ML092790469

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Revision 5 to Core Operating Limits Report Reload 17, Cycle 18, Enclosure 2
ML092790469
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 09/24/2009
From: Donell A, Rubinaccio G
Exelon Generation Co, Exelon Nuclear
To:
Office of Nuclear Reactor Regulation
References
Download: ML092790469 (29)
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Enclosure 2 Core Operating Limits Report for Peach Bottom Atomic Power Station (PBAPS) Unit 3 Reload 17, Cycle 18, Revision 5 Non-Proprietary Version

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3CI8 Core Operating Limits Report Non-Proprietary Information Submitted In Page 1 of128 Accordance with 10 CFR 2.390 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 3 RELOAD 17, CYCLE 18 (This revision Is a complete re-write) 0 Prepared By: Date: 9/24/09 Adam C. Donell / G. Rubinaccio ESA Reviewer. Date:

A. Olson Independent Revicwer: z ;--) z ~e.Zknc/- Date:

Approved By: Date: ?-2.-o0

1. J. Tusar Station Qualified Reviewer: Date:______

J. f-olley,

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 2 of 28 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 11 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

27

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 3 of 28 Accordance with 10 CFR 2.390 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure - GEl4 7 Table 3-2 MAPLHGR Versus Average Planar Exposure - GNF2 7 Table 3-3 MAPLHGR Single Loop Operation (SLO) Reduction Factor 7 Table 4-1 Operating Limit Minimum Critical Power Ratio - GE 14 9 Table 4-2 Operating Limit Minimum Critical Power Ratio - GNF2 9 Table 4-3 Power Dependent MCPR(P) Limit Adjustments and Multipliers 10 Table 4-4 Flow Dependent MCPR Limits MCPR(F) 10 Table 5-1 Linear Heat Generation Rate Limits - GE14 U02 rods 11 Table 5-2 Linear Heat Generation Rate Limits - GNF2 U02 rods 11 Table 5-3 Linear Heat Generation Rate Limits - GE 14 Gadolinia rods 12 Table 5-4 Linear Heat Generation Rate Limits - GNF2 Gadolinia rods 12 Table 5-5 Power Dependent LHGR Multiplier LHGRFAC(P) 13 Table 5-6 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

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 4 of 28 Accordance with 10 CFR 2.390 Table 10-7 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 40F < FWT DELTA < 55F 21 Table 10-8 AFTO Operating Limit Minimum Critical Power Ratio - GE14 30F < FWT DELTA < 55F 23 Table 10-9 AFTO Operating Limit Minimum Critical Power Ratio - GNF2 30F < FWT DELTA < 55F 23 Table 10-10 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 30F < FWT DELTA _ 55F 24 Table 10-11 AFTO Flow Dependent MCPR Limits MCPR(F) 30F < FWT DELTA _ 55F 24 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. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 5 of 28 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 EOR End of Rated. The cycle exposure at which reactor power is equal to 100% (3514 MWth) with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.

FFWTR Final Feedwater Temperature Reduction 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 RCF Rated Core Flow RPTOOS Recirculation Pump Trip Out of Service SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation TBVOOS Turbine Bypass Valves Out of Service

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 6 of 28 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 18 (Reload 17):

  • 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 82.9% of rated core flow during full power (3514 MWt) operation
  • Increased Core Flow (ICF), up to 110% of rated core flow
  • End-of-Cycle Power Coastdown to a minimum power level of 40%
  • Final Feedwater Temperature Reduction (FFWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) to 900 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 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 References 2, 6, 7, 9, 15 and 17. The Allowable Values, documented in Reference 6, 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 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 1 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 18.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 7 of 28 Accordance with 10 CFR 2.390 3.0 MAPLHGR LIMITS 3.1 Technical Specification Section 3.2.1, 3.3.4.2, 3.4.1 and 3.7.6 3.2 Description The MAPLHGR limits (kW/ft) obtained from the emergency core cooling system (ECCS) analysis are provided in Tables 3-1 and 3-2. The MAPLHGR limits comprise a given fuel type as a function of average planar exposure. The MAPLHGR tables are used when hand calculations are required. All MAPLHGR values for each fuel type as a function of axial location and average planar exposure shall be less than or equal to the applicable MAPLHGR limits for the respective fuel and lattice types. These MAPLHGR limits are specified in Reference 2 and the process computer databank. The SLO MAPLHGR reduction factor is applied as shown in Table 3-3 per Reference 2. This value is based on the limiting GEl4 product line. 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 II 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 13.71 18.00 13.71 60.78 7.50 63.50 6.69 TABLE 3-3 MAPLHGR Single Loop Operation (SLO) Reduction Factor (Reference 2)

SLO Reduction Factor 0.73

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3CI8 Core Operating Limits Report Non-Proprietary Information Submitted in Page 8 of 28 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 GE14 is provided in Table 4-1. The Operating Limit MCPR (OLMCPR) for GNF2 is provided in Table 4-2. These 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).

Separate OLMCPR values are presented in Table 4-1 and Table 4-2 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 are provided in Table 4-3. Table 4-3 is valid for a maximum temperature reduction of 90 'F for FWTR operation. The flow-dependent MCPR limits are provided in Table 4-4. The impact of AFTO on MCPR is addressed in Section 10.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 9 of 28 Accordance with 10 CFR 2.390 TABLE 4-1 Operating Limit Minimum Critical Power Ratio - GE14 (Reference 2)

SCRAM Cycle Exposure Time < EOR- 2600 > EOR- 2600 EOOS Combination OptionM' MWd/ST MWd/ST B 1.33 1.38 BASE A 1.36 1.41 B 1.35 1.40 BASE SLO(2) A 1.38 1.43 B 1.38 1.44 TBVOOS A 1.41 1.47 B 1.40 1.46 TBVOOS SLO(2) A 1.43 1.49 B 1.38 1.46 RPTOOS A 1.49 1.63 B 1.40 1.48 RPTOOS SLO(2) A 1.51 1.65 TABLE 4-2 Operating Limit Minimum Critical Power Ratio - GNF2 (Reference 2)

SCRAM Cycle Exposure Time < EOR - 2600 > EOR - 2600 1

EOOS Combination Option* ) MWd/ST MWd/ST B 1.38 1.45 BASE A 1.43 1.50 B 1.40 1.47 BASE SLO(2) A 1.45 1.52 B 1.42 1.51 TBVOOS A 1.47 1.56 B 1.44 1.53 TBVOOS SLO12) A 1.49 1.58 B 1.40 1.50 RPTOOS A 1.50 1.60 B 1.42 1.52 RPTOOS SLO( 2 ) A 1.52 1.62

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

(2) For single-loop operation, the MCPR operating limit is 0.02 greater than the two loop limit per Reference 2.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 10 of 28 Accordance with 10 CFR 2.390 TABLE 4-3 Power Dependent MCPR(P) Limit Adjustments And Multipliers (Symmetric Feedwater Heating)

(References 2 and 17)

Core Core Thermal Power (% of rated)

EGOS Combination Flow(% 0 25 <30 >30 40 55 65 100 of rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp

< 60 2.45 2.45 2.36 Base < 60 1.340 1.286 1.256 1.131 1.000

> 60 2.70 2.70 2.50

< 60 2.47 2.47 2.38 Base SLO 1.340 1.286 1.256 1.131 1.000

> 60 2.72 2.72 2.52

<60 3.19 3.19 2.70 RPTOOS > 60 3.68 3.68 1.570 3.19______________ 1.440 1.335 1.131 1.000

< 60 3.21 3.21 2.72 RPTOOS SLO 1.570 1.440 1.335 1.131 1.000

> 60 3.70 3.70 3.21 TBVOOS <60 3.19 3.19 2.70 1.570 1.440 1.335 1.131 1.000

> 60 3.68 3.68 3.19 1

<60 3.21 3.21 2.72 TBVOOS SLO 1.570 1.440 1.335 1.131 1.000

> 60 3.70 3.70 3.21 TABLE 4-4 Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating)

(References 2, 7, and 15)

Core Flow MCPR(F)

(% rated) Limit 0.0 1.7073 79.06 I 1.250 110.0 1.250

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 11 of 28 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 U02 rod LHGR limits for GEl4 are provided in Table 5-1. The U02 rod LHGR limits for GNF2 are provided in Table 5-2. The Gadolinia rod LHGR limits for GE 14 are provided in Table 5-3. The Gadolinia rod LHGR limits for GNF2 are provided in Table 5-4. The LHGR values as a function of peak pellet exposure are provided in Reference 13. 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 References 2, 6, 7, and 17. The impact of AFTO on LHGR is addressed in Section 10.

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

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

GE14 0.00 13.40 14.51 13.40 57.61 i 8.00 63.50 5.00 TABLE 5-2 Linear Heat Generation Rate Limits - GNF2 U02 rods (Reference 13)

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

GNF2 ((

_________________________________ ))

((GNF Proprietary Information removed between double brackets))

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 12 of 28 Accordance with 10 CFR 2.390 TABLE 5-3 Linear Heat Generation Rate Limits - GE14 Gadolinia rods (Reference 13)

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

GE14 0.00 11.76 12.08 11.76 54.21 7.02 59.98 4.39 TABLE 5-4 Linear Heat Generation Rate Limits - GNF2 Gadolinia rods (Reference 13)

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

GNF2 ((

______________________________________ 1

((GNF Proprietary Information removed between double brackets))

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 13 of 28 Accordance with 10 CFR 2.390 TABLE 5-5 Power Dependent LHGR Multiplier LHGRFAC(P)

(Symmetric Feedwater Heating)

(References 2, 6, and 17)

Core Thermal Power (% of rated)

Core Flow _________________________________

EOOS Combination (% of rated) 0 25 <30 >30 40 155 65 1857 95 100 LHGRFAC(P) Multiplier Base<60 0.584 0.584 0.600 0.750 0.798 0.798 0.900 1.000 1.000 1.000

> 60 0.532 0.532 0.568 Base SLO <60 0.584 0.584 0.600 0.750 0.798 0.798 0.900 1.000 1.000 1.000

> 60 0.532 0.532 0.568

< 60 0.507 0.507 0.572 RPTOOS S 0 0.698 0.706 0.744 0.806 0.930 1.000 1.000

> 60 0.421 0.421 0.460 RPTOOS SLO60 0.507 0.507 0.572 0.698 0.706 0.744 0.806 0.930 1.000 1.000

> 60 0.421 0.421 0.460 TBVOOS :S6 .0 .0 0520.698 0.706 0.744 0.806 0.930 1.000 1.000

> 60 0.421 0.421 0.460

<60 0.507 0.507 0.572 TBVOOS SLO 0.698 0.706 0.744 0.806 0.930 1.000 1.000

> 60 0.42 1 0.42=1 0.460 TABLE 5-6 Flow Dependent LHGR Multiplier LHGRFAC(F)

(Symmetric Feedwater Heating)

(References 2, 6, and 7)

Core Flow (% of rated)

EOOS Combination 0 25 33.6 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.506 0.673 0.730 0.973 1.000 1.000 Single Loop 0.506 0.673 0.730 0.730 0.730 0.730

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 14 of 28 Accordance with 10 CFR 2.390 6.0 ROD BLOCK MONITOR SETPOINTS 6.1 Technical Specification Section 3.3.2.1 6.2 Description The RBM power-biased Analytical Limits, Allowable Values and MCPR Limits are provided in Table 6-1 based on Reference 4 with supporting documentation from References 2 and 10.

TABLE 6-1 Rod Block Monitor Setpoints (References 2, 4 and 10)

Power Level Analytical Limit(') Allowable Value(l) MCPR Limit 123.0% 121.2% < 1.70 (2)

LTSP < 1.40 3 118.0% 116.2% < 1.70 (2)

ITSP

< 1.403 113.2% 111.4% < 1.70 (2)

HTSP

< 1.40 3 1NOP N/A N/A < 1.70 (2)

__J1 I< 1.40 (3)

(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 (see References 2, 4 and 10).

(2) This is the MCPR limit (given THERMAL POWER is >28.4% and < 90%) below which the RBM is required to be OPERABLE (see References 2 and 4 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 References 2 and 4 and TS Table 3.3.2.1-1).

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 15 of 28 Accordance with 10 CFR 2.390 7.0 TURBINE BYPASS VALVE PARAMETERS 7.1 Technical Specification Section 3.7.6 7.2 Description The operability requirements for the steam bypass system are governed by Technical Specification 3.7.6. If the requirements cannot be met, the appropriate power and flow dependent limits for Turbine Bypass Valves Out-of-Service (TBVOOS) must be used. Additionally the OLMCPR for TBVOOS must be applied. The minimum number of bypass valves to maintain system operability is provided in Table 7-2 per References 2 and 18. Table 7-1 also includes other Turbine Bypass Valve response time parameters.

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 (References 2 and 18)

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

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 16 of 28 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. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 17 of 28 Accordance with 10 CFR 2.390 9.0 STABILITY PROTECTION OSCILLATION POWER RANGE MONITOR (OPRM) 9.1 Technical Specification Section 3.3.1, Table 3.3.1.1 -1 Function 2.f 9.2 Description The Cycle 18 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 16. 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)

Corresponding Maximum PBDA Trip Amplitude Confirmation Count Trip Setting 1.12 14 TABLE 9-2 OPRM PBDA Trip Settings - SLO(')

(Valid For SLO Conditions Only)

(Reference 2)

PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting 1.16 17 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. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 18 of 28 Accordance with 10 CFR 2.390 10.0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION (AFTO)

Asymmetric feedwater heating (resulting from removing a heater string, or individual feedwater heaters, from operation) is the result of the specific configuration of the feedwater lines at Peach Bottom. A reduction in heating in either the 'A' or the 'C' heater strings will result in a temperature mismatch between the feedwater flows entering the opposite sides of the reactor vessel. Asymmetric feedwater temperature operation (AFTO) is defined as operation in a feedwater heater/string configuration that results in a specified threshold difference as described in Reference 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 References 2, 6, 7, 11 and 17 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 'F. Once the temperature difference exceeds 20 'F the graduated penalties from Table 10-1 are applied to the thermal limits.

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

(Reference 11)

MFLCPR MFLPD/MAPRAT 40F < FWT DELTA < 55F 2% 4%

30F < FWT DELTA < 40F 2% 3%

20F < FWT DELTA < 30F No Penalty / Max Allowable 2%

OF < FWT DELTA < 20F No Penalty No Penalty / Max Allowable

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 19 of 28 Accordance with 10 CFR 2.390 TABLE 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTA <30F (Asymmetric Feedwater Heating)

(References 2, 6, 11 and 17)

Core Thermal Power (% of rated)

Core Flow________________________________

EOOS Combination (% of rated) 0 25 <30 >30 40 55 1 65 85 T-95 100 LHGRFAC(P) Multiplier

<0 0.572 0.572 0.588 Base 0.735 0.782 0.782 0.882 0.980 0.980 0.980

> 60 0.521 0.521 0.557 Base SLO <60 0.572 0.572 0.588 0.735 0.782 0.782 0.882 0.980 0.980 0.980

> 60 0.521 0.521 0.557 RPTOOS < 60 0.497 0.497 0,561 0.684 0.692 0.729 0.790 0.911 0.980 0.980

>60 0.413 0.413 0.451 1 RPTOOS SLO <60 0.497 0.497 0.56 1 0.684 0.692 0.729 0.790 0.911 0.980 0.980

>60 0.413 0.413 0.451 1 TBVOOS <60 0.497 0.497 0.561 0.684 0.692 0.729 0.790 0.911 0.980 0.980

> 60 0.413 0.413 0.451

<60 0.497 0.497 0.561 TBVOOSSLO 0.684 0.692 0.729 0.790 0.911 0.980 0.980

> 60 0.413 0.413 0.451 TABLE 10-3 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 30F < FWT DELTA < 40F (Asymmetric Feedwater Heating)

(References 2, 6, 11 and 17)

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 T 95 100 LHGRFAC(P) Multiplier

< 60 0.566 0.566 0.582 Base 0.728 0.774 0.774 0.873 0.970 0.970 0.970

>60 0.516 0.516 0.551

< 60 0.566 0.566 0.5 82 Base SLO 0.728 0.774 0.774 0.873 0.970 0.970 0.970

>60 0.516 0.516 0.551

ý60

<POS 0.492 0.492 0.555 0.677 0.685 0.722 0.782 0.902 0.970 0.970

> 60 0.408 0.408 0.446 1 155 RPTOOS SLO <60 0.492 0.492 0.555 0.677 0.685 0.722 0.782 0.902 0.970 0.970

>< 60 60 0.492 0.408 0.492 0.408 0.555 0.446 TBVOOS <0 0 0 0.677 0.685 0.722 0.782 0.902 0.970 0.970

> 60 0.408 0.408 0.446

< 60 0.492 0.492 0.555 TBVOOSSLO 0.677 0.685 0.722 0.782 0.902 0.970 0.970

> 60 0.408 0.408 0.446

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 20 of 28 Accordance with 10 CFR 2.390 TABLE 10-4 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 40F < FWT DELTA < 55F (Asymmetric Feedwater Heating)

(References 2, 6, 11 and 17)

Core Thermal Power (% of rated)

CominaionCore Flow EOOS Combination (% of rated) 0 25 1 <30 1 >30 1 40 1 55 1 65 1 85 T 95 100 LHGRFAC(P) Multiplier

<60 0.561 0.561 0.576 Base 0.720 0.766 0.766 0.864 0.960 0.960 0.960

>60 0.511 0.511 0.545 Base SLO 60 0.561 0.561 0.576 0.720 0.766 0.766 0.864 0.960 0.960 0.960

>60 0.511 0.511 0.545 RPTOOS <60 0.487 0.487 0.549 0.670 0.678 0.714 0.774 0.893 0.960 0.960

> 60 0.404 0.404 0.442 RPTOOS SLO <60 0.487 .0.487 0.549 0.670 0.678 0.714 0.774 0.893 0.960 0.960 TBVOOS <60 0.487 0.487 0.549 0.670 0.678 0.714 0.774 0.893 0.960 0.960

> 60 0.404 0.404 0.442

< 60 0.487 0.487 0.549 TBVOOS SLO 0.670 0.678 0.714 0.774 0.893 0.960 0.960

> 60 0.404 0.404 0.442

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 21 of 28 Accordance with 10 CFR 2.390 TABLE 10-5 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTA < 30F (Asymmetric Feedwater Heating)

(References 2, 6, 7 and 11)

Core Flow (% of rated)

EOOS Combination 0 25 33.6 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.496 0.660 0.715 0.954 0.980 0.980 Single Loop 0.496 0,660 0.715 0.715 0.715 0.715 TABLE 10-6 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 30F < FWT DELTA < 40F (Asymmetric Feedwater Heating)

(References 2, 6, 7 and 11)

Core Flow (% of rated)

EOOS Combination 0 25 33.6 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.491 0.653 0.708 0.944 0.970 0.970 Single Loop 0.491 0.653 0.708 0.708 0.708 0.708 TABLE 10-7 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 40F < FWT DELTA <55F (Asymmetric Feedwater Heating)

(References 2, 6, 7 and 11)

Core Flow (% of rated)

EOOS Combination 0 25 33.6 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.486 0.646 0.701 0.934 0.960 0.960 Single Loop 0.486 0.646 0.701 0.701 0.701 0.701

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 22 of 28 Accordance with 10 CFR 2.390 MCPR LIMITS The OLMCPRs 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 Table 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 AUTO are provided in Table 10-11. The power and flow-dependent OLMCPR curves were obtained from References 2, 4, 7, 9, 15 and 17 and were adjusted with a 2% penalty for feedwater temperature difference greater than 30 'F as displayed in Table 10-1 per References 11 and 14. No MCPR penalties are required for asymmetric temperature differentials less than or equal to 30 'F.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 23 of 28 Accordance with 10 CFR 2.390 TABLE 10-8 AFTO Operating Limit Minimum Critical Power Ratio-GE14 30F < FWT DELTA < 55F (Asymmetric Feedwater Heating)

(References 2, 4, 7, 9 and 11)

SCRAM Cycle Exposure Time < EOR- 2600 > EOR- 2600 EOOS Combination Option(O MWd/ST MWd/ST B 1.36 1.41 BASE A 1.39 1.44 B 1.38 1.43 BASE SLO(2) A 1.41 1.46 B 1.41 1.47 TBVOOS A 1.44 1.50 B 1.43 1.49 TBVOOS SLO(2- A 1.46 1.52 B 1.41 1.49 RPTOOS A 1.52 1.66 B 1.43 1.51 RPTOOS SLO12) A 1.54 1.68 TABLE 10-9 AFTO Operating Limit Minimum Critical Power Ratio-GNF2 30F < FWT DELTA < 55F (Asymmetric Feedwater Heating)

(References 2, 4, 7, 9 and 11)

SCRAM Cycle Exposure Time < EOR- 2600 > EOR- 2600 EOOS Combination Optionm') MWd/ST MWd/ST B 1.41 1.48 BASE A 1.46 1.53 B 1.43 1.50 BASE SLO(2) A 1.48 1.55 B 1.45 1.54 TBVOOS A 1.50 1.59 B 1.47 1.56 TBVOOS SLO(2) A 1.52 1.61 B 1.43 1.53 RPTOOS A 1.53 1.63 B 1.45 1.55 RPTOOS SLO(2) A 1.55 1.65

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

(2) For single-loop operation, the MCPR operating limit is 0.02 greater than the two loop limit per Reference 2.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 24 of 28 Accordance with 10 CFR 2.390 TABLE 10-10 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 30F < FWT DELTA <55F (Asymmetric Feedwater Heating)

(References 2, 7, 9, 11, 14 and 17)

Core Core Thermal Power (% of rated) 0 EOOS Combination ofOrSted)ination__Flow Flow (% 125<30 1 >30 40 55 65 100 of rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp

< 60 2.50 2.50 2.41 Base < 1.340 1.286 1.256 1.131 1.000

> 60 2.75 2.75 2.55 Base SLO <60 2.52 2.52 2.43 1.340 1.286 1.256 1.131 1.000

> 60 2.77 2.77 2.57

< 60 3.25 3.25 2.75 RPTOOS 1.570 1.440 1.335 1.131 1.000

> 60 3.75 3.75 3.25

< 60 3.27 13.27 2.77 RPTOOS SLO < 1.570 1.440 1.335 1.131 1.000

> 60 3.77 3.77 3.27

< 60 3.25 3.25 2.75 TBVOOS < 1.570 1.440 1.335 1.131 1.000

> 60 3.75 3.75 3.25

< 60 3.27 3.27 2.77 TBVOOS SLO 1.570 1.440 1.335 1.131 1.000

> 60 3.77 3.77 3.27 TABLE 10-11 AFTO Flow Dependent MCPR Limits MCPR(F) 30F < FWT DELTA < 55F (BOC to EOC)

(Asymmetric Feedwater Heating)

(References 2, 7, 9, 11, 14 and 15)

Flow MCPR(F)

(% rated) Limit 0 1.741 79.06 1.275 110 1.275

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 25 of 28 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 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.

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

Valid For All Conditions Except Single Loop (References 2 and 11)

AFTO Reduction Factor 20F < FWT DELTA _<30F 0.980 30F < FWT DELTA:< 40F 0,970 40F < FWT DELTA < 55F 0.960 TABLE 10-13 AFTO MAPLHGR Single Loop Operation (SLO) Reduction Factor (Asymmetric Feedwater Heating)

(References 2 and 11)

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

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 26 of 28 Accordance with 10 CFR 2.390 11.0 MODES OF OPERATION TABLE 11-1 Modes of Operation (References 2, 7 and 12)

EOOS Options . Operating Region' Base, Option A or B Yes Base SLO, Option A or B Yes TBVOOS, Option A or B Yes TBVOOS SLO, Option A or B Yes RPTOOS, Option A or B Yes RPTOOS SLO, Option A or B Yes TBVOOS and RPTOOS, Option A or B No TBVOOS and RPTOOS SLO, Option A or B No 12.0 METHODOLOGY The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. "General Electric Standard Application for Reactor Fuel", NEDE-2401 1-P-A-16, October 2007; and the U.S.

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

2. "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Units 2 and 3", NEDC-32162P, Revision 2, March 1995.
3. PECo-FMS-0001-A, "Steady-State Thermal Hydraulic Analysis of Peach Bottom Units 2 and 3 using the FIBWR 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.

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

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 27 of 28 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 17 Cycle 18", GNF Document No.

0000-0094-9487-SRLR, Revision 0, August 2009.

3. "General Electric Standard Application for Reactor Fuel", NEDE-2401 1-P-A-16, October 2007; and the U.S.

Supplement NEDE-2401 1-P-A- 16-US, October 2007.

4. "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.
5. DELETED
6. "Peach Bottom Atomic Power Station Evaluation for Extended Final Feedwater Temperature Reduction of 900 F", NEDC-32707P, Supplement 1, May 1998.
7. "ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station", NEDC-32847P, June 1998.
8. PECO Calculation PE-0173, Revision 1, "Determination of Total Time Required to Initiate the Trip Signal to the EOC-RPT Circuit Breaker".
9. "Peach Bottom Atomic Power Station Units 2 and 3 Plant and Cycle Independent ARTS Thermal Limits Analysis", NEDC - 32162P, Supplement 1, Revision 0, August 2001.
10. PECO Calculation PE-025 1, Revision 1, "Power Range Neutron Monitoring System Setpoint Calculations, Peach Bottom Atomic Power Station Units 2 and 3".
11. "Peach Bottom Asymmetric Feedwater Temperature Operation Fuel Thermal Limits Evaluation Update",

GE-NE-0000-0057-0522-RO, January 2007.

12. "GE14 Fuel Design Cycle-Independent Analyses for Peach Bottom Atomic Power Station Units 2 & 3,"

GENE L12-00880-00-01P, September 2000.

13. "Fuel Bundle Information Report for Peach Bottom Unit 3 Reload 17 Cycle 18", GNF Document No. 0000-0094-9487-FBIR, Revision 0, August 2009.
14. CR 00171805, AFTO ARTS thermal limit penalties not applied above 100% CTP.
15. "Letter from F. T. Bolger to C. P. Collins, "Removal of MCPR(F) Low Flow Correction in NEDC-32847P", February 4, 2002.
16. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications", NEDO-32465-A, August 1996.
17. "Peach Bottom 2 and 3 Off-Rated Analyses Below the PLU Power Level", GE-NE-0000-0041-8205-RO, August 2005.

Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 5 P3C18 Core Operating Limits Report Non-Proprietary Information Submitted in Page 28 of 28 Accordance with 10 CFR 2.390

18. "Final Resolved OPL-3 Parameters for Peach Bottom Unit 3 Cycle 18", TODI ES0900013, August 11, 2009.
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