ML19331A028

Issuance of the Core Operating Limits Report for Reload 22, Cycle 23

ML19331A028
Person / Time
Site:	Peach Bottom
Issue date:	11/21/2019
From:	Pat Navin Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML19331A028 (26)

Text

Exelon Generation November 21, 2019 U.S. Nuclear Regulatory Commission A TIN: 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 22, Cycle 23 Enclosed is a copy of Revision 16 of the Core Operating Limits Report (COLA) for Peach Bottom Atomic Power Station (PBAPS) Unit 3 for Reload 22, Cycle 23. This revision incorporates the revised cycle specific parameters resulting from the new core configuration as a result of the PBAPS Unit 3 refueling outage.

This COLA 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 Dan Dullum at (717) 456-3339.

Rei#fj Patrick D. Navin Site Vice President Peach Bottom Atomic Power Station CCN: 19-133

Attachment:

Core Operating Limits Report for PBAPS Unit 3, Revision 16 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)

D. Tancabel, State of Maryland (without attachment)

Enloa Nucle1r - Nuclear Fuels P3C23 Core Opcraung L1rruts Report COLR PEACH BOTTOM 3 Rev. 16 Page 1 of25 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 3 RELOAD 22, CYCLE 23 (This revision is a complete re-write)

Prepared By: _ _.M

__ -v-(' _________ _

Meg~bacher - Nuclear Fuels Reviewed By: -~-/:-----------

Tim Mitchell - Reactor Engineering Reviewed By: --~----~-

__ tr Independent Review By:

SQRBy:

Baris Sarikaya - Engineering Safety Analysis Date: _1_0_11_a1_1 s_

Date: I 0-20-19 10/18/2019 Date: ___ _

Date:

10/18/19 Date:

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report Table of Contents Revision History List of Tables 1.0 Terms and Definitions 2.0 General Information 3.0 MAPLHGR Limits 4.0 MCPRLimits 5.0 LHGR Limits 6.0 Rod Block Monitor Setpoints 7.0 Turbine Bypass Valve Parameters 8.0 EOC Recirculation Pump Trip (EOC-RPT) Operability 9.0 Stability Protection COLR PEACH BOTTOM 3 Rev. 16 Page 2 of25 Page 3

4 5

6 7

8 12 14 15 16 17 10.0 Asymmetric Feedwater Temperature Operation (AFTO) 19 11.0 Modes of Operation 23 12.0 Methodology 23 13.0 References 24 Appendix A (Power/Flow Operating Map for MELLLA+ with TPO) 25

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report Revision Revision 16 Revision History COLR PEACH BOTTOM 3 Rev. 16 Page 3 of25 Description New issue for Cycle 23

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 16 Page 4 of25 List of Tables Table 3-1 MAPLHGR Versus Average Planar Exposure Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier Table 4-1 Operating Limit Minimum Critical Power Ratio Table 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers Table 4-3 Flow Dependent MCPR Limits MCPR(F)

Table 4-4 SLO Flow Dependent MCPR Limits MCPR(F)

Table 4-5 Cycle Specific SLMCPR (MCPR999%)

Table 5-1 Linear Heat Generation Rate Limits - U02 rods Table 5-2 Linear Heat Generation Rate Limits - Gad rods Table 5-3 Power Dependent LHGR Multiplier LHGRF AC(P)

Table 5-4 Flow Dependent LHGR Multiplier LHGRF AC(F)

Table 6-1 Rod Block Monitor Setpoints Table 7-I Turbine Bypass System Response Time Table 7-2 Minimum Required Bypass Valves to Maintain System Operability Table 8-1 Recirculation Pump Trip Response Time Table 9-1 Automated BSP Setpoints for the Scram Region Table 9-2 Manual BSP Endpoints for Normal Feedwater Temperature Table 9-3 Manual BSP Endpoints for Reduced Feedwater Temperature Page 7

7 9

10 11 11 11 12 12 13 13 14 15 15 16 17 18 18 Table 10-1 AFTO MAPLHGR Reduction Factor 19 Table 10-2 AFTO Operating Limit Minimum Critical Power Ratio 20°F < FWT DELTA$ 55°F 20 Table 10-3 AFTO Power Dependent MCPR Limit Adjustments and Multipliers 21 MCPR(P) 20°F < FWT DELTA$ 55°F Table 10-4 AFTO Flow Dependent MCPR Limits MCPR(F) 20°F < FWT DELTA$ 55°F 21 Table 10-5 AFTO Power Dependent LHGR Multiplier LHGRF AC(P) 20°F < FWT DEL TA$ 55°F 22 Table 10-6 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20°F < FWT DELTA$ 55°F 22 Table 11-1 Modes of Operation 23 Table 11-2 EOOS Options Included in 'Base' Conditions 23

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report 1.0 Terms and Definitions COLR PEACH BOTTOM 3 Rev. 16 Page 5 of25 ABSP AFTO AITOLFWH APRM ARTS BASE BOC BSP DLO DSS-CD ECCS-LOCA EOC EOOS EOR FOL FFWTR FWHOOS FWf HFCL HTSP ICF

!TSP Kp LHGR LHGRFAC(F)

LHGRFAC(P)

LTSP MAPLHGR MCPR MCPR99.,,

MCPR(F)

MCPR(P)

MELLLA MELLLA+

MS!VOOS NCL OLMCPR PLUOOS PROOS RBM RDF RPTOOS RTP RWF.

SFTO SLMCPR SLO SRVOOS Tau(T)

TB SOOS TBVOOS Tcvrrsvoos TPO Automated Backup Stability Protection Asymmetric Feedwater Temperature Operation Asymmetric Feedwater Temperature Operation Loss-of-Feedwater Heatmg Average Power Range Monitor APRM, Rod Block and Technical Specification Improvement Program The "BASE" condltmn is defined by a group of md1vidual operatmg conditions that are applicable to all Modes of Operation discussed in Section I I. The "BASE" condition includes the EOOS conditmns provided in Table 11-2 as well as operation with FWHOOS/FFWTR.

Beginning of Cycle Backup Stability Protection Dual Loop Operation Detect and Suppress Solution - Confirmation Density Emergency Core Cooling System - Loss of Coolant Accident End of Cycle Equipment Out of Service. An analyzed option that assumes certain equipment to be non-operational End of Rated. The cycle exposure at which reactor power is equal to 100% with recrrculatmn system flow equal to I 00%, all conrrol rods fully withdrawn, all feedwater heaung in service and eqwhbrium Xenon Facility Operating License Final Feedwater Temperature Reducuon Feedwater Heater(s) Out of Service Feedwater Temperature High Flow Control Line Rod Block Monitor High Trip Setpomt Increased Core Flow Rod Block Monitor Intermediate Trip Setpoint Off-rated power dependent OLMCPR multiplier Lmear Heat Generation Rate Off-rated flow dependent LHGR multiplier Off-rated power dependent LHGR mulupher Rod Block Monitor Low Trip Setpomt MaxJmum Average Planar Linear Heat Generatmn Rate Minimum Critical Power Ratio Limitmg MCPR value such that 99 9 percent of the fuel m the core is not suscepuble to boilmg transition Off-rated flow dependent OLMCPR Off-rated power dependent OLMCPR Maximum Extended Load Lme Limit Analysis Maximum Extended Load Lme Limit Analysis Plus Main Steam Isolation Valve Out of Service Natural Circulation Lme Operating Limit Mimmum Critical Power Ratio Power Load Unbalance Out of Service Pressure Regulator Out of Service Rod Block Monitor Recirculation Drive Flow Rccrrculation Pump Tnp Out of Service Rated Thennal Power Rod Withdrawal Error Symmetric Feedwatcr Temperature Opcratmn Safety Limit Minimum Critical Power Ratio Single Loop Operation Safety/RehefValve(s) Out of Service A measure of scram time performance to notch posiuon 36 throughout the cycle Turbine Bypass System Out of Service Turbme Bypass Valve(s) Out of Service Turbine Control Valve and/or Turbine Stop Valve Out of Service Thermal Power Optimization, also known as Measurement Uncertamty Recapture

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report 2.0 General Information COLR PEACH BOTTOM 3 Rev. 16 Page 6 of25 This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 3 Cycle 23 (Reload 22):

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 MCPR99'>"!o 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 limits 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(l6).

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 85.2% of rated core flow during full power ( 4016 MWt) operation (Appendix A)

Increased Core Flow (ICF), up to 110% ofrated 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 1h and 5th 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 OLM CPR is determined by the cycle-specific reload analyses in Reference 2. Rated LHGR values are obtained from the bundle-specific thermal-mechanical analysis documented in Reference 13. 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 23 core is comprised entirely ofGNF2 fuel.

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report 3.0 MAPLHGR LIMJTS 3.1 Technical Specification Section 3.2.l, 3.3.4.2, 3.4.1and3.7.6 3.2 Description COLR PEACH BOTTOM 3 Rev. 16 Page 7 of25 The limiting MAPLHGR value for the most limiting lattice of GNF2 fuel as a function of average planar exposure is given in Table 3-1. For single loop operation, a multiplier is used, which is shown in Table 3-2. The power-and flow-dependent LHGR multipliers are sufficient to provide adequate protection for the off-rated conditions from an ECCS-LOCA analysis perspective. The MAPLHGR multipliers can either be set to unity or set equal to the LHGR multipliers, which remain compliant with the basis of the ECCS-LOCA analysis with no loss ofECCS-LOCA margin.

The impact of AFTO on MAPLHGR is addressed in Section I 0.

TABLE3-1 MAPLBGR Versus Average Planar Exposure (Reference 2)

Average Planar Exposure MAPLHGR Limit (GWd/ST)

(kW/ft) 0.0 13.78 17.52 13.78 60.78 7.50 63.50 6.69 TABLE3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2)

SLO Multiplier 0.73

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report 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 COLR PEACH BOTTOM 3 Rev. 16 Page 8 of25 The Operating Limit MCPR (OLMCPR) for GNF2 fuel 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 (r),

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 OLM CPR value if Tau is between 0.0 (Tau Option B) and 1.0 (Tau Option A). Table 4-1 is valid for a maximum FWT reduction of90°F (Reference 2).

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) (Reference 2). The flow-dependent MCPR limits are provided in Tables 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 l 0. For PRIPLUOOS + TBSOOS and PR/PLUOOS + RPTOOS conditions, the limits are listed in Section 1 O; these values are bounding for non-AFTO conditions.

The cycle-specific SLMCPRs, known as MCPR99_9*~, can be found in Table 4-5 for dual loop and single loop operating conditions. The values in Table 4-5 or conservative values were used to calculate the MCPR limits and off-rated limits in this section and Section 10.

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report TABLE4-1 COLR PEACH BOTTOM 3 Rev. 16 Page 9 of25 Operating Limit Minimum Critical Power Ratio (Symmetric Feedwater Heating)

(Reference 2)

SCRAM Cycle Exposure Time

< EOR-3995

~EOR-3995 EOOS Combination Option<!)

MWd/ST MWd/ST BASE B

1.40 1.40 A

1.44 1.48 BASE SL0<2l B

1.43 1.43 A

1.47 1.51 RPTOOS B

1.40 l.43 A

1.56 1.60 RPTOOS SL0<2l B

1.43 1.46 A

1.59 1.63 PR/PLUOOS B

1.40 1.40 A

1.44 1.48 PR/PLUOOS SLOl2!

B 1.43 l.43 A

l.47 1.51 TB SOOS B

1.46 1.46 A

1.48 1.54 TBSOOS SLO l2l B

1.49 1.49 A

1.51 1.57 (1 ) When Tau does not equal 0 or 1, use linear interpolation.

(2) For single-loop operation, the MCPR operating limit is 0.03 higher than the two-loop value IP.eference 2 I.

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report TABLE 4-2 COLR PEACH BOTTOM 3 Rev. 16 Page 10 of25 Power Dependent MCPR(P) Limit Adjustments and Multipliers

{Symmetric Feedwater Heating)

{Reference 2)

Core Core Thermal Power (% of rated)

EOOS Combination Flow 0

22.6

~26.3 >26.3 40 55 65 85 100

{% 01 rated Operating Limit MCPR Operating Limit MCPR Multiplier, Kp

<60 2.67 2.67 2.60 Base 1.392 1.288 1.237 1.130 1.067 1.000

~ 60 2.99 2.99 2.83

<60 2.70 2.70 2.63 Base SLO 1.392 1.288 1.237 1.130 1.067 1.000

~60 3.02 3.02 2.86

<60 2.67 2.67 2.60 RPTOOS

~ 60 2.99 2.99 2.83 1.392 1.288 1.237 1.130 1.067 1.000

<60 2.70 2.70 2.63 RPTOOS SLO 1.392 1.288 1.237 1.130 1.067 1.000

~ 60 3.02 3.02 2.86

<60 2.67 2.67 2.60 PR/PLUOOS

~60 2.99 2.99 2.83 1.392 1.288 1.237 1.210 1.147 1.000

< 60 2.70 2.70 2.63 PR/PLUOOS SLO 1.392 1.288 1.237 1.210 1.147 1.000

~60 3.02 3.02 2.86

<60 3.64 3.64 TB SOOS

~ 60 4.15 4.15 3.25 3.78 1.399 1.323 1.237 1.155 1.079 1.000

<60 3.67 3.67 3.28 TBSOOSSLO 1.399 1.323 1.237 1.155 1.079 1.000

~ 60 4.18 4.18 3.81

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report TABLE4-3 COLR PEACH BOTTOM 3 Rev. 16 Page 11 of25 Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating)

(Reference 2) 0.0 1.73 30.0 1.56 86.0 1.25 110.0 1.25 TABLE4-4 SLO Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating)

(Reference 2)

Core Flow MCPR(F)

(%rated)

Limit 0.0 1.76 30.0 1.59 86.0 1.28 110.0 1.28 Table 4-5 Cycle Specific SLMCPR (MCPR99.9%)

<Reference 2)

Loop Operation MCPR99.9%

DLO 1.14 SLO 1.14

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report 5.0 LHGR LIMITS COLR PEACH BOTTOM 3 Rev. 16 Page 12 of25 5.1 Technical Specification Section 3.2.3, 3.3.4.2, 3.4.1and3.7.6 5.2 Description The LHGR values for GNF2 fuel are provided in Tables 5-1 and 5-2. The ARTS-based LHGR power-dependent multipliers are provided in Table 5-3. Table 5-3 is valid for a maximum temperature reduction of 90°F for FFWTR operation (bounding for FWHOOS operation)

(Reference 2). The flow-dependent multipliers are provided in Table 5-4 as a function of the number of recirculation loops in operation. 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 1 O; 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 - U02 rods (References 11 and 13)

Fuel Type LHGR Limit GNF2 See Reference 13 TABLE 5-2 Linear Heat Generation Rate Limits - Gad rods (References 11 and 13)

Fuel Type LHGRLimit GNF2 See Reference 13

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 16 Page 13 of25 EOOS Combination Base Base SLO RPTOOS RPTOOS SLO PR/PLUOOS PR/PLUOOSSLO TB SOOS TBSOOS SLO TABLES-3 Power Dependent LHGR Multiplier LHGRFAC(P)

{Symmetric Feedwater Heating)

{Reference 2)

Core Thermal Power {% of rated)

Core Flow 0

22.6

26.3

>26.3 40 55

{%of rated)

LHGRFAC(P) Multiplier

<60 0.508 0.508 0.522 0.620 0.696 2'.: 60 0.508 0.508 0.522

<60 0.508 0.508 0.522 0.620 0.696 2'.: 60 0.508 0.508 0.522

<60 0.508 0.508 0.522 0.620 0.696 2'.: 60 0.508 0.508 0.522

<60 0.508 0.508 0.522 0.620 0.696 2'.: 60 0.508 0.508 0.522

<60 0.508 0.508 0.522 0.620 0.696 2'.: 60 0.508 0.508 0.522

<60 0.508 0.508 0.522 0.620 0.696 2'.:60 0.508 0.508 0.522

<60 0.397 0.397 0.442 0.620 0.655 2'.: 60 0.397 0.397 0.417

<60 0.397 0.397 0.442 0.620 0.655 2'.: 60 0.397 0.397 0.417 TABLES-4 Flow Dependent LHGR Multiplier LHGRFAC(F)

{Symmetric Feedwater Heating)

{Reference 2)

Core Flow {% of rated) 0.751 0.751 0.751 0.751 0.751 0.751 0.714 0.714 EOOS Combination 0

30 33.6 70 80 LHGRF AC(F) Multiplier Dual Loop 0.506 0.706 0.730 0.973 1.000 Single Loop 0.506 0.706 0.730 0.730 0.730 65 85 0.817 0.930 0.817 0.930 0.817 0.930 0.817 0.930 0.817 0.930 0.817 0.930 0.817 0.930 0.817 0.930 110 1.000 0.730 100 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 16 Page 14 of25 6.0 ROD BLOCK MONITOR SETPOINTS 6.1 Technical Specification Section 3.3.2. I 6.2 Description The RBM power-biased Allowable Values and MCPR Limits are provided in Table 6-1 with supporting documentation in References 2, 3, 9 and 10. The SFTO MCPR Limits apply when FWT difference is below 20°F. The AFTO MCPR Limits apply with FWT difference between 20 and 55°F. AFTO conditions are discussed further in Section 10. The values correspond to the OLMCPR values provided in Table 4-1.

Power Level LTSP ITSP HTSP INOP TABLE 6-1 Rod Block Monitor Setpoints (References 2, 3, 9 and 10)

Allowable Value< 1>

SFTO MCPR Limit 124.0%

<I.81 <2>

< 1.49 <3J 119.2%

< 1.81 <2>

<1.49(3) 114.2%

< 1.81 <2l

<I.49 (3J NIA

< 1.81 (l)

<1.49(3)

AFTO MCPR Limit

< 1.86 (4)

< 1.53 <5>

< 1.86 <4l

< 1.53 <5>

< 1.86 (.\\)

<1.s3<5l

< 1.86 <4l

< 1.53 <5l (1) These setpoints !with RBM filter time constan t between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated RWE MCPP limi t which is less than or equal to the minimum cycle OLMCPR based on other events (see CJ LP Referenc es 2 and 9).

(::) This is the MCPR limit for symmetric feedwater heating operation (given THERMAL POWEP is >

28. 41 and< 90" ! below which the PBM is required t o be OPEPABLE (see COLR Reference 2 and~S Table 3.3. 2.1-1 ).

(3) This is the MCPP limit for symmetri.: feedwa t er heating operation (given THERMi'-L POWER is -,

90 ~) belo w which the RBM is required to be OPERABLE (see COLR Reference 2 and TS Table

3. 3.::.1-1 1.

(4) This is the MCPP limit for asymmetric feedwater hea t ing operation (given THEPMAL POWER is,

8. 4 and < 90 l below which the RBM is required t o be OPERABLE (See COLR Reference 2, 10 and TS Table 3.3.2.1-1).

(5) This is the MCPR limit for asymmet:ric feedwater hea t ing operation (given THERMAL POWER is ~

90 1! belr w which the PBM is required to be ? PEPABLE (see COLR Peference ::, 10 and TS Table 3.3.2.1-l l.

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 16 Page 15 of25 7.0 TURBINE BYPASS VALVE PARAMETERS

7. l Technical Specification Section 3.7.6 7.2 Description The operability requirements for the turbine 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 System 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 12)

Maximum delay time before start of bypass valve opening following initial turbine inlet valve movement<n Maximum time after initial turbine inlet valve movementCIJ for bypass valve position to reach 80% of full flow (includes the above delay time)

(I) First movement of any TSV m: any TCV (whichever occurs first)

TABLE 7-2 0.10 sec 0.30 sec Minimum Required Bypass Valves to Maintain System Operability (Reference 12)

Reactor Power No. of Valves in Service P~22.6%

7

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 16 Page 16 of25 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 turhine valves (turbine control vah'e or turbine stop valve) start to close until complete arc supprt!ssion

<?f'the EOC-RPT circuit breakers as described i11 Reference 7.

0.175 sec

Ei:clon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report 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 COLR PEACH BOTTOM 3 Rev. 16 Page 17 of25 Per Reference 2, the Cycle 23 DSS-CD SAD Setpoint was confirmed to be 1.10 for DLO and SLO.

The Automated 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, respectively. Table 9-3 is intended for feedwater temperatures l 0-90°F below nominal.

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

Parameter Symbol Value Slope of ABSP APRM flow-mTrip 1.37 biased trip linear segment ABSP APRM flow-biased trip setpoint power intercept.

Constant Power Line for Trip PssP-Tnp 39.3 %RTP from zero Drive Flow to Flow Breakpoint value ABSP APRM flow-biased trip setpoint drive flow intercept.

WssP-Trip 46.5 %RDF Constant Flow Line for Trip Flow Breakpoint value WssP-Break 20.3 %RDF

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report TABLE 9-2<1i COLR PEACH BOTTOM 3 Rev. 16 Page 18 of25 Manual BSP Endpoints for Normal Feedwater Temperature (Reference 2)

Endpoint Power(%)

Flow(%)

Definition Al 74.2 50.6 Scram Region Boundary, HFCL Bl 40.0 31.0 Scram Region Boundary, NCL A2 63.5 50.0 Controlled Entry Region Boundary, HFCL B2 27.6 30.1 Controlled Entry Region Boundary, NCL Note: The BSP Boundary for Nonna! and Reduced Feedwater Temperature is defined by the MELLLA boundary line, per Reference 2.

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

Endpoint Power(%)

Flow(%)

Definition Al' 64.4 51.3 Scram Region Boundary, HFCL Bl '

33.7 30.6 Scram Region Boundary, NCL A2' 66.8 54.4 Controlled Entry Region Boundary, HFCL B2' 27.6 30.1 Controlled Entry Region Boundary, NCL Note: The BSP Boundary for Nonna! 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 endpoints provided in Table 9-~ and Table 9-3.

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 16 Page 19 of25 10.0 ASYMMETRIC FEED WATER TEMPERATURE OPERATION (AFTO)

Asymmetric feedwater heating 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 feed water 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. 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 13 of Reference 10 will be implemented when the threshold asymmetry temperature is exceeded; this will minimize the number of AFTO thermal limit tables in the COLR and core monitoring system. There is no AFTO penalty for a FWT difference below 20°F, between 20 and 55°F difference there is a 4%

LHGRIMAPLHGR penalty and a 3% MCPR penalty, and thermal limits are unanalyzed for a difference above 55°F. The MCPR penalty for AFTO also applies to RBM Operability MCPR Limits which are addressed in Section 6.0.

10.1 MAPLHGR LIMITS An appropriate penalty must be applied to MAPLHGR limits under asymmetric feedwater temperature operation (AFTO) for varying temperature differentials per Reference I 0. 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.

TABLE 10-1 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)

(Reference 10)

AFTO Reduction Factor 20°F<FWTDELTA:S55°Fi 0.960

Exelon Nuclear - Nuclear **ucls P3C23 Core Operating Limits Report 10.2 MCPR LIMITS COLR PEACH BOTTOM 3 Rev. 16 Page 20 of25 The OLMCPRs during asymmetric feedwater temperature operation with a feedwater temperature difference greater than 20°F are provided in Table 10-2. The ARTS-based power-dependent MCPR limits for use during AFTO conditions are provided in Table I 0-3. The flow-dependent MCPR limits for AFTO are provided in Table 10-4. The power-and flow-dependent OLM CPR curves were obtained from Reference 2 and were adjusted with a penalty for feedwater temperature difference greater than 20°F 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).

No MCPR penalties are required for asymmetric temperature differentials less than or equal to 20°F.

TABLE 10-2 A.FTO Operating Limit Minimum Critical Power Ratio 20°F < FWT DELTA~ 55°F

{Asymmetric Feedwater Heating)

(References 2, 8, and 10)

SCRAM Cycle Exposure Time

< EOR-3995

EOR - 3995 EOOS Combination OptionOl MWd/ST MWd/ST BASE B

1.44 1.44 A

1.48 1.52 RPTOOS B

1.44 1.47 A

1.61 1.65 PR/PLUOOS B

1.44 1.44 A

1.48 1.52 TB SOOS B

I.SO 1.50 A

1.52 l.59 PR/PLUOOS + TBSOOS B

1.50 1.50 A

NIA NIA PR/PLUOOS + RPTOOS B

1.44 1.47 A

NIA NIA (ll When Tau does not equal 0 or l, use linear interpolation.

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report TABLE 10-3 COLR PEACH BOTTOM 3 Rev. 16 Page 21 of25 AFfO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 20°F < FWT DEL TA~ 55°F (Asymmetric Feedwater Heating)

(References 2, 8, and 10)

Core Core Thermal Power (% of rated)

EOOS Combination Flow 0

22.6

26.3

>26.3 40 55 65 85

(%of 100 rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp Base

<60 2.75 2.75 2.68 l.392 1.288 1.237 1.130 2: 60 3.08 3.08 2.91

<60 2.75 2.75 2.68 1.288 RPTOOS 1.392 1.237 1.130 2: 60 3.08 3.08 2.91

<60 2.75 2.75 2.68 PR/PLUOOS 1.392 1.288 1.237 1.210 2: 60 3.08 3.08 2.91

<60 3.75 3.75 3.35 TB SOOS l.399 l.323 l.237 1.155 2: 60 4.27 4.27 3.89

<60 3.75 3.75 3.35 PR/PLUOOS + TBSOOS 1.399 1.323 1.237 1.210 2: 60 4.27 4.27 3.89

<60 2.75 2.75 2.68 PR/PLUOOS + RPTOOS 1.392 1.288 1.237 1.210 2: 60 3.08 3.08 2.91 TABLE 10-4 AFfO Flow Dependent MCPR Limits MCPR(F) 20°F < FWT DELTA :5 55°F (Asymmetric Feedwater Heating)

(References 2 and 10)

Flow MCPR(F)

(%rated)

Limit 0.0 1.78 30.0 1.61 86.0 1.29 110.0 1.29 1.067 1.000 1.067 1.000 1.147 1.000 1.079 1.000 1.147 1.000 1.147 1.000

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 16 Page 22 of25 10.3 LHGR LIMITS The ARTS-based LHGR power-dependent multipliers for AFTO operation are provided in Table 10-5. The flow-dependent multipliers for AFTO in DLO are provided in Table 10-6. The power-and flow-dependent LHGR multipliers were obtained from Reference 2 and were adjusted with the appropriate penalties per Reference I 0. PRIPLUOOS + TB SOOS and PRIPLUOOS + 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 Reference 10 are applied to the thermal limits. Additionally, no LHGR penalties are required for AFTO while in SLO as previously discussed.

TABLE 10-5 AFTO Power Dependent LHGR Multiplier LHGRF AC(P) 20°F < FWT DELTA :5 55°F (Asymmetric Feedwater Heating)

(References 2, 8, and 10)

Core Core Thermal Power (% of rated)

EOOS Combination Flow 0

22.6

526.3

>26.3 40 55 65 85

(%of rated)

LHGRFAC(P) Multiplier

<60 0.488 0.488 0.501 Base 0.595 0.668 0.721 0.784

~ 60 0.488 0.488 0.501

<60 0.488 0.488 0.501 RPTOOS 0.595 0.668 0.721 0.784

~60 0.488 0.488 0.501

<60 0.488 0.488 0.501 PRIPLUOOS 0.595 0.668 0.721 0.784

~60 0.488 0.488 0.501

<60 0.381 0.381 0.424 TB SOOS 0.595 0.629 0.685 0.784

~ 60 0.381 0.381 0.400

<60 0.381 0.381 0.424 PRIPLUOOS + TBSOOS 0.595 0.629 0.685 0.784

~60 0.381 0.381 0.400

<60 0.488 0.488 0.501 PRIPLUOOS + RPTOOS 0.595 0.668 0.721 0.784

~60 0.488 0.488 0.501 TABLE 10-6 AFTO Flow Dependent LHGR Multiplier LHGRF AC(F) 20°F < FWT DELTA :5 55°F (Asymmetric Feedwater Heating)

(References 2 and 10)

Core Flow (% of rated)

EOOS Combination 0

I 30 I

33.6 I

70 I

80 I

LHGRFAC(F) Multiplier 0.893 0.893 0.893 0.893 0.893 0.893 110 Dual Loop 0.486 I 0.678 I 0.701 I

0.934 I

0.960 I

0.960 100 0.960 0.960 0.960 0.960 0.960 0.960

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 16 Page 23 of25 11.0 MODES OF OPERATION The following conditions are supported by the Peach Bottom 3 Cycle 23 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.

EOOS Options Base1*2 TB SOOS RPTOOS PLUOOS PROOS PR/PLUOOS and TBSOOS PR/PLUOOS and RPTOOS 12.0 METHODOLOGY TABLE 11-1 Modes of Operation (Reference 2)

Supported Scram Supported Recirculation Sneed Option Loop Operation AorB DLO or SL03 AorB DLO or SL03 AorB DLO or SL03 AorB DLO or SL03 AorB DLO or SL03 B

DLO B

DLO TABLE 11-2 EOOS Options Included in 'Base' Conditions (Reference 2)

EOOS Condition TCV/Tsvoos5 MSIVOOS5 SRVOOS TBVOOS Supported SFTO/AFTO SFTO or AFTO SFTOor AFTO SFTOor AFTO SFTOor AFTO SFTOor AFTO AFT04 AFT04 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 documents:

1.

"General Electric Standard Application for Reactor Fuel," Global Nuclear Fuel Document No. NEDE-240 l l-P-A-29, October 2019 and U.S. Supplement NEDE-240 l l-P-A-29-US, October 2019.

1 The ' Base ' condition includes the options listed in Table 11-2.

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 limns bound SFTO limits.

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

Exelon Nuclear - Nuclear Fuels P3C23 Core Operating Limits Report

13.0 REFERENCES

COLR PEACH BOTTOM 3 Rev. 16 Page 24 of25

l. "Technical Specifications for Peach Bottom Atomic Power Station Unit 3," Exelon Document, Docket No. 50-278, Appendix A to License No. DPR-56.

2.

"Supplemental Reload Licensing Report for Peach Bottom Unit 3 Reload 22 Cycle 23," Global Nuclear Fuel Document No. 004N8287, Revision 0, August 2019.

3. "Removal of Generic ARTS Rated RWE DCPR for Limerick Units l and 2, Nine Mile Point Unit 2, and Peach Bottom Units 2 and 3," General Electric Hitachi Nuclear Energy Document No. 005N2836-RO, Revision 0, July 2019.

4. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," Global Nuclear Fuel Document No. NEDC-33270P, Revision 9, December 2017.

5. "Clarify Rated Feedwater Temp for Feedwater Temp Reduction Curves," Exelon Technical Evaluation EC 628049, Revision 0, August 2019.

6. "Safety Analysis Report for Peach Bottom Atomic Power Station Units 2 and 3 Thermal Power Optimization," General Electric Hitachi Nuclear Energy Document No. NED0-33873, Revision 0, February 2017.

7. "Determination of Time Required to Initiate Trip Signal to the RPT CKT," Exelon Calculation No. PE-0173, Revision I A, January 2019.

8. "Peach Bottom Atomic Power Station Units 2 and 3 TRACG Implementation for Reload Licensing Transient Analysis," General Electric Hitachi Nuclear Energy Document No. 0000-0135-9000-R2, June 2017.

9. "Provide Allowable Values (AV) and Nominal Trip Setpoints (NTSP) for Various Setpoint Functions of the NUMAC PRNM System," Exelon Calculation No. PE-0251, Revision 4, July 2017.

10. "Final Evaluation Report Exelon Nuclear Generating Company LLC Peach Bottom Units 2 & 3 TPO with EPU/MELLLA+ PCR E03: Asymmetric Feedwater Temperature Operation for TPO with EPU/MELLLA+," General Electric Hitachi Nuclear Energy Document No. 001N6733, Revision 2, Sept.

2017. This is searchable in EDMS as "PEAM-MUR-PCR-E03," Revision 0.

11. "Fuel Bundle Information Report for Peach Bottom Unit 3 Reload 22 Cycle 23," Global Nuclear Fuel Document No. 004N8288, Revision 0, August 2019.

12. "Final Resolved OPL-3 Parameters for Peach Bottom Unit 3 Cycle 23," Exelon TOOi ENSAF ID#

ES1900006, Revision 0, May 2019.

13. "PRIME-Based GNF2 LHGR Envelopes for Peach Bottom Atomic Power Station Units 2 and 3,'"

Global Nuclear Fuel Document No. 004N7833-P, Revision 0, April 2018.

Exelon Nuclear - Nuclear Furls P3C23 Core Operating Limits Report APPENDIX A COLR PEACH BOTTOM 3 Rev. 16 Page 25 of25 Power/Flow Operating Map for MELLLA+ with TPO (Reference 6)

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