A
1.58 1.72 (1) When Tau does not equal 0 or 1, use linear interpolation.
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. 7 Page 23 of 64 I
TABLE 10-9 AFTO Operating Limit Minimum Critical Power Ratio-GNF2 > 30F FWT DELTA (Asymmetric Feedwater Heating)
SCRAM Cycle Exposure Time
< EOR-3400
> EOR-3400 EOOS Combination Option°')
MWd/ST MWd/ST B
1.51 1.51 BASE A
1.51 1.56 B
1.51 1.55 BASE SLO A
1.52 1.60 B
1.51 1.55 TBVOOS A
1.53 1.60 B
1.57 1.64 B
1.51 1.54 RPTOOS A
1.55 1.64 B
1.51 1.58 RPTOOS SLO A
1.59 1.68 (1)
When Tau does not equal 0 or 1, use linear interpolation.
I
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. 7 Page 24 of 64 TABLE 10-10 AFrO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) > 30F FWT DELTA (Asymmetric Feedwater Heating)
Core Core Thermal Power (% of rated)
EOOS Combination Flow (%
0 j25 < 3 0
>30 140 55 165 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 BaseSLO 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)
Flow MCPR(F)
(% rated)
Limit 0.0 1.735 79.0 1.275 110.0 1.275 TABLE 10-12 AFFO SLO Flow Dependent MCPR Limits MCPR(F) > 30F FWT DELTA (BOC to EOC)(Asymmetric Feedwater Heating)
Flow MCPR(F)
(% rated)
Limit 0.0 1.776 79.0 1.316 110.0 1.316 III
Exelon Nuclear-Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 7 P2C19 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 AFTO multiplier in Table 10-13 must be applied to the SLO multiplier in Table 3-3 of Section 3, MAPLHGR Limits.
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 GEl4 and GNF2 fuel type per References 8 and 10.
TABLE 10-13 AFrO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)
Valid For All Conditions Except Single Loop 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)
SLO AFTO Reduction Factor 20F < FWT DELTA _< 30F 0.715 30F < FWT DELTA < 40F 0.708 j.40F < FWT DELTA:< 55F 0.701
Exelon Nuclear - Nuclear Fuels P2C19 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. 7 Page 26 of 64 TABLE 11-1 Modes of Operation (Reference 2)
Operating Region (Including AFTO EOOS Options and/or FFWTR)
Base, Option A or B Yes Base SLO, Option A or B Yes TBVOOS, Option A or B Yes TBVOOS SLO, Option A or B Yes RPTOOS, Option A or B Yes RPTOOS SLO, Option A or B Yes TBVOOS and RPTOOS, Option A or B No TBVOOS and RPTOOS SLO, Option A or B No 12.0 METHODOLOGY The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:
- 1. "General Electric Standard Application for Reactor Fuel," NEDE-2401 I-P-A-18, April 2011 and U.S. Supplement NEDE-2401 1-P-A-18-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.
"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.
Not Used
- 4.
Not Used
- 5.
Not Used
Exelon Nuclear - Nuclear Fuels P2C19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390
- 6.
Not Used COLR PEACH BOTTOM 2 Rev. 7 Page 27 of 64 I
- 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. I 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-0251, 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 1E dated 8/25/11.
- 10. General Electric Document GE-NE-0000-0057-0522-RO, "Evaluation Report for Peach Bottom Asymmetric Feedwater Temperature Operation Fuel Thermal Limits Evaluation Update", Revision 0, January 2007.
- 11. Global Nuclear Fuels Document 0000-01 10-4769-FBIR, "Fuel Bundle Information Report for Peach Bottom 2 RELOAD 18 CYCLE 19", Revision 1, August 2010.
- 12. Not Used
- 13. Not Used
- 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 P2CI 9 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR PEACH BOTTOM 2 Rev. 7 Page 28 of 64 Appendix A
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. 7 Appendix A GN ýF Global Nuclear Fuel A Joint Venture of GE, Toshiba, & Hitachi 0000-01 10-4769-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 P2C 19 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 7 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 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.
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.
Page 2 COLR Page 33 of 64
Exelon Nuclear - Nuclear Fules P2C19 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 7 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 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.
Reference 2 limits GNF2 peak pellet exposure (PPE) to ((
))1.
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. 7 Appendix A 0000-011 0-4769-FBIR-NP Revision I Non-Proprietary Information Class I
- 2. References
- 1. General Electric Standard Application for Reactor Fuel, NEDE-240 11-P-A-I16, October 2007; and the U.S. Supplement, NEDE-2401 I-P-A-16-US, October 2007.
2 GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), NEDC-33270P, Revision 3, March 2010.
Page 4 COLR Page 35 of 64
Exelon Nuclear - Nuclear Fules P2C 19 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. 7 Appendix A 0000-011 0-4769-FB IR-NP Revision 1 Non-Proprietary Information Class I Appendix A UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 10DNAB416-15GZ-I OOT-150-T6-2908 (GEl 4C)
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 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 1 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 P2C 19 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. 7 Appendix A 0000-0110-4769-FB IR-NP Revision 1 Non-Proprietary Information Class I Reload 18 Revision I UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB4 17-13G6,0-OOT-i 50-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. 7 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Cl.qsa I U02/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE14-P1ODNAB415-15GZ-1OOT-150-T6-2910 (GEl4C)
Bundle Number: 2910 Peak Pellet Exposure U0 2 LIIGR 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).
Page 7 COLR Page 38 of 64
Exelon Nuclear - Nuclear Fules P2C 19 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. 7 Appendix A 0000-0110-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE14-P1ODNAB416-15GZ-IOOT-150-T6-2911 (GEI4C)
Bundle Number: 2911 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00(0.00) 13.40 16.00 (1.4.51) 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 occuning 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. 7 Appendix A 0000-011 0-4769-FBIR-NP Revision I Non-Proprietary Information Class I U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB416-15GZ-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 (1.4.51) 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) 1.1.76 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. 7 Appendix A 0000-0110-4769-FB IR-NP Revision 1 Non-Proprietary Information Class I UO2 Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P IODNAB409-15GZ-1OOT-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 (1.4.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 6 GWd/MT (GWd/ST) kW/ft 0.00(0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 6 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).
Page 10 COLR Page 41 of 64
Exelon Nuclear - Nuclear Fules P2C 19 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. 7 Appendix A Non-Proprietary Information Class I 0000-0110-4769-FBIR-NP Revision 1 UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 1 0DG2B406-12G6.0- 100T2-150-T6-3337 (GNF2)
Bundle Number: 3337 Peak Pellet Exposure U02 LHGR Limit GWd/MT (GWd/ST) kW/ft
((
Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 7 GWdIMT (GWd/ST) kW/ft l[
Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [f I].
Page 11 COLR Page 42 of 64
Exelon Nuclear - Nuclear Fules P2C 19 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. 7 Appendix A 0000-011 10-4769-FB IR-NP Revision 1 Non-Proprietary Information Class I Reload 1.8 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10DG2B393-15GZ-100T2-150-T6-3334 (GNF2)
Bundle Number: 3334 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft
((
Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWdIMT (GWd/ST) kW/ft I[
_______________________________ ]
8 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((
I].
Page 12 COLR Page 43 of 64
Exelon Nuclear - Nuclear Fules P2C 19 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. 7 Appendix A 0000-0 1 10-4769-FBIR-NP Revision I Non-Proprietary Information Class I UO 21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB420-13GZ-1OOT-150-T6-3097 (GE 14C)
Bundle Number: 3097 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 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).
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. 7 Appendix A 0000-0110-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I UO 21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE14-P1ODNAB416-15GZ-10OT-150-T6-3098 (GEl4C)
Bundle Number: 3098 Peak Pellet Exposure UO2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00(0.00) 13.40 16.00 (1.4.51) 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 10 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 18 COLR PEACH BOT7OM 2 Rev. 7 Appendix A 0000-01.10-4769-FB IR-NP Revision 1 Non-Proprietary Information Class I UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1ODNAB411-15GZ-1OOT-150-T6-3099 (GE 14C)
Bundle Number: 3099 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWdIST) 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
" 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. 7 Appendix A 0000-0110-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I Reload 18 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10DG2B388-6G8.0/6G7.0/2G6.0-10012-150-T6-3336 (GNF2)
Bundle Number: 3336 Peak Pellet Exposure UM2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit12 GWd/MT (GWd/ST) kW/ft
((_____________________1 12 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [f 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. 7 Appendix A 0000-011 0-4769-FB IR-NP Revision I Non-Proprietary Information Class I UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-PIODG2B392-15GZ-100T2-150-T6-3335 (GNF2)
Bundle Number: 3335 Peak Pellet Exposure UO2 LHGR Limit GWd/MT (GWd/ST) kWlft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit1 3 GWd/MT (GWd/ST) kW/ft
![____________________
__________________________________ ]
13 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((
fl.
Page 17 COLR Page 48 of 64
Exelon Nuclear - Nuclear Fules P2C 19 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. 7 Appendix A Non-Proprietary Information Class I 0000-0110-4769-FBIR-NP Revision I UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 1 0DG2B392-15GZ-100T2-150-T6-3332 (GNF2)
Bundle Number: 3332 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 14 GWd/MT (GWd/ST) kW/ft 11____________________
__________________________________11 14 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((
1].
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. 7 Appendix A 0000-011 0-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I Appendix B Fuel Bundle Information Table B-I Bundle Specific Information Fuel Bundle Enrichment Weight Weight Max Exposure Fuel Bundle Num Enrichen
(
of U02 of U k, a at Ma Bundle Number (wt% U-235)
(kg)
(kg) 200C 1s GWd/MT (GWd/ST)
GE 14-P 1ODNAB416-15GZ-1OOT-150-T6-2908 (GE14C)
GE14-PlODNAB4!7-13G6.0-2909 1 OOT-150-T6-2909 (GE I 4C)
GE1.4-PI ODNAB415-15GZ-1OOT-150-T6-2910 (GE I4C)
GE 14-P 1ODNAB416-15GZ-IOOT-150-T6-2911 (GEI4C)
GEI4-PIODNAB416-15GZ-100T-150-T6-2912 (GE14C)
GE 14-P I ODNAB409-15GZ-2913 100T-150-T6-2913 (GE14C)
GNF2-P10DG2B406-12G6.0-3337 100T2-150-T6-3337 (GNF2)
GNF2-PI 0DG2B393-15GZ-100T2-150-T6-3334 (GNF2)
GE14-PIODNAB420-13GZ-IOOT-150-T6-3097 (GE14C)
GE 14-P 1ODNAB4 16-15GZ-100T-150-T6-3098 (GE 14C)
GEI4-P1ODNAB411-15GZ-1OOT-150-T6-3099 (GE 14C)
GNF2-P 10DG2B388-6G8.0/6G7,0/2G6.0-100T2-150-3336 T6-3336 (GNF2)
GNF2-PI 0DG2B392-15GZ-100T2-150-T6-3335 (GNF2)
GNF2-P 10DG2B392-15GZ-100T2-150-T6-3332 (GNF2) 15 Maximum lattice k, for the most reactive uncontrolled state plus a i[
11 adder for uncertainties.
Page 19 COLR Page 50 of 64
Exelon Nuclear - Nuclear Fules P2C 19 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. 7 Appendix A 0000-011 0-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I Reload 18 Class I
[I Figure B-I Enrichment and Gadolinium Distribution for EDB No. 2908 Fuel Bundle GE14-PIODNAB416-1-GZ-10OT-150-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 18 COLR PEACH BOTTOM 2 Rev. 7 Appendix A 0000-011 0-4769-FB IR-NP Revision 1 Non-Proprietary Information Class I 1]
Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 2909 Fuel Bundle GE14-P1ODNAB417-13G6.0-1OOT-150-T6-2909 (GE14C)
Page 21 COLR Page 52 of 64
Exelon Nuclear - Nuclear Fules P2C 19 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. 7 Appendix A 0000-011 0-4769-FB IR-NP Revision I Non-Proprietary Information Class I Figure B-3 Enrichment and Gadolinium Distribution for EDB No. 2910 Fuel Bundle GEI4-PIODNAB415-1.5GZ-OOT-150-T6-2910 (GE14C)
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. 7 Appendix A 0000-01 10-4769-FBIR-NP Revision I Non-Proprietary Information Class I
[I 1]
Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 2911 Fuel Bundle GEI4-PIODNAB416-15GZ-10OT-150-T6-291.1 (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 1.8 COLR PEACH BOTTOM 2 Rev. 7 Appendix A 0000-0110-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I Reload 1.8 Class I
((
Figure B-5 Enrichment and Gadolinium Distribution for EDB No. 2912 Fuel Bundle GEI4-PlODNAB416-15GZ-1OOT-150-T6-2912 (GE14C)
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. 7 Appendix A 0000-0110-4769-FBIR-NP Revision I Non-Proprietary Information Class I Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 2913 Fuel Bundle GEI4-P1ODNAB409-15GZ-IOOT-150-T6-2913 (GEI4C)
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. 7 Appendix A 0000-0110-4769-FBIR-NP Revision I Non-Proprietary Information Class I it 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 P2C 19 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 OI.R P.,EACH.OTT'OM2 Rev. 7.
Appendix A 0000-01 10-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I
[I 11 Figure B-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 Nan-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Peach Bottom Unit 2 Reload 18 COLR PEACH BOTTOM 2 Rev. 7 Appendix A 0000-0110-4769-FBIR-NP Revision I Non-Proprietary Information Class I 1[
Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 3097 Fuel Bundle GE14-P1ODNAB420-13GZ-IOOT-150-T6-3097 (GE14C)
Page 28 COLR Page 59 of 64
Exelon Nuclear - Nuclear Fules P2C 19 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. 7 Appendix A Non-Proprietary Information Class I 0000-0 110-4769-FB IR-NP Revision 1 It 1]
Figure B-10 Enrichment and Gadolinium Distribution for EDB No. 3098 Fuel Bundle GE14-P1ODNAB416-15GZ-100T-150-T6-3098 (GE14C)
Page 29 COLR Page 60 of 64
Exelon Nuclear - Nuclear Fules P2C 19 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. 7 Appendix A 0000-0110-4769-FBIR-NP Revision I Non-Proprietary Information Class I
((
))
Figure B-11 Enrichment and Gadolinium Distribution for EDB No. 3099 Fuel Bundle GE14-PIODNAB411-15GZ-IOOT-150-T6-3099 (GEl4C)
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. 7 Appendix A 0000-011 0-4769-FBIR-NP Revision 1 Non-Proprietary Information Class I
((
I]
Figure B-12 Enrichment and Gadolinium Distribution for EDB No. 3336 Fuel Bundle GNF2-P1ODG28388-6G8.0/6G7.0/2G6.0-100T2-150-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. 7 Appendix A 0000-01 10-4769-FBIIR-NP Revision 1 Non-Proprietary Information Class I
((
1]
Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 3335 Fuel Bundle GNF2-PIODG2B392-15GZ-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. 7 Appendix A 0000-011 10-4769-FB [R-NP Revision I Non-Proprietary Information Class I
((
))
Figure B-14 Enrichment and Gadolinium Distribution for EDB No. 3332 Fuel Bundle GNF2-PIODG2B392-15GZ-100T2-150-T6-3332 (GNF2)
Page 33 COLR Page 64 of 64