ML062700092

Issuance of the Core Operating Limits Report for Reload 16, Cycle 17, Revision 4

ML062700092
Person / Time
Site:	Peach Bottom
Issue date:	09/26/2006
From:	Cowan B Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML062700092 (23)

Text

Exelon Nuclear www exeioncorp corn 200 Exelon VJay Kennett Square,PA 19y+S TS 5.6.5.d September 26,2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Peach Bottom Atomic Power Station, Unit 2 Facility Operating License No. DPR- 44 NRC V

Subject:

Issuance of the Core Operating Limits Report for Reload 16, Cycle 17, Revision 4 Enclosed is a copy of the Core Operating Limits Report (COLR) for Peach Bottom Atomic Power Station (PBAPS), Unit 2, Reload 16, Cycle 17, Revision 4. Revision 4 of this report incorporates the revised cycle specific parameters resulting from the new core configuration being implemented during the PBAPS, Unit 2 refueling outage.

This COLR is being submitted to the NRC in accordance with PBAPS, Unit 2 Technical Specifications (TS) Section 5.6.5.d.

If you have any questions, please contact Tom Loomis (610-765-5510).

Very truly yours, Pamela B. Cowan Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC Enclosure cc: S. J. Collins, Regional Administrator, Region I, USNRC F. L. Bower, USNRC Senior Resident Inspector, PBAPS R. Guzman, Project Manager [PBAPS] USNRC J. Kim, Assistant Project Manager [PBAPS] USNRC

Exelon Nuclear NucIear Fuels COLR PEACH BOTTOM 2 Rw. 4 P2Ci7 Con! Operating Limits Report Page 1 of 22 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOLMICP O W R STATION UNIT 2 RELOAD 16, CYCLE 17 (This is a Complete Rewrite)

Reviewed By: AP  ? -

A. R. Psarcts Approved By: Date: QdQ';tO6 Station Qusli Reviewer: Dare:

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Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 2 of 22 Page 1 .O Terms and Definitions 4 2.0 General Information 5 3.0 MAPLHGR Limits 6 4.0 MCPR Limits 7 5 .O Linear Heat Generation Rate Limits 10 6.0 Rod Block Monitor Setpoints 12 7 .O Turbine Bypass Valve Parameters 13 8.0 EOC Recirculation Pump Trip (EOC-RPT) Operability 14 9.0 Stability Protection Oscillation Power Range Monitor (OPRM) 15 10.0 Asymmetric Feedwater Temperature Operation (AFTO) 16 11.0 Modes of Operation 21 12.0 Methodology 21 13.0 References 21

Exeion Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 3 of 22 Table 3-1 MAPLHGR Versus Average Planar Exposure-GE 14 6 Table 3-2 MAPLHGR Single Loop Operation (SLO) Reduction Factor 6 Table 4- 1 Operating Limit Minimum Critical Power Ratio-GE14 8 Table 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers 9 Table 4-3 Flow Dependent MCPR Limits MCPR(F) 9 Table 5-1 Linear Heat Generation Rate Limits - U02 rods 10 Table 5-2 Power Dependent LHGR Multiplier LHGFWAC(P) 11 Table 5-3 Flow Dependent LHGR Multiplier LHGRFAC(F) 11 Table 6-1 Rod Block Monitor Setpoints 12 Table 7-1 Turbine Bypass System Response Time 13 Table 7-2 Minimum Required Bypass Valves To Maintain System Operability 13 Table 9- 1 OPRM PBDA Trip Settings 15 Table 9-2 OPRM PBDA Trip Settings - SLO 15 TabIe 10-1 AFTO Power Dependent LHGR Multiplier LHGIWACO)) 16 Table 10-2 AFTO Flow Dependent LHGR Multiplier LHGRFACP) 17 Table 10-3 AFTO Operating Limit Minimum Critical Power Ratio-GE 14 18 Table 10-4 AFTO Power Dependent MCPR Limit Adjustments and Multipliers 19 Table 10-5 AFTO Flow Dependent MCPR Limits MCPR(F) 19 Table 10-6 AFTO MAPLHGR Reduction Factor 20 Table 10-7 AFTO MAPLHGR Single Loop Operation (SLO) Reduction Factor 20 Table 11- 1 Modes of Operation 21

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 4 of 22 1.0 Terms and Definitions AFT0 Asymmetric Feedwater Temperature Operation ARTS APRM and RBM Technical Specification Analysis BASE Defines two (2) loop operation with at least seven turbine bypass valves in service and the reactor recirculation pump trip system in service.

BOC Beginning Of Cycle DTSP Rod Block Monitor Downscale Trip Setpoint 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% (35 14 Mvirth) with recirculation system flow equal to loo%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.

FFWTR Final Feedwater Temperature Reduction moos 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 2 Rev. 4 P2C17 Core Operating Limits Report Page 5 of 22 2.0 General Information This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 2 Cycle 17 (Reload 16):

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 (LHCR)

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 0 EOC Recirculation Pump Trip (EOC-RPT) Parameters 0 Dual Loop Stability Protection - Oscillation Power Range Monitor (OPRM) Trip Setpoints 0 Single Loop Stability Protection - Oscillation Power Range Monitor (OPRM) Trip Setpoints 0 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 (MElLLL) down to 82.9% of rated core flow during full power (3514 MWt) operation Increased Gore 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 55" F temperature reduction Final Feedwater Temperature Reduction (FFWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) to 90"F temperature reduction maintaining I 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, 8, 9, 11, 18 and 20). The Allowable Values, documented in Reference (S), for feedwater temperature as a function of thermal power for both FWHOOS and E;EwTR are specified in the appropriate Peach Bottom procedures.

Also note that the following description of MAPLHGR, LHGR and MCPR limits pertain to - AFTO conditions. A separate description of AFT0 limits and their associated ARTS tables are located in Section 10.

Preparation of this report was performed in accordance with Exelon Nuclear procedures. This report is submitted in accordance with Technical Specification 5.6.5 of Reference (1) and contains all thermal limit parameters related to the implementation of the ARTS Improvement Program and Maximum Extended Load Line Limit Analyses (ARTS/MELLLA) for Peach Bottom Unit 2 Cycle 17.

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

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 6 of 22 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 References (2) and (16) and the process computer databank. The SLO MAPLHGR multiplier is applied as shown in Table 3-2 per Reference 2. This value is based on the limiting GE14 product line. The impact of AFT0 on MAPLHGR is addressed in Section 10.

TABLE 3-1 MAPLHGR Versus Average Planar Exposure-GE14 (Reference 2,16 and 24)

Average Planar Exposure MAPLHGR Limit TABLE3-2 MAPLHGR Single Loop Operation (SLO) Reduction Factor (Reference 2 and 24)

SLO Reduction Factor

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 7 of 22 4.0 MCPR LIMITS 4.1 Technical Specification Section 2.1.1.2,3.2.2,3.3.4.2,3.4.1and 3.7.6 4.2 Description The Operating Limit MCPR (OLMCPR) for each fuel type is provided in Table 4-1. 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.O (Tau Option A).

Separate OLMCPR values are presented in Table 4-1 for the following domains:

TBVs In-Service (seven or more in-service) and RPT In-Service, maximum FuI?TR of 90 OF TBVs Out-of-Service (three or more out-of-service) and RPT In-Service, maximum FWTR of 90 OF TBVs In-Service (seven or more in-service) and RPT Out-of-Service,maximum FWTR of 90 O F The ARTS-based power-dependent MCPR limits are provided in Table 4-2. Table 4-2 is valid for a maximum temperature reduction of 90 O F for EWTR operation. The flow-dependent MCPR limits are provided in Table 4-3. Table 4-3 is valid for all operating conditions with symmetric feedwater temperature operation. The impact of AFT0 on MCPR is addressed in Section 10.

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 8 of 22 TABLE 4-1 Operating Limit Minimum Critical Power Ratio-GE14 (Reference 2,4,9 and 11)

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

(*) For single-loop operation, the MCPR operating limit is 0.02 greater than the two loop value except when the Two Loop Operation MCPR operating limit is less than 1.38 (consistent with Reference I5 and 2).

(3) OLMCPR limit set by the Single Loop Operation (SLO) - Recirculation Pump Seizure Analysis.

(Reference I5 and 2)

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 Page 9 of 22 P2C17 Core Operating Limits Report TABLE4-2 Power Dependent MCPR(P) Limit Adjustments And Multipliers (Symmetric Feedwater Heating)

(Reference 2,4,9,11 and 20)

( P 1 .000 1 .000 1 .Ooo 1.000 TBVOOS SLO 1 .Ooo TABLE4-3 Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating)

(Reference 2,4,9,11, and 18)

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 10 of 22 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. The LHGR values as a function of peak pellet exposure are provided in Reference (16 and 23). The ARTS-based LHGR power-dependent multipliers are provided in Table 5-2. Table 5-2 is valid for a maximum temperature reduction of 90" F for EWTR operation. The flow-dependent multipliers are provided in Table 5-3 as a function of the number of recirculation loops in operation. The SLO LHGR multiplier is accounted for in Table 5-3. The power-and flow-dependent LHGR multipliers were obtained from References (4,8,9, I 1 and 20). The impact of AFT0 on LHGR is addressed in Section 10.

TABLE 5-1 Linear Heat Generation Rate Limits - U 0 2 rods (Reference 16 and 23)

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

All Fuel Types

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 11of 22 TABLE 5-2 Power Dependent LHGR Multiplier LHGRFAC(P)

(Symmetric Feedwater Heating)

(References 4,8,9,11 and 20)

Core Thermal Power (% of rated)

EOOS Combination Core Flow

(% of rated) 0 1 25 1 <30 I 230 I 40 I 55 I 65 I 85 I 95 I 100 dultig ier 0.798 0.900 1.OOo 1.000 1.OOo 0.798 0.900 1.000 1.000 1.OOo 0.744 0.806 0.930 1.OOO 1.000 0.744 0.806 3.930 1.000 1.OOo 0.744 0.806 9.930 1.OOO 1.OOo TBVOOS SLO 0.744 0.806 3.930 1.000 1.000 TABLE5-3 Flow Dependent LHGR Multiplier LHGRFAC(F)

(Symmetric Feedwater Heating)

(References 2,4,8,9 and 11)

Core Flow (% of rated)

EOOS Combination 0 25 33.6 70 80 110 LHGRFAC(F1 Multiplier k

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 12 of 22 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 per Reference (4) with supporting documentation in References (2), (7), and (12).

TABLE 6-1 Rod Block Monitor Setpoints (References 2,4,7 and 12)

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 COLR references 2,4 and 12).

(2)

This is the MCPR limit (given THERMAL POWER is &?8.4% and c 90%) below which the RBM is required to be OPERABLE (see COLR references 2 and 4 and TS Table 3.3.2.1-1).

13)

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

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 13 of 22 7.0 TURBINE BYPASS VALVE PARAMETERS

7. I 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),(5). (6), and (22). Table 7-1 also includes other Turbine Bypass Valve response time parameters.

TABLE 7-1 Turbine Bypass System Response Time (Reference 2,5,6 and 22)

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 TABLE7-2 Minimum Required Bypass Valves To Maintain System Operability (References 2,5,6 and 22)

Reactor Power

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 14 of 22 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 ( W O O S ) must be used. Additionally the OLMCPR for W O O S 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 E O C - W circuit breakers. Reference (10) provides the basis for the RPT response time.

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 15 of 22 9.0 STABILITY PROTECTION OSCILLATIONPOWER RANGE MONITOR (OPRM) 9.1 Technical Specification Section 3.3.1.2.F 9.2 Description The Cycle 17 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 19). The OPRM Growth Rate Algorithm (GRA) and Amplitude Based Algorithm ( M A ) trip settings for dual loop and single loop can be found in the Power Range Neutron Monitoring Configuration Control Documents (SPIDs) G-080-VC-234 through 237 (Unit-2).

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

(Reference 2)

TABLE9-2 OPRM PBDA Trip Settings - SLO (Valid For SLO Conditions Only)

(Reference 2 and 21)

I) The standard two loop operation OPRM Trip Settings specified in Table 9- 1 must be implemented prior to restarting the idle pump when exiting the SLO condition.

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 16 of 22 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 heatedstring configuration that results in a specified threshold difference as described in Reference 14. This threshold is a function of power and flow. The curve of the threshold values is incorporated in the station procedures that govern AFTO.

The ARTS-based LHGR power-dependent multipliers for AFTO operation are provided in Table 10-1. The flow-dependent multipliers for AFTO are provided in Tables 10-2 as a function of the number of recirculation loops in operation only. The power-and flow-dependent LHGR multipliers were obtained from References (2, 4, 8,9 and 20) and were adjusted with a 7% penalty as per Reference (13). The SLO multiplier and the AFT0 multiplier must be simultaneously applied.

TABLE 10-1 AFTO Power Dependent LHGR Multiplier LHGRFAC(P)

(Asymmetric Feedwater Heating)

(References 2,4,8,9,13 and 20)

I I LHGRl QC(P)Multiplier I I I 0.742 0.742 0.837 0.930 0.930 0.930 I I 0.742 0.742 10.837 10.930 10.930 0.930 0.657 0.692 0.750 0.865 0.930 0.930 0.657 0.692 0.750 0.865 0.930 0.930 I I I I I 0.657 0.692 0.750 0.865 0.930 0.930 I I I I I 0.657 0.692 0.750 0.865 0.930 0.930

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 17 of 22 TABLE 10-2 AFT0 Flow Dependent LHGR Multiplier LHGRFAC(F)

(AsymmetricFeedwater Heating)

(References 2,4,8,9 and 13)

EOOS Combination Dual Loop 0.470 0.626 0.679 0.905 0.930 0.930 Single Loop 0.470 0.626 0.679 0.679 0.679 0.679

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 18 of 22 The OLMCPR for each fuel type during asymmetric feedwater temperature operation is provided in Table 10-

3. The ARTS-based power-dependent MCPR limits for use during AFTO conditions are provided in Table 10-

4. The flow-dependent MCPR limits for AFTO are provided in Table 10-5. The power and flow-dependent OLMCPR curves were obtained from References (9, 11, 18 and 20) and were adjusted with a 4% penalty as per Reference (1 3) and ( 17).

TABLE 10-3 AFTO Operating Limit Minimum Critical Power Ratio-GE14 (Asymmetric Feedwater Heating)

(Reference 2,4,9,11 and 13)

(')

W e n 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 value except when the Two Loop Operation MCPR operating limit is less than I .38 (consistent with Reference 15 and 2). The AFTO multiplier must be included in this limit and therefore 1.44 is used to maintain compliance with the limit.

(3)

OLMCPR limit set by the Single Loop Operation (SLO) - Recirculation Pump Seizure Analysis.

(Reference 15 and 2)

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 19 of 22 TABLE 10-4 AFTO Power Dependent MCPR Limit Adjustments And Multipliers (Asymmetric Feedwater Heating)

(Reference 9,11,13,17 and 20) c60 3.34 3.34 2.83 TBVOOS SLO 1.570 1.440 1.335 1.131 1.om

>60 3.85 3.85 3.34 I TABLE 10-5 AFTO Flow Dependent MCPR Limits MCPR(F)

(BOC to EOC)

(Asymmetric Feedwater Heating)

(Reference 9,11,13,17,18)

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 20 of 22 A 7% penalty is applied to all MAPLHGR limits for all conditions under asymmetric feedwater temperature operation (AFTO) as per Reference (13). For single-loop operation, the AFT0 multiplier is also applied to the MAPLHGR limits, in Table 10-6. The SLO multiplier in Table 3-2 and the AFTO multiplier in Table 10-6 must be simultaneously applied. Therefore, the SLO MAPLHGR multiplier is clamped at the value shown in Table 10-7 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 10-6 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)

Valid For All Conditions Except Single Loop (Reference 2 and 13)

AFTO Reduction Factor TABLE 10-7 AFTO MAPLHGR Single Loop Operation (SLO) Reduction Factor (Asymmetric Feedwater Heating)

(Reference 2 and 13)

SLO AFTO Reduction

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 21 of 22 11.0 MODES OF OPERATION TABLE 11-1 Modes of Operation (Reference 2,9 and 15) 12.0 METHODOLOGY The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRG,specifically those described in the following document:

I . "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-15, September 2005 and U.S.

Supplement NEDE-240 1 1-P-A- 15-US, September 2005.

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 16, Cycle 17", GNF Document No.

oooO-0049-7088-SRLR, Revision 0, July 2006.

3. "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A- 15, September 2005 and U.S.

Supplement NEDE-24011-P-A-15-US, September 2005.

4. "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Unit 2 and 3", NEDC-32162P, Revision 2, March 1995.

5. Letter from R. M. Butrovich to H. J. Diamond, "Peach Bottom-2 Cycle 11 Turbine Bypass Valve Capacity Variation from Design Basis", January 9, 1995.

6. Letter from G. V. Kumar to G. C. Storey, "PBAPS Evaluation of Turbine Bypass Surveillance Requirements", January 19, 1995.

7. PECO Energy Calc. PM-0875, "GE NSSS Setpoints Required to Support Power Rerate."

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

Exelon Nuclear Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 4 P2C17 Core Operating Limits Report Page 22 of 22

8. Peach Bottom Atomic Power Station Evaluation for Extended Final Feedwater Temperature Reduction of 90 F,NEDC-32707P, Supplement 1, May 1998.

9. ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station, NEDC-32847P, June 1998.

10. PECO Calculation PE-0173, Determination of Total Time Required to Initiate the Trip Signal to the EOC-RPT Circuit Breaker.

11. 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.

12. PECO Calculation PE-0251, Revision 1, Power Range Neutron Monitoring System Setpoint Calculations, Peach Bottom Atomic Power Station Units 2 and 3.

13. Safety Review for Peach Bottom Atomic Power Station Units 2 and 3 Asymmetric Feedwater Temperature Operation, NEDC-32691P, Revision 0, May 1997.

14. ECR 02-00478, AsymmetricFeedwater Operation Implementation

15. GE14 Fuel Design Cycle-Independent Analyses for Peach Bottom Atomic Power Station Units 2 & 3, GENE L 12-00880-0-01P, September 2000

16. Fuel Bundle Information Report for Peach Bottom 2 Reload 16 Cycle 17, GNF Document No. oo00-0049-7088-FBIR, Revision 0, July 2006

17. CR 00171805, AFT0 ARTS thermal limit penalties not applied above 100% CTP

18. Letter from F. T. Bolger to C. P. Collins, Removal of MCPRO Low Flow Correction in NEDC-32847P, February 4,2002.

19. Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, NEDO-32465-A, August 1996.

20. Peach Bottom 2 and 3 Off-Rated Analyses Below the PLU Power Level, GE-NE-ooOo-0041-8205-R0, August 2005 2 1. Evaluation of SLO OPRM Setpoints for Peach Bottom Unit 2 Cycle 17, EC362177

22. OPL-3Form for Peach Bottom 2 Cycle 17,GNF DRF. ooOo-0050-1388, March 30,2006

23. Fuel Bundle Information Report for Peach Bottom 2 Reload 15 Cycle 16, GNF Document No.

0000-0025-6977-FBIR, Revision 0, August 2004 24.Supplemental Reload Licensing Report for Peach Bottom 2, Reload 15, Cycle 16, GNF Document No.

oooO-0025-6977-SRLR,Revision 0, August 2004.