ML17318A033

Issuance of the Core Operating Limits Report for Reload 21, Cycle 22

ML17318A033
Person / Time
Site:	Peach Bottom
Issue date:	11/13/2017
From:	Navin P D Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CCN: 17-94
Download: ML17318A033 (27)

Text

Exelon Generation November 13, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Unit 3 Renewed Facility Operating License No. DPR-56 NRG Docket No. 50-278 TS 5.6.5.d

Subject:

Issuance of the Core Operating Limits Report for Reload 21, Cycle 22 Enclosed is a copy of Revision 12 of the Core Operating Limits Report (COLA) for Peach Bottom Atomic Power Station (PBAPS) Unit 3 for Reload 21, Cycle 22. Revision 12 of this report incorporates the revised cycle specific parameters resulting from the new core configuration as a result of the PBAPS Unit 3 refueling outage. This COLR is being submitted to the NRG as required by the PBAPS, Unit 3 Technical Specifications (TS) Section 5.6.5.d. If you have any questions concerning this letter, please contact Ms. Stephanie J. Hanson at (717) 456-3756.

Patrick D. Navin Site Vice President Peach Bottom Atomic Power Station CCN: 17-94

Enclosure:

Unit 3 Core Operating Limits Report for Reload 21, Cycle 22, Revision 12 cc: Regional Administrator, Region I, USNRC (without attachment)

USNRC Senior Resident Inspector, PBAPS (without attachment)

Project Manager -PBAPS, USNRC (with attachment) R. R. Janati, Pennsylvania Bureau of Radiation Protection (without attachment)

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

Exelon Nuclear -Nuclear Fucb P3C22 C'orc Operating Limits Repon COLR PEACH BOTTOM 3 Rev. 12 Page I of26 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 3 RELOAD 21, CYCLE 22 (This revision is a complete re-write)

Prepared By: .-r-r . Tae Wook Ahn -Nuclear Fuels Prepared By: Reviewed By: ___

__ l£. _____ _ Matthew Miller -Reactor Engineering Reviewed By: Supplementary Review By: Independent Review By: Travis Bement Engineering Safety Analysis Patricia Henry -Cycle Management Lead -Ta_m_a-ra_S_t-at-he_s_ Nuclear Fuels A [)(/jJrri'P;J Approved By: ____ ___ 0_ "'0_0 ____ _ Armando Johnson -NF Senior Manager SQRBy: Date: 10/09/2017 D 10/9/2017 ate: ----Date: I0/10/1? Date: 10/9/17 Date: 10/9/2017 Date: 10/10/17 Date: _1_1 O_C_T_1_7 Date: /O /nj;'}

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 2 of 26 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 1 2 6.0 Rod Block Monitor Setpoints 1 4 7.0 Turbine Bypass Valve Parameters 1 5 8.0 EOC Recirculation Pump Trip (EOC

-RPT) Operability 1 6 9.0 Stability Protection 1 7 10.0 Asymmetric Feedwater Temperature Operation (AFTO) 1 9 11.0 Modes of Operation 2 4 12.0 Methodology 2 4 13.0 References 2 5 Appendix A (Power/Flow Operating Map for MELLLA+)

2 6 Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 3 of 26 Revision History Revision Description Revision 12 New issue for Cycle 22 Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 4 of 26 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure 7 Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier 7 Table 4-1 Operating Limit Minimum Critical Power Ratio 9 Table 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers 10 Table 4-3 Flow Dependent MCPR Limits MCPR(F) 1 1 Table 4-4 SLO Flow Dependent MCPR Limits MCPR(F) 1 1 Table 5-1 Linear Heat Generation Rate Limits

- UO2 rods 1 2 Table 5-2 Linear Heat Generation Rate Limits

- Gad rods 1 2 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 1 3 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) 1 3 Table 6-1 Rod Block Monitor Setpoints 1 4 Table 7-1 Turbine Bypass System Response Time 1 5 Table 7-2 Minimum Required Bypass Valves to Maintain System Operability 1 5 Table 8-1 Recirculation Pump Trip Response Time 1 6 Table 9-1 Automatic BSP Setpoints for the Scram Region 1 7 Table 9-2 Manual BSP Endpoints for Normal Feedwater Temperature 1 8 Table 9-3 Manual BSP Endpoints for Reduced Feedwater Temperature 1 8 Table 10-1 AFTO Thermal Limit Penalties 1 9 Table 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20

°F < FWT DELTA 55°F 20 Table 10-3 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20°F < FWT DELTA 55°F 20 Table 10-4 AFTO Operating Limit Minimum Critical Power Ratio 20

°F < FWT DELTA 55°F 21 Table 10-5 AFTO Power Dependent MCPR Limit Adjustments and Multipliers 22 MCPR(P) 20°F < FWT DELTA 55°F Table 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 20

°F < FWT DELTA 55°F 22 Table 10-7 AFTO MAPLHGR Reduction Factor 23 Table 11-1 Modes of Operation 24 Table 11-2 EOOS Options Included in 'Base' Conditions 24

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 5 of 26 1.0 Terms and Definitions ABSP Automatic Backup Stability Protection AFTO Asymmetric Feedwater Temperature Operation AFTO LFWH Asymmetric Feedwater Temperature Operation Loss

-of-Feedwater Heating APRM Average Power Range Monitor ARTS APRM and RBM Technical Specification Analysis BASE The "BASE" condition is defined by a group of individual operating conditions that are applicable to all Modes of Operation discussed in Section 11. The "BASE" condition includes the EOOS conditions provided in Table 11

-2 as well as operation with FWHOOS/FFWTR. BOC Beginning Of Cycle BSP Backup Stability Protection DSS-CD Detect and Suppress Solution

- Confirmation Density DTSP Rod Block Monitor Downscale Trip Setpoint EOC End 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% 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 FWT Feedwater Temperature HFCL High Flow Control Line 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(F) ARTS MCPR thermal limit flow dependent adjustments and multipliers MCPR(P) ARTS MCPR thermal limit power dependent adjustments and multipliers MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ Maximum Extended Load Line Limit Analysis Plus MSIVOOS Main Steam Isolation Valve Out of Service NCL Natural Circulation Line OLMCPR Operating Limit Minimum Critical Power Ratio PLUOOS Power Load Unbalance Out of Service PROOS Pressure Regulator Out of Service RBM Rod Block Monitor RDF Rated Drive Flow RPTOOS Recirculation Pump Trip Out of Service RTP Rated Thermal Power RWE Rod Withdrawal Error SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation TB SOOS Turbine Bypass System Out of Service TCV/TSVOOS Turbine Control Valve and/or Turbine Stop Valve Out of Service

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 6 of 26 2.0 General Information This report provides the following cycle

-specific parameter limits for Peach Bottom Atomic Power Station Unit 3 CYCLE 2 2 (RELOAD 21): 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 SLO MCPR adjustment Linear Heat Generation Rate (LHGR) ARTS LHGR thermal limit multipliers SLO LHGR multipliers Rod Block Monitor (RBM) allowable values and MCPR limits Turbine Bypass Valve parameters EOC Recirculation Pump Trip (EOC

-RPT) parameters Stability Protection 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. SLO, FWHOOS operation, and FFWTR operation are not permitted in the MELLLA+ Region as controlled by station procedures. For the MELLLA+ Region, a specific definition of FWHOOS is provided in Facility Operating License (FOL) Section 2.C(16).

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 MELLLA+ Region down to 83% of rated core flow during full power (3 951 MWt) operation (Appendix A)

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 55° F temperature reduction Final Feedwater Temperature Reduction (FFWTR) between End

-of-Rated (EOR) and End-of-Cycle (EOC) to 90° F temperature reduction (4 th and 5 th stage FWHOOS) Asymmetric Feedwater Temperature Operation ARTS provides for power and flow

-dependent thermal limit adjustments and multipliers that allow for a more reliable administration of the MCPR and LHGR thermal limits. The OLMCPR is determined by the cycle

-specific reload analyses in Reference 2. Rated LHGR values are obtained from the bundle

-specific thermal

-mechanical analysis. Supporting documentation for the ARTS

-based limits is provided in Reference 2.

The off-rated limits assumed in the ECCS

-LOCA analyses bound the cycle

-specific limits calculated for MELLLA+ operation.

The Allowable Values documented in Reference 5 for feedwater temperature as a function of thermal power for both FWHOOS and FFWTR are specified in the appropriate Peach Bottom procedures.

The Peach Bottom Unit 3 Cycle 22 core is comprised entirely of GNF2 fuel.

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 in Section 10. Preparation of this report was performed in accordance with Exelon Nuclear procedures. This report is provided to the NRC 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 MELLLA+ for Peach Bottom Unit 3 Cycle 2 2.

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 7 of 26 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 Table 3-1. The MAPLHGR limits comprise a given fuel type as a function of average planar exposure.

All MAPLHGR values for GNF2 as a function of axial location and average planar exposure shall be less than or equal to the applicable MAPLHGR limits for GNF2 fuel and lattice type. These MAPLHGR limits are specified in Reference 2 and the process computer databank.

The SLO MAPLHGR multiplier is provided in Table 3

-2 per Reference 2 and must be applied to the Table 3-1 limits when operating in SLO.

The impact o f AFTO on MAPLHGR is addressed in Section 10.0.

TABLE 3-1 MAPLHGR Versus Average Planar Exposure (Reference 2)

Average Planar Exposure (GW d/ST) MAPLHGR Limit (kW/ft) 0.0 13.78 17.52 13.78 60.78 7.50 63.50 6.69 TABLE 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2)

SLO Multiplier 0.73 Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 8 of 26 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 GNF2 fuel is provided in Table s 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 Table 4

-1 for the following conditions

• TB S In-Service (per Section 7.0), RPT In

-Service (per Section 8.0), PR/PLU In-Service, and maximum FFWTR of 90 F (a.k.a. "BASE")

• TBS Out-of-Service (per Section 7.0), RPT In

-Service (per Section 8.0), PR/PLU In-Service, and maximum FFWTR of 90 F

• TBS In-Service (per Section 7.0), RPT In-Service (per Section 8.0), PR/PLU Out-of-Service, and maximum FFWTR of 90 F

• TBS In-Service (per Section 7.0), RPT Out

-of-Service (per Section 8.0), PR/PLU In-Service, and maximum FFWTR of 90 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 F for FFWTR operation (bounding for FWHOOS operation). The flow

-dependent MCPR limits are provided in Table s 4-3 and 4-4. Table 4

-3 is valid for dual loop operating conditions with symmetric feedwater temperature operation and Table 4-4 is valid for single loop operating conditions with symmetric feedwater temperature operation.

The impact of AFTO on MCPR is addressed in Section 10

.0. For PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS conditions, the limits are listed in Section 10

.0, these values are bounding for non

-AFTO conditions.

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 9 of 26 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (Reference 2)

EOOS Combination SCRAM Time Option (1) Cycle Exposure

< EOR - 3915 MWd/ST > EOR - 3915 MWd/ST BASE B 1.40 1.42 B*(3) 1.38 1.41 A 1.48 1.50 BASE SLO(2) B 1.43 1.4 5 A 1.51 1.5 3 RPTOOS B 1.43 1.45 A 1.60 1.62 RPTOOS SLO(2) B 1.46 1.48 A 1.63 1.65 PR/PLUOOS B 1.40 1.42 A 1.48 1.50 PR/PLUOOS SLO(2) B 1.43 1.45 A 1.51 1.53 TBSOOS B 1.44 1.47 A 1.53 1.56 TBSOOS SLO (2) B 1.47 1.50 A 1.56 1.59 (1) When Tau does not equal 0 or 1, use linear interpolation.

(2) For single

-loop operatio n, the MCPR operating limit is 0.03 higher than the two loop value (Reference 2).

(3) Limit is only applicable if it i s confirmed that a 45ms or greater delay exists between the time of the first TCV movement and the time of first TSV movement following a turbine trip; this may be selected per applicable station procedures.

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 10 of 26 TABLE 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers (Symmetric Feedwater Heating)

(Reference

2) EOOS Combination Core Flow (% of rated) Core Thermal Power (% of rated) 0 2 3 <26.7 26.7 40 55 65 85 100 Operating Limit MCPR Operating Limit MCPR Multiplier, Kp Base < 60 2.67 2.67 2.60 1.392 1.288 1.237 1.130 1.067 1.000 > 60 2.99 2.99 2.83 Base SLO < 60 2.70 2.70 2.63 1.392 1.288 1.237 1.130 1.067 1.000 > 60 3.02 3.02 2.86 RPTOOS < 60 2.67 2.67 2.60 1.392 1.288 1.237 1.130 1.067 1.000 > 60 2.99 2.99 2.83 RPTOOS SLO

< 60 2.70 2.70 2.63 1.392 1.288 1.237 1.130 1.067 1.000 > 60 3.02 3.02 2.86 PR/PLUOOS < 60 2.67 2.67 2.60 1.392 1.288 1.237 1.210 1.147 1.000 > 60 2.99 2.99 2.83 PR/PLUOOS SLO

< 60 2.70 2.70 2.63 1.392 1.2 88 1.237 1.210 1.147 1.000 > 60 3.02 3.02 2.86 TBSOOS < 60 3.64 3.64 3.25 1.399 1.323 1.237 1.155 1.079 1.000 > 60 4.15 4.15 3.78 TBSOOS SLO

< 60 3.6 7 3.6 7 3.2 8 1.399 1.323 1.237 1.155 1.079 1.000 > 60 4.1 8 4.1 8 3.81

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 11 of 26 TABLE 4-3 Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating)

(Reference

2) Core Flow (% rated) MCPR(F) Limit 0.0 1.7 4 30.0 1.5 7 86.0 1.2 5 110.0 1.2 5 TABLE 4-4 SLO Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating)

(Reference 2)

Core Flow (% rated) MCPR(F) Limit 0.0 1.7 7 30.0 1.60 86.0 1.2 8 110.0 1.2 8 Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 12 of 26 5.0 LHGR LIM I TS 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 GNF2 fuel type are provided in Table s 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 o F for FFWTR operation (bounding for FWHOOS 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 provided and accounted for in Table 5

-4. The power

- and flow-dependent LHGR multipliers were obtained from Reference

2. The impact of AFTO on LHGR is addressed in Section 10.

For PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS conditions, the limits are listed in Section 10; these values are bounding for non

-AFTO conditions. The power and flow dependent LHGR multipliers are sufficient to provide adequate protection for the off

-rated conditions from an ECCS

-LOCA analysis perspective.

TABLE 5-1 Linear Heat Generation Rate Limits

- UO2 rods (References 4 and 11) Fuel Type LHGR Limit GNF2 See Appendix B of Reference 4 TABLE 5-2 Linear Heat Generation Rate Limits

- Gad rods (References 4 and 11) Fuel Type LHGR Limit GNF2 See Appendix B of Reference 4

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 13 of 26 TABLE 5-3 Power Dependent LHGR Multiplier LHGRFAC(P)

(Symmetric Feedwater Heating)

(Reference

2) EOOS Combination Core Flow (% of rated)

Core Thermal Power (% of rated) 0 23 <26.7 7 40 55 65 85 100 LHGRFAC(P) Multiplier Base 0.5 08 0.5 08 0.5 22 0.620 0.696 0.751 0.817 0.930 1.000 > 60 0.5 08 0.5 08 0.5 22 Base SLO 0.508 0.508 0.522 0.620 0.696 0.751 0.817 0.930 1.000 > 60 0.508 0.508 0.522 RPTOOS 0.508 0.508 0.522 0.620 0.696 0.751 0.817 0.930 1.000 > 60 0.508 0.508 0.522 RPTOOS SLO 0.508 0.508 0.522 0.620 0.696 0.751 0.817 0.930 1.000 > 60 0.508 0.508 0.522 PR/PLUOOS 0.508 0.508 0.522 0.620 0.696 0.751 0.817 0.930 1.000 > 60 0.508 0.508 0.522 PR/PLUOOS SLO 0.508 0.508 0.522 0.620 0.696 0.751 0.817 0.930 1.000 > 60 0.508 0.508 0.522 TBSOOS 0.397 0.397 0.442 0.620 0.655 0.714 0.817 0.930 1.000 > 60 0.397 0.397 0.417 TBSOOS SLO 0.397 0.397 0.442 0.620 0.655 0.714 0.817 0.930 1.000 > 60 0.397 0.397 0.417 TABLE 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)

(Symmetric Feedwater Heating)

(Reference 2)

EOOS Combination Core Flow (% of rated) 0 30 33.6 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.506 0.706 0.730 0.973 1.000 1.000 Single Loop 0.506 0.706 0.730 0.730 0.730 0.730 Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 14 of 26 6.0 ROD BLOCK MONITOR SETPOINTS 6.1 Technical Specification Section 3.3.2.1 6.2 Description The RBM power

-biased Allowable Values and MCPR Limits are provided in Table 6

-1 with supporting documentation in References 2 and 9.

The values correspond to the OLMCPR values provide in Table 4

-1. TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 9) Power Level Allowable Value (1) MCPR Limit LTSP 118.2% < 1.83 (2) < 1.50 (3) ITSP 113.4% < 1.83 (2) < 1.50 (3) HTSP 108.4% < 1.83 (2) < 1.50 (3) INOP N/A < 1.83 (2) < 1.50 (3)

(1) These setpoints (with RBM filter time const ant 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 R eference s 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 R eference 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 R eference 2 and TS Table 3.3.

2.1-1).

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 15 of 26 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 System Out-of-Service (TBSOOS) must be used. Additionally

, the OLMCPR for TBSOOS 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. TABLE 7-1 Turbine Bypass System Response Time (Reference 1

2) Maximum delay time before start of bypass valve opening following initial turbine inlet valve movement(1) 0.10 sec Maximum time after initial turbine inlet valve movement(1) for bypass valve position to reach 80% of full flow (includes the above delay time) 0.30 sec (1) First movement of any TSV or any TCV (whichever occurs first)

TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability (Reference 1

2) Reactor Power No. of Valves in Service 3% 7 Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 1 6 of 26 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 Out Of Service (RPTOOS) must be used. Additionally

, the OLMCPR for RPTOOS must be applied. Table 8-1 includes the total RPT response time parameter.

TABLE 8-1 Recirculation Pump Trip Response Time (Reference 12

) Total Recirculation Pump Trip Response Time The time from when the turbine valves (turbine control valve or turbine stop valve) start to close until complete arc suppression of the EOC

-RPT circuit breakers as described in Reference 7.

0.175 sec Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 17 of 26 9.0 STABILITY PROTECTION 9.1 Technical Specification Section 3.3.1

.1, Table 3.3.1.1

-1 Function 2.f 9.2 Description Per Reference 2, the Cycle 22 DSS-CD S AD Setpoint was confirmed to be 1.10 for DLO and SLO. The Automatic Backup Stability Protection (BSP) Setpoints are provided in Table 9

-1. The Manual BSP Endpoints for Normal Feedwater Temperature and Reduced Feedwater Temperature are provided in Tables 9

-2 and 9-3. Reduced FWT as stated in Table 9

-3 is intended for feedwater temperatures 10-90°F below nominal.

TABLE 9-1 Automatic BSP Setpoints for the Scram Region (Reference 2)

Parameter Symbol Value Slope of ABSP APRM flow

-biased trip linear segment.

mTrip 1.3 7 ABSP APRM flow

-biased trip setpoint power intercept.

Constant Power Line for Trip from zero Drive Flow to Flow Breakpoint value.

PBSP-Trip 39.3 %RTP ABSP APRM flow

-biased trip setpoint drive flow intercept. Constant Flow Line for Trip.

WBSP-Trip 46.5 %RDF Flow Breakpoint value WBSP-Break 20.0 %RDF

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 18 of 26 TABLE 9-2 (1) Manual BSP Endpoints for Normal Feedwater Temperature (Reference 2)

Endpoint Power (%) Flow (%) Definition A1 74.3 49.2 Scram Region Boundary, HFCL B1 40.7 31.0 Scram Region Boundary, NCL A2 64.5 50.0 Controlled Entry Region Boundary, HFCL B2 28.1 30.1 Controlled Entry Region Boundary, NCL Note: The BSP Boundary for Normal and Reduced Feedwater Temperature is defined by the MELLLA boundary line, per Reference 2.

TABLE 9-3 (1) Manual BSP Endpoints for Reduced Feedwater Temperature (Reference 2)

Endpoint Power (%) Flow (%) Definition A1 6 4.0 49.4 Scram Region Boundary, HFCL B1 34.4 30.6 Scram Region Boundary, NCL A2 66.4 52.4 Controlled Entry Region Boundary, HFCL B2 28.1 30.1 Controlled Entry Region Boundary, NCL Note: The BSP Boundary for Normal and Reduced Feedwater Temperature is defined by the MELLLA boundary line, per Reference 2.

(1) Station may elect to place additional administrative margin on the e ndpoints provided in Table 9-2 and Table 9

-3.

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 19 of 26 10.0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION (AFTO)

Asymmetric feedwater heating (resulting from removing a heater string, or individual feedwater heaters, from operation) is the result of the specific configuration of the feedwater lines at Peach Bottom. A reduction in heating in either the 'A' or the 'C' heater strings will result in a temperature mismatch between the feedwater flows entering the opposite sides of the reactor vessel. This temperature mismatch may result in errors in the thermal limit values calculated by the core monitoring system. Thermal limit values for all conditions and events are impacted by these errors excluding SLO conditions. The station no longer requires SLO AFTO files or penalties due to a 3D MONICORE upgrade required for EPU operation. 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.

To simplify the implementation of the AFTO limits, only the maximum AFTO penalties indicated in Table 10-1 will be implemented when the threshold asymmetry temperature (temperature above which a penalty is required) is exceeded. This will minimize the number of AFTO thermal limit tables in the COLR and core monitoring system.

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

(Reference 10)

MFLCPR MFLPD/MAPRAT 40°°F 3% 4% 30°°F 2% 3% 20°°F 2% 2% 0°°F No Penalty No Penalty LHGR LIMITS The ARTS-based LHGR power

-dependent multipliers for AFTO operation are provided in Table 10

-2. The flow-dependent multipliers for AFTO in DLO are provided in Table 10

-3. The power

-and flow-dependent LHGR multipliers were obtained from Reference 2 and were adjusted with the appropriate penalties displayed in Table 10

-1 as per Reference 10

. PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS values were obtained by taking the most limiting values of the two EOOS conditions (Reference 8). The maximum feedwater temperature difference allowed without a thermal limit penalty is 20 F. Once the temperature difference exceeds 20 F the maximum penalties from Table 10

-1 are applied to the thermal limits. Additionally, no LHGR penalties are required for AFTO while in SLO as previously discussed.

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 20 of 26 TABLE 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 2 0°°F (Asymmetric Feedwater Heating)

(References 2 , 8, and 1 0) EOOS Combination Core Flow (% of rated) Core Thermal Power (% of rated) 0 23 <26.7 7 40 55 65 85 100 LHGRFAC(P) Multiplier Base 0.488 0.488 0.501 0.595 0.668 0.721 0.784 0.893 0.960 > 60 0.488 0.488 0.501 RPTOOS 0.488 0.488 0.501 0.595 0.668 0.721 0.784 0.893 0.960 > 60 0.488 0.488 0.501 PR/PLUOOS 0.488 0.488 0.501 0.595 0.668 0.721 0.784 0.893 0.960 > 60 0.488 0.488 0.501 TBSOOS 0.381 0.381 0.424 0.595 0.629 0.685 0.784 0.893 0.960 > 60 0.381 0.381 0.400 PR/PLUOOS + TBSOOS 0.381 0.381 0.424 0.595 0.629 0.685 0.784 0.893 0.960 > 60 0.381 0.381 0.400 PR/PLUOOS + RPTOOS 0.488 0.488 0.501 0.595 0.668 0.721 0.784 0.893 0.960 > 60 0.488 0.488 0.501 TABLE 10-3 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 2 0°°F (Asymmetric Feedwater Heating)

(References 2 and 10) EOOS Combination Core Flow (% of rated) 0 30 33.6 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.486 0.6 78 0.701 0.934 0.960 0.960 Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 21 of 26 MCPR LIMITS The OLMCPR s during asymmetric feedwater temperature operation with a feedwater temperature difference greater than 2 0 F are provided in Table 10-4. The ARTS

-based power

-dependent MCPR limits for use during AFTO conditions are provided in Table 10

-5. The flow

-dependent MCPR limits for AFTO are provided in Table 10-6. The power and flow

-dependent OLMCPR curves were obtained from Reference 2 and were adjusted with a 3% penalty for feedwater temperature difference greater than 2 0F as displayed in Table 10

-1 as per Reference 10. PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS values were obtained by taking the most limiting OLMCPR values of the two EOOS conditions (Reference 8). No MCPR penalties are required for asymmetric temperature differentials less than or equal to 2 0 F. Additionally, no MCPR penalties are required for AFTO while in SLO as previously discussed.

TABLE 10-4 AFTO Operating Limit Minimum Critical Power Ratio 2 0°°F (Asymmetric Feedwater Heating)

(References 2 , 8, and 10) EOOS Combination SCRAM Time Option (1) Cycle Exposure

< EOR - 3915 MWd/ST > EOR - 3915 MWd/ST BASE B 1.44 1.46 B*(2) 1.42 1.45 A 1.52 1.55 RPTOOS B 1.47 1.49 A 1.65 1.67 PR/PLUOOS B 1.44 1.46 A 1.52 1.55 TBSOOS B 1.48 1.51 A 1.58 1.61 PR/PLUOOS + TBSOOS B 1.48 1.51 A N/A N/A PR/PLUOOS + RPTOOS B 1.47 1.49 A N/A N/A

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

(2) Limit is only applicable if it is confirmed that a 45ms or greater delay exists between the time of the first TCV movement and the time of first TSV movement following a turbine trip; this may be selected per applicable station procedures.

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 22 of 26 TABLE 10-5 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 2 0°°F (Asymmetric Feedwater Heating)

(References 2, 8, and 1 0) EOOS Combination Core Flow (% of rated) Core Thermal Power (% of rated) 0 23 <26.7 7 40 55 65 85 100 Operating Limit MCPR Operating Limit MCPR Multiplier, Kp Base < 60 2.75 2.75 2.68 1.392 1.288 1.237 1.130 1.067 1.000 > 60 3.08 3.08 2.91 RPTOOS < 60 2.75 2.75 2.68 1.392 1.288 1.237 1.130 1.067 1.000 > 60 3.08 3.08 2.91 PR/PLUOOS < 60 2.75 2.75 2.68 1.392 1.288 1.237 1.210 1.147 1.000 > 60 3.08 3.08 2.91 TBSOOS < 60 3.75 3.75 3.35 1.399 1.323 1.237 1.155 1.079 1.000 > 60 4.27 4.27 3.89 PR/PLUOOS + TBSOOS

< 60 3.75 3.75 3.35 1.399 1.323 1.237 1.210 1.147 1.000 > 60 4.27 4.27 3.89 PR/PLUOOS + RPTOOS

< 60 2.75 2.75 2.68 1.392 1.288 1.237 1.210 1.147 1.000 > 60 3.08 3.08 2.91 TABLE 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 2 0°°F (Asymmetric Feedwater Heating)

(References 2 and 10) Flow (% rated) MCPR(F) Limit 0.0 1.79 30.0 1.62 86.0 1.29 110.0 1.29 Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 23 of 26 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. The reduction factor listed in Table 10

-1 is the maximum penalty for the full range of analyzed FWT mismatches, bounding all smaller temperature deltas.

No MAPLHGR penalties are required for AFTO while in SLO as previously discussed.

TABLE 10-7 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)

(References 2 and 10)

AFTO Reduction Factor 2 0°55°F 0.9 6 0 Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 24 of 26 11.0 MODES OF OPERATION The following conditions are supported by the Peach Bottom 3 Cycle 22 licensing analysis; operation in a condition (or conditions) is controlled by station procedures. If a combination of options is not listed, it is not supported. Table 11-1 provides allowed modes of operation with thermal limit sets in the COLR. Table 11-2 provides allowed modes of operation that do not contain explicit thermal limit sets in the COLR. TABLE 11-1 Modes of Operation (Reference 2)

EOOS Options Supported Scram Speed Option Supported Recirculation Loop Operation Supported SFTO/AFTO Base 1 , 2 A or B DLO or SLO 3 SFTO or AFTO TBSOOS A or B DLO or SLO 3 SFTO or AFTO RPTOOS A or B DLO or SLO 3 SFTO or AFTO PLUOOS A or B DLO or SLO 3 SFTO or AFTO PROOS A or B DLO or SLO 3 SFTO or AFTO PR/PLUOOS and TBSOOS B DLO AFTO 4 PR/PLUOOS and RPTOOS B DLO AFTO 4 TABLE 11-2 EOOS Options Included in 'Base' Conditions (Reference 2)

EOOS Condition TCV/TSVOOS 5 MSIVOOS 5 SRVOOS TBVOOS 12.0 METHODOLOGY

The analytical methods used in determining the core operating limits have been previously reviewed and approved by the NRC, specifically those described in the following document s: 1. "General Electric Standard Application for Reactor Fuel," Global Nuclear Fuel Document No.

NEDE-24011-P-A-2 5 , August 201 7 and U.S. Supplement NEDE

-24011-P-A-2 5-US, August 2017

.

1 The 'Base' condition includes the options listed in Table 11

-2. 2 The 'Base' condition includes operation with FWHOOS/FFWTR. Operation not permitted in the MELLLA+ Region for reduced FWT conditions as controlled by station procedures.

3 Operation in SLO not permitted in the MELLLA+ Region as controlled by station procedures.

4 AFTO limits bound SFTO limits.

5 Permitted at power levels provided in the applicable station procedure.

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 25 of 26

13.0 REFERENCES

1. "Technical Specifications for Peach Bottom Atomic Power Station Unit 3 ," Exelon Document, Docket No. 50-27 8, Appendix A to License No. DPR-56.

2. "Supplemental Reload Licensing Report for Peach Bottom Unit 3 Reload 21 Cycle 2 2 ," Global Nuclear Fuel Document No. 003N1452, Revision 0 , September 2017.

3. "General Electric Standard Application for Reactor Fuel (GESTAR II)

," Global Nuclear Fuel Document No. NEDE-24011-P-A-2 5 , August 2017 and U.S. Supplement NEDE

-24011-P-A-2 5-US, August 2017

. 4. "GNF2 Advantage Generic Compliance with NEDE

-24011-P-A (GESTAR II)," Global Nuclear Fuel Document No. NEDC -33270P, Revision 8, April 201 7. 5. "Peach Bottom EPU Evaluation of Feedwater Temperature vs. Reactor Power for Feedwater Temperature Conditions of Nominal Rated, FWHOOS (Nominal

--," General Electric Hitachi Nuclear Energy Document No. 001N2494

-R0, Revision 0, July 2014. This document is searchable in Exelon EDMS under document number "PEAM

-EPU-1 Rev. 0A."

6. "Safety Analysis Report for Peach Bottom Atomic Power Station Units 2 & 3 Maximum Extended Load Line Limit Analysis Plus", General Electric Hitachi Nuclear Energy Document No. NEDO -33720, Revision 0, September 2014.

7. "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

," PECO Calculation No. PE

-0173, Revision 1, December 1998.

8. "Peach Bottom Units 2 and 3 TRACG Cycle

-Independent PROOS & PLUOOS Analysis Repor t ," Global Nuclear Fuel Document No. 002N8351, Revision 2, May 25, 2016.

9. "Provide Allowable Values (AV) and Nominal Trip Setpoints (NTSP) for Various Setpoint Functions of the NUMAC PRNM System

", PECO Calculation No. PE

-0251, Revision 3, October 2016.

10. "Final Evaluation Report Exelon Nuclear Generating Company LLC

, Peach Bottom Units 2 & 3

, MELLLA+, Asymmetric Feedwater Temperature Operation for EPU/MELLLA+

," General Electric Hitachi Nuclear Energy Document No. 001N6733

-R1, Revision 1 , September 2014. This document is searchable in Exelon EDMS under document number "PEAM

-EPU-68 Rev. 1." 11. "Fuel Bundle Information Report for Peach Bottom Unit 3 Reload 21 Cycle 2 2 ," Global Nuclear Fuel Document No.

003 N 1453, Revision 0, August 2017

.

12. "Final Resolved OPL

-3 Parameters for Peach Bottom Unit 3 Cycle 22," Exelon TODI ENSAF ID#

ES1700007, Revision 1 , June 201 7.

Exelon Nuclear

- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 12 P 3 C 22 Core Operating Limits Report Page 26 of 26 APPENDIX A Power/Flow Operating Map for MELLLA+

(Reference 6)

BSP Boundary