ML18023A137

From kanterella
Jump to navigation Jump to search
Issuance of the Core Operating Limits Reports
ML18023A137
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 01/23/2018
From: Pat Navin
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CCN: 18-06
Download: ML18023A137 (54)
v • d • e


Text

Exelon Generation.

January 23, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278

Subject:

Issuance of the Core Operating Limits Reports TS 5.6.5.d

Reference:

1. Letter from U.S. NRC (A. B. Ennis) to Exelon (B. Hanson), "Peach Bottom Atomic Power Station, Units 2 and 3 - Issuance of Amendments Re: Measurement Uncertainty Recapture Power Update (CAC Nos.

MF9289 and MF9290; EPID L-2017-LLS-0001)," dated November 15, 2017 (ADAMS Accession No. ML17286A013).

Enclosed are copies of the revised Core Operating Limits Reports (COLA) for Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3. These reports incorporate the revised cycle specific parameters resulting from implementation of License Amendment Nos. 316 and 319, for Units 2 and 3 respectively, relating to PBAPS Measurement Uncertainty Recapture Uprate (Reference 1 ).

The revised COLRs are being submitted to the NRC as required by the PBAPS 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.

Respectt~

Patrick D. Navin Site Vice President Peach Bottom Atomic Power Station CCN: 18-06

Enclosures:

1. Unit 2 Core Operating Limits Report for Reload 21, Cycle 22, Revision 12
2. Unit 3 Core Operating Limits Report for Reload 21, Cycle 22, Revision 13 cc:

USNRC Region I, Regional Administrator, (without attachment)

USNRC Senior Resident Inspector, PBAPS (without attachment)

USNRC Project Manager - PBAPS (with attachment)

R. A. Janati, Pennsylvania Bureau of Radiation Protection (without attachment)

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

ENCLOSURES Unit 2 Core Operating Limits Report for Reload 21, Cycle 22, Revision 12 Unit 3 Core Operating Limits Report for Reload 21, Cycle 22, Revision 13

bcl1111 '\\uclc:ir. '\\urlcar I 11ch P~C2.J Cun.: O~~rJlmg l..11m1.. R...,.... n COLR PEACH BOTTOM 2 Re\\'. 12 Page I of26 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOl\\1 ATOlWIC POWER STATION UNIT 2 Prepared By Prepnred By:

Reviewed By:

Re\\ iewed By:

Independent Review By:

Approved By*

Station Qualified Reviewer:

RELOAD 21, CYCLE 22 (This is a Complete Re-write)

M. Doerzbachcr Nuck::ir Fuels C. Bums Nuclc:ar Fuels

/i Cihah. - Renc!or Engineeting

~v-T. l3ement - Engineering Safety Analysis K. Mccoskey - Nuclear Fuels

,Jnn~jJrm;~

~---

A Johnson - NI" Sr. 1\\-fanaget Date:

11/16117 Date: 11/17/2017 om,. JJjdJ 7 Date: 11/17/17 Date: 11/17/2017 Date. 27NOV1 7 11/3()/1?

Date: ___ _

Enlon Nuclc11r - Nuclear Fuels P2C22 Core Operating Limits Report Table of Contents Revision History List of Tables 1.0 Tenns and Definitions 2.0 General Infonnation 3.0 MAPLHGR Limits 4.0 MCPR Limits 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 10.0 Asymmetric Feedwater Temperature Operation (AFTO) 11.0 Modes of Operation 12.0 Methodology 13.0 References COLR PEACH BOTTOM 2 Rev. 12 Page 2 of26 Page 3

4 5

6 7

8 12 14 15 16 17 19 24 25 25 Appendix A (Power/Flow Operating Map for MELLLA+ with TPO) 26

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report Revision Revision 12 Revision 11 Revision History COLR PEACH BOTTOM 2 Rev. 12 Page 3 of26 Description Revised for Rated Thermal Power of 4016 MWth New Issue for Cycle 22 Note that no revision bars were used, as this is a complete re-write based on new licensing.

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 12 Page 4 of26 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) 11 Table 4-4 SLO Flow Dependent MCPR Limits MCPR(F) 11 Table 5-1 Linear Heat Generation Rate Limits - U02 rods 12 Table 5-2 Linear Heat Generation Rate Limits - Gad rods 12 Table 5-3 Power Dependent LHGR Multiplier LHGRF AC(P) 13 Table 5-4 Flow Dependent LHGR Multiplier LHGRF AC(F) 13 Table 6-1 Rod Block Monitor Setpoints 14 Table 7-1 Turbine Bypass System Response Time 15 Table 7-2 Minimum Required Bypass Valves to Maintain System Operability 15 Table 8-1 Recirculation Pump Trip Response Time 16 Table 9-1 Automatic BSP Setpoints for the Scram Region 17 Table 9-2 Manual BSP Endpoints for Normal Feedwater Temperature 18 Table 9-3 Manual BSP Endpoints for Reduced Feedwater Temperature 18 Table 10-1 AFTO Power Dependent LHGR Multiplier LHGRF AC(P) 20F < FWT DEL TA :'.S 55F 20 Table 10-2 AFTO Flow Dependent LHGR Multiplier LHGRF AC(F) 20F < FWT DELTA :'.S 55F 20 Table 10-3 AFTO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTA :'.S 55F 21 Table 10-4 AFTO Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) 20F < FWT DELTA :'.S 55F 22 Table 10-5 AFTO Flow Dependent MCPR Limits MCPR(F) 20F < FWT DEL TA :'.S 55F 22 Table 10-6 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 P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 12 Page 5 of26 1.0 ABSP TERMS AND DEFINITIONS AFTO AFTOLFWH APRM ARTS BASE BOC BSP DSS-CD DTSP EOC EOOS EOR FFWTR FWHOOS FWT l-IFCL HTSP ICF ITSP LHGR LHGRFAC(F)

LHGRFAC(P)

LTSP MAPLHGR MCPR MCPR(F)

MCPR(P)

MELLLA MELLLA+

MSIVOOS NCL OLM CPR PLUOOS PROOS RBM RDF RPTOOS RTP RWE SLMCPR SLO SRVOOS TBVOOS TB SOOS TCV/TSVOOS TPO Automatic Backup Stability Protection Asymmetric Feedwater Temperature Operation Asymmetric Feedwater Temperature Operation Loss-of-Feed water Heating Average Power Range Monitor APRM and RBM Technical Specification Analysis 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.

Beginning Of Cycle Backup Stability Protection Detect and Suppress Solution - Confirmation Density Rod Block Monitor DO\\mscale Trip Setpoint 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 I 00% with recirculatlon system flow equal to I 00%. all control rods fully withdra\\m, all feedwater heating in service and equilibrium Xenon.

Final Feed water Temperature Reduction F eedwater Heaters Out of Service Feedwater Temperature High Flow Control Line Rod Block Monitor High Trip Setpoint Increased Core Flow Rod Block Monitor Intermediate Trip Setpoint Linear Heat Generation Rate ARTS LHGR thermal limit flow dependent adjustments and multipliers ARTS LHGR thermal limit power dependent adjustments and multipliers Rod Block Monitor Low Trip Setpoint Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio ARTS MCPR thermal limit flow dependent adjustments and multipliers ARTS MCPR thermal limit power dependent adjustments and multipliers Maximum Extended Load Line Limit Analysis Maximum Extended Load Line Limit Analysis Plus Main Steam Isolation Valve Out of Service Natural Circulation Line Operating Limit Minimum Critical Power Ratio Power Load Unbalance Out of Service Pressure Regulator Out of Service Rod Block Monitor Rated Drive Flow Recirculation Pump Trip Out of Service Rated Thermal Power Rod Withdrawal Error Safety Limit Minimum Critical Power Ratio Single Loop Operation Safety Relief Valve Out of Service Turbine Bypass Valve Out of Service Turbine Bypass System Out of Service Turbine Control Valve and/or Turbine Stop Valve Out of Service Thermal Power Optimization, also knO\\\\TI as Measurement Uncertainty Recapture

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report 2.0 GENERAL INFORMATION COLR PEACH BOTTOM 2 Rev. 12 Page 6 of26 This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 2 CYCLE 22 (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(l6).

This report provides cycle-specific Operating Limit MCPR, LHGR, MAPLHGR thennal limits, and related information for the following conditions:

All points in the operating region of the power/flow map including the MELLLA+ Region down to 85.2%

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

Increased Core Flow (!CF), 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) up to 55° F temperature reduction Final Feedwater Temperature Reduction (FFWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) up to 90° F temperature reduction (4th 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 OLMCPR is determined by the cycle-specific reload analyses in Reference 2. Rated LHGR values are obtained from the bundle-specific thennal-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 2 Cycle 22 core is comprised entirely of GNF2 fuel.

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report 3.0 MAPLHGR LIMITS

3. I Technical Specification Section 3.2. I, 3.3.4.2, 3.4. I and 3.7.6 3.2 Description COLR PEACH BOTTOM 2 Rev. 12 Page 7 of26 The limiting MAPLHGR value for the most limiting lattice of GNF2 fuel as a function of average planar exposure is given in Table 3-I. For single loop operation, a multiplier is used, which is shown in Table 3-2. The impact of AFTO on MAPLHGR is addressed in Section I 0.0.

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

Average Planar Exposure MAPLHGR Limit (GWD/ST)

(kW/ft) 0.0 13.78 I 7.52 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 P2C22 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 2 Rev. 12 Page 8 of26 The Operating Limit MCPR (OLM CPR) for GNF2 fuel is provided in Table 4-1. These values are detennined by the cycle-specific fuel reload analyses in Reference 2. The values in Table 4-1 assume a 45 ms or greater delay between the time of the first TCV movement and the time of first TSV movement following a turbine trip, as analyzed in Appendix H of 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 perfonnance 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). Table 4-1 is valid for a maximum FWT reduction of90°F (Reference 2).

Separate OLMCPR values are presented in Table 4-1 for the conditions listed in Section 11.0. 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 I 0.0; these values are bounding for non-AFTO conditions.

The ARTS-based power-dependent MCPR limits are provided in Table 4-2. Table 4-2 is valid for a maximum temperature reduction of90 °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.

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 12 Page 9 of26 TABLE4-l Operating Limit Minimum Critical Power Ratio (Reference 2)

SCRAM Cvcle Exposure Time

< EOR-4096

, EOR - 4096 EOOS Combination Option<1>

MWd/ST MWd/ST B

1.38 1.42 BASE A

1.44 1.50 B

1.42 1.44 BASE SLO A

1.46 1.52 B

1.41 1.44 RPTOOS A

1.58 1.61 B

1.43 1.46 RPTOOS SLO A

1.60 1.63 B

1.38 1.42 PR/PLUOOS A

1.44 1.50 B

1.42 1.44 PR/PLUOOS SLO A

1.46 1.52 B

1.42 1.47 TB SOOS A

1.51 1.56 B

1.44 1.49 TBSOOSSLO A

1.53 1.58 (I) When Tau does not equal 0 or I, use linear interpolation.

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report TABLE 4-2 COLR PEACH BOTTOM 2 Rev. 12 Page 10 of26 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 2:26.3 40 55 65 85 100 of 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 2.69 2.69 2.62 Base SLO 1.392 1.288 1.237 1.130 1.067 1.000

> 60 3.01 3.01 2.85

~60 2.67 2.67 2.60 RPTOOS 1.392 1.288 1.237 1.130 1.067 1.000

> 60 2.99 2.99 2.83

~60 2.69 2.69 2.62 RPTOOS SLO 1.392 1.288 1.237 1.130 1.067 1.000

> 60 3.01 3.01 2.85

~60 2.67 2.67 2.60 PR/PLUOOS 1.392 1.288 1.237 1.210 1.147 1.000

> 60 2.99 2.99 2.83 PR/PLUOOS SLO

~60 2.69 2.69 2.62 1.392 1.288 1.237 1.210 1.147 1.000

> 60 3.01 3.01 2.85

~60 3.64 3.64 3.25 TB SOOS 1.399 1.323 1.237 1.155 1.079 1.000

> 60 4.15 4.15 3.78

~60 3.66 3.66 3.27 TBSOOS SLO 1.399 1.323 1.237 1.155 1.079 1.000

> 60 4.17 4.17 3.80

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report TABLE 4-3 COLR PEACH BOTTOM 2 Rev. 12 Page 11 of26 Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feedwater Heating)

Reference 2 Core Flow

(%rated) 0.0 1.74 30.0 1.57 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 1.27 110.0 1.27

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report 5.0 LHGR LIMITS COLR PEACH BOTTOM 2 Rev. 12 Page 12 of26 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 the GNF2 fuel type 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 of90° 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 ofrecirculation 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 I 0.0. 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. 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 4 and 10)

Fuel Type LHGRLimit GNF2 See Appendix B of Reference 4 TABLE 5-2 Linear Heat Generation Rate Limits - Gad rods (References 4 and 10)

Fuel Type LHGRLimit GNF2 See Appendix B of Reference 4

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report TABLE 5-3 COLR PEACH BOTTOM 2 Rev. 12 Page 13 of26 Power Dependent LHGR Multiplier LHGRFAC(P)

(Symmetric Feedwater Heating)

(Reference 2)

Core Flow Core Thermal Power (% of rated)

EOOS

(%of Combination rated)

Base

60

> 60 Base SLO

60

>60 RPTOOS

60

>60 RPTOOS SLO

60

> 60 PR/PLUOOS

60

> 60 PR/PLUOOS SLO

60

>60 TB SOOS

60

>60

60 TBSOOSSLO

> 60 EOOS Combination Dual Loop Single Loop 0

22.6

<26.3 2:26.3 40 55 65 LHGRFAC(P) Multiplier 0.508 0.508 0.522 0.620 0.696 0.508 0.508 0.522 0.508 0.508 0.522 0.620 0.696 0.508 0.508 0.522 0.508 0.508 0.522 0.508 0.508 0.522 0.620 0.696 0.508 0.508 0.522 0.508 0.508 0.522 0.620 0.696 0.508 0.508 0.522 0.508 0.508 0.522 0.620 0.696 0.508 0.508 0.522 0.508 0.508 0.522 0.620 0.696 0.397 0.397 0.442 0.397 0.397 0.417 0.620 0.655 0.397 0.397 0.442 0.620 0.655 0.397 0.397 0.417 TABLE 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)

(Symmetric Feedwater Heating)

(Reference 2)

Core Flow(% of rated) 0 30 33.6 70 LHGRFAC(F) Multiplier 0.506 0.706 0.730 0.973 0.506 0.706 0.730 0.730 0.751 0.817 0.751 0.817 0.751 0.817 0.751 0.817 0.751 0.817 0.751 0.817 0.714 0.817 0.714 0.817 80 1.000 0.730 85 0.930 0.930 0.930 0.930 0.930 0.930 0.930 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 P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 12 Page 14 of26 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 and 8. These values correspond to the OLMCPR values provided in Table 4-1.

Power Level LTSP

!TSP HTSP

!NOP TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 8)

Allowable Valuel'>

118.2%

113.4%

108.4%

NIA MCPR Limit

< 1.83 <2>

< 1.50 <3>

< 1.83 (2)

< 1.50 (3)

< 1.83 (2)

< 1.50 (3)

< 1.83 (2)

< 1.50 <3>

(I) These setpoints (with RBM filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated RWE MCPR limit which is less than or equal to the minimum cycle OLM CPR based on other events (see COLR References 2 and 8).

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

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

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 12 Page 15of26 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 per Reference 12.

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(!)

Maximum time after initial turbine inlet valve movement(!) for bypass valve position to reach 80% offull flow (includes the above delay time)

(I) First movement of any TSV or 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 P2:22.6%

7

Exelon Nuclear-Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 12 Page 16 of26 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 P2C22 Core Operating Limits Report 9.0 ST ABILITY 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 2 Rev. 12 Page 17 of26 Per Reference 2, the Cycle 22 DSS-CD SAo Setpoint was confirmed to be I. I 0 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 Table 9-3, respectively. Table 9-3 is intended for feedwater temperatures I 0-90°F below nominal.

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

Parameter Symbol Value Slope of ABSP APRM flow-mTtip 1.62 biased trip linear segment.

ABSP APRM flow-biased trip setpoint power intercept.

Constant Power Line for Trip PssP-Ttip 39.8 %RTP from zero Drive Flow to Flow Breakpoint value.

ABSP APRM flow-biased trip setpoint drive flow intercept.

WssP-Trip 46.7 %RDF Constant Flow Line for Trip.

Flow Breakpoint value WssP-Break 25.0 %RDF

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report TABLE 9-2<1)

COLR PEACH BOTTOM 2 Rev. 12 Page 18 of26 Manual BSP Endpoints for Normal Feedwater Temperature (Reference 2)

Endpoint Power(%)

Flow(%)

Definition Al 73.2 49.3 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 Normal and Reduced Feedwater Temperature is defined by the MELLLA boundary line, per Reference 2.

TABLE 9_3<5>

Manual BSP Endpoints for Reduced Feedwater Temperature (Reference 2)

Endpoint Power(%)

Flow(%)

Definition Al' 63.4 50.0 Scram Region Boundary, HFCL Bl' 33.8 30.6 Scram Region Boundary, NCL A2' 65.0 52.0 Controlled Entry Region Boundary, HFCL B2' 27.6 30.I 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.

(I) Station may elect to place additional administrative margin on the endpoints provided in Table 9-2 and Table 9-3.

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 12 Page 19 of26 10.0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION (AFTO)

Asymmetric feedwater heating is the result of the specific configuration of the feed water 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 penalties due to a 30 MONICORE upgrade. AFTO is defined as operation in a feedwater heater/string configuration that results in a specified threshold difference as described in Reference 9. To simplify the implementation of the AFTO limits, only the maximum AFTO penalties indicated in Table 13 of Reference 9 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, for a difference between 20 and 55°F there is a 4% LHGR/MAPLHGR penalty and a 3% MCPR penalty, and thermal limits are unanalyzed for a difference above 55°F.

10.1 LHGR LIMITS The ARTS-based LHGR power-dependent multipliers for AFTO operation are provided in Table 10-1. The flow-dependent multipliers for AFTO in DLO are provided in Table 10-2. The power-and flow-dependent LHGR multipliers were obtained from Reference 2 and were adjusted with the appropriate penalties as per Reference 9. PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS values were obtained by taking the most limiting values of the two EOOS conditions (Reference 11 ). 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 9 are applied to the thermal limits. Additionally, no LHGR penalties are required for AFTO while in SLO as previously discussed.

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report TABLE 10-1 COLR PEACH BOTTOM 2 Rev. 12 Page 20 of26 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTA~ 55F (Asymmetric Feedwater Heating)

(References 2, 9 and 11)

Core Core Thermal Power(% of rated)

EOOS Combination Flow 0

22.6

<26.3

~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 0.893

> 60 0.488 0.488 0.501 s 60 0.488 0.488 0.501 RPTOOS 0.595 0.668 0.721 0.784 0.893

> 60 0.488 0.488 0.501 s 60 0.488 0.488 0.501 PR/PLUOOS 0.595 0.668 0.721 0.784 0.893

> 60 0.488 0.488 0.501 s 60 0.381 0.381 0.424 TB SOOS 0.595 0.629 0.685 0.784 0.893

> 60 0.381 0.381 0.400 s 60 0.381 0.381 0.424 PR/PLUOOS + TBSOOS 0.595 0.629 0.685 0.784 0.893

>60 0.381 0.381 0.400 S60 0.488 0.488 0.501 PR/PLUOOS + RPTOOS 0.595 0.668 0.721 0.784 0.893

> 60 0.488 0.488 0.501 TABLE 10-2 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTAS 55F (Asymmetric Feedwater Heating)

(References 2 and 9)

Core Flow (% of rated)

EOOS Combination 0

I 30 I

33.6 I

70 I

80 I

110 LHGRFAC(F) Multiplier 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 P2C22 Core Operating Limits Report I 0.2 MCPR LIMITS COLR PEACH BOTTOM 2 Rev. 12 Page 21 of26 The OLMCPRs during asymmetric feedwater temperature operation with a feedwater temperature difference greater than 20°F are provided in Table I 0-3. 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 Reference 2 and were adjusted with a penalty for feedwater temperature difference greater than 20°F as per Reference 9. The values in Table I 0-3 assume a 45 ms or greater delay between the time of the first TCV movement and the time of first TSV movement following a turbine trip. PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS values were obtained by taking the most limiting values of the two EOOS conditions (Reference 11). No MCPR penalties are required for asymmetric temperature differentials less than or equal to 20 °F.

TABLE 10-3 AFTO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTA :S 55F (Asymmetric Feedwater Heating)

(References 2, 9 and 11)

SCRAM Cycle Exposure Time

<EOR-4096 :::_EOR-4096 EOOS Combination OptionC*>

MWdlST MWdlST BASE B

1.42 1.46 A

1.48 1.55 RPTOOS B

1.45 1.48 A

1.63 1.66 PR/PLUOOS B

1.42 1.46 A

1.48 1.55 TB SOOS B

1.46 1.51 A

1.56 1.61 PR/PLUOOS +TB SOOS B

1.46 1.51 A

NIA NIA PR/PLUOOS + RPTOOS B

1.45 1.48 A

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

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report TABLE 10-4 COLR PEACH BOTTOM 2 Rev. 12 Page 22 of26 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 20F < FWT DELTA~ 55F (Asymmetric Feedwater Heating)

(References 2, 9 and 11)

Core Core Thermal Power(% of rated)

EOOS Combination Flow 0

22.6

<26.3 2:26.3 40 55 65 85 100

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

60 2.75 2.75 2.68 Base 1.392 1.288 1.237 1.130

> 60 3.08 3.08 2.91

60 2.75 2.75 2.68 RPTOOS 1.392 1.288 1.237 1.130

>60 3.08 3.08 2.91

60 2.75 2.75 2.68 PR/PLUOOS 1.392 1.288 1.237 1.210

>60 3.08 3.08 2.91

60 3.75 3.75 3.35 TB SOOS 1.399 1.323 1.237 1.155

>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

> 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

>60 3.08 3.08 2.91 TABLE 10-5 AFTO Flow Dependent MCPR Limits MCPR(F) 20F < FWT DELTA~ 55F (Asymmetric Feedwater Heating)

(References 2 and 9)

Flow MCPR(F)

(%rated)

Limit 0.0 1.79 30.0 1.62 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 P2C22 Core Operating Limits Report 10.3 MAPLHGR LIMITS COLR PEACH BOTTOM 2 Rev. 12 Page 23 of26 An appropriate penalty must be applied to MAPLHGR limits under asymmetric feedwater temperature operation (AFTO) for varying temperature differentials as per Reference 9. The reduction factor listed in Table I 0-6 is the maximum penalty for the full range of analyzed FWT mismatches, bounding all smaller temperature deltas.

TABLE 10-6 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)

(References 2 and 9)

AFTO Reduction Factor 20F < FWT DELTA ::s 55F I 0.960

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating L1m1ts Report COLR PEACH BOTTOM 2 Rev. 12 Page 24 of26 11.0 MODES OF OPERATION The following conditions are supported by the Peach Bottom 2 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 ofoperation 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 Base'.2 TB SOOS RPTOOS PLUOOS PROOS PR/PLUOOS and TBSOOS PR/PLUOOS and RPTOOS TABLE 11-1 Modes of Operation (Reference 2)

Supported Scram Supported Recirculation Speed Option Loop Operation A orB DLO or SL03 A orB DLO or SL03 A or B DLO or SL03 A orB DLO or SL03 A or B DLO or SL03 B

DLO B

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

Condition TBVOOS SRVOOS MSIVOOS 5 TCV/TSVOOS5 1 The 'Base' condition includes the options listed in Table 11-2.

Supported SFTO/AFTO SFTO or AFTO SFTO or AFTO SFTO or AFTO SFTOor AFTO SFTO or AFTO AFT04 AFT04 2 The 'Base' condition includes operation with FWHOOS/FFWTR. Operation not permitted in the MELLILA+ 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 P2C22 Core Operating Limits Report 12.0 METHODOLOGY COLR PEACH BOTTOM 2 Rev. 12 Page 25 of26 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:

1.

"General Electric Standard Application for Reactor Fuel", Global Nuclear Fuel Document No. NEDE-240 I l-P-A-25, August 2017 and U.S. Supplement NEDE-24011-P-A-25-US, August 2017.

13.0 REFERENCES

I. "Technical Specifications for Peach Bottom Atomic Power Station Unit 2", Exelon Document, Docket No. 50-277, License No. DPR-44.

2.

Global Nuclear Fuel Document "Supplemental Reload Licensing Report for Peach Bottom Unit 2 Reload 21 Cycle 22 Mid-Cycle Thermal Power Optimization (TPO), GNF Document No. 004N2488, Revision 0, October 2017.

3. Global Nuclear Fuel Document "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-25, August 2017 and U.S. Supplement NEDE-24011-P-A-25-US, August 2017.
4.

Global Nuclear Fuel Document NEDC-33270P Rev. 6, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," March 2016.

5.

General Electric Hitachi Document 001N2494-RO, "Peach Bottom EPU Evaluation ofFeedwater Temperature vs.

Reactor Power for Feedwater Temperature Conditions ofNominal Rated, FWHOOS (Nominal -55' F) and FFWTR (Nominal -90°F)", July 2014. This document is searchable in Exelon EDMS under document number "PEAM-EPU-1" Rev. OA.

6. General Electric Hitachi Document NED0-33873, "Safety Analysis Report for Peach Bottom Atomic Power Station, Units 2 and 3, Thermal Power Optimization", Revision 0, February 2017.
7. PECO Calculation PE-0173, "Determination of Total Time Required to Initiate the Trip Signal to the EOC-RPT Circuit Breakers Trip Coils and to Complete the Recirculation Pump Trip", Rev. 1 dated 12/22/98.
8.

Exelon Calculation PE-0251, Revision 4, "Provide Allowable Values (AV) and Nominal Trip Setpoints (NTSP) for Various Setpoint Functions of the NUMAC PRNM System" dated 7/31 /17.

9.

General Electric Hitachi Document 00 I N6733-R2, Final Evaluation Report Exelon Nuclear Generating Company LLC, Peach Bottom Units 2 & 3, TPO with EPU/MELLLA+ PCR E03: Asymmetric Feedwater Temperature Operation forTPO with EPU/MELLLA+", Revision 2, September2017. This document is searchable in Exelon EDMS under document number "PEAM-MUR-PCR-E03" Rev. 0.

10. Global Nuclear Fuel Document 002N6786, "Fuel Bundle Information Report for Peach Bottom Unit 2 Reload 21 Cycle 22", Revision 0, September 2016.
11. Global Nuclear Fuel Document 0000-0135-9000-R2, Peach Bottom Atomic Power Station Units 2 and 3 TRACG Implementation for Reload Licensing Transient Analysis", dated June 2017.
12. Exelon TOOi ENSAF ID# ES 1700008, Rev. 0, Final Resolved OPL-3 Parameters for Peach Bottom Unit 2 Cycle 22 TPO", 5/30/2017.

Exelon Nuclear-Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 12 Page 26 of26 APPENDIX A POWER/FLOW OPERA TING MAP FOR MELLLA+ with TPO (Reference 6)

Core Flow (Mihm/hr) 0 10 20 30 40 50 60 70 80 90 100 110 120 120 r ~ --*-*-~;;;~;;;;t ---*-.

1

~

1

~~:.i:-~~~;* -*- ~-:i~~~*~;~;-.-.---*--*-*--.... *-- *-*-~*---*-*....._.._.--*-* l 4819 1 Pt Ccre Flow' 'lb l'l:>wet. 'lb 100\\u CLTP

" 3951 MWt 110 ~.,.!£E. Increa$ed Core Flow Reg.on

!o&lb Core Flow

" 102. S Mlb/hr 4418

_A_ tlab.Jral_Cu"!_~tioo [ ____ _

j __!!_ 30% MlnimU'l'I Pu~

,-=----

  • 100 J._f; ___ _J_!O __, __ Ji.Q__

! 0 101.S 100.0 l r:t 99.0 96.4 l l 100.0 98.4 90 *;

E 100.0 100.0 I F 110.0 100.0

' F' 110.0 I

98~.4 ___,

80 -; T 110.0

--21.0 i H --lOOAO 21.0 i _!_ ___

37.4 2.!_.o __

70

  • l 85.2 100 1-------*

J _!_

83.0 _I

~~--

  • K 55.o n.s 60 ~ L 55.0 67.3
M 56.0 67.3 i

50 f 40 l f l 30.! f 20 1 1

10

_../

I 0

0 10 20 30 40 BSP Boundary I ta' uanon ln1erlock I 50 60 70 80 90 100 Core Floll (%)

~01~ \\l\\\\f !

.\\9!'1'.U\\\\t 4016 3614 110 i l f

r r I I l l 3213 2811 2410 2008 1606 1205 803 402

! 0 120

~

~

-=

~

~

E~clnn Nucle~*r - Nuch!:1r FuL*I-=

P3C:!2 C"ur~ Opcra1ing Lnml' Rcpwt COLR PEACH BOTTOM 3 Rcv.13 Page I of 24 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM A TO MIC POWER ST A TI ON UNIT 3 RELOAD 21, CYCLE 22 Prepared By:

Reviewed By: ~/-~

Matthew Miller Reactor En1:,rineering Rov;,,,.dBy'

~

~

Trm*is Bem*e~l--E~gT;~-eri;;g s~fet-y"/;:;-1-;lysis independent Review By:

J~~

Tamara Stathes Nuclear Fuels ApprovedBy: ___ ~~

0 SQR By:

Armando Johnson NF Senior Manager J~-4'--_,,,~tio_n_Q-~-ia-li-fi~-d~

Date: 11/1/2017 Date:

J _VID/J()//

Date: 11i2i17 Date:

11 /8/17 Date: 13NOV17_

1/13/ ')

Date:

1

Exelon l'luclear - Nuclear Fuels P3C22 Core Operutmg Lim i t~ Report COLR PEACH BOTTOM 3 Rev. 13 Page 2 of24 Table of Contents Page 1.0 Tenns and Definitions 5

2.0 General Information 6

3.0 MAPLHGR Limits 7

4.0 MCPR Limits 8

5.0 LHGR Limits 12 6.0 Rod Block Monitor Setpoints 14 7.0 Turbine Bypass Valve Parameters 15 8.0 EOC Recirculation Pump Trip (EOC-RPT) Operability 16 9.0 Stability Protection 17 10.0 Asymmetric Feedwater Temperature Operation (AFTO) 19 11.0 Modes of Operation 22 12.0 Methodology 22 13.0 References 23 Appendix A (Power/Flow Operating Map for MELLLA+)

24

Exelon Nuclear - Nuclear Fuels P3C22 Core Operating l.11111ts R~port Revision Revision 13 Revision 12 Revision History COLR PEACH BOTTOM 3 Rev. 13 Page 3 of24 Description Update of Cycle 22 COLR to allow for implementation of Thermal Power Optimization/Measurement Uncertainty Recapture (TPO/MUR) to 4016 MW1 New issue for Cycle 22

Exelon i'iurlear - Nuclear Fuels P3C'22 Cor~ Opcmtmg I 111111~ R~port COLR PEACH BOTTOM 3 Rev. 13 Page 4 of24 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 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 7-1 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 Automatic 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

IO 11 11 12 12 13 13 14 15 15 16 17 18 18 Table 10-1 AFTO Power Dependent LHGR Multiplier LHGRF AC(P) 20°F < FWT DELTA~ 55°F 19 Table 10-2 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20°F < FWT DELTA~ 55°F 20 Table 10-3 AFTO Operating Limit Minimum Critical Power Ratio 20°F < FWT DELTA~ 55°F 20 Table I 0-4 AFTO Power Dependent MCPR Limit Adjustments and Multipliers 21 MCPR(P) 20°F < FWT DELTA~ 55°F Table I 0-5 AFTO Flow Dependent MCPR Limits MCPR(F) 20°F < FWT DELTA~ 55°F 21 Table 10-6 AFTO MAPLHGR Reduction Factor 21 Table 11-1 Modes of Operation 22 Table 11-2 EOOS Options Included in 'Base' Conditions 22

Exelon Nuclear - Nuclear Fuels P3C ~2 Core Operating Limits Report 1.0 Terms and Definitions COLR PEACH BOTTOM 3 Rev. 13 Page 5 of24 ABS!'

AFIO AFTO Lf'WH APRM AR rs BASE BOC BS!'

DSS-CD DTSP EOC EOOS EOR FFWTR FWHOOS f'WT Hf'CL llTSP ICF ITSP LllGR LI IGRF AC(F)

Ll-IGRFAC(I')

LTSP MAPLHGR MCPR MCPR(F)

MCPR(P)

MELL LA MELI.LA+

MSIVOOS NCL OLM CPR PLUOOS PROOS RBM RDf' RP TO OS RTP RWE SLMCPR Sl.O TB SOOS TCV/TSVOOS Automatic Backup Stabilit) Protection As) mmetric Feed water I emperature Operation Asymmetric f'ccd\\\\atcr Temperature Operation Loss-ot~f'eed\\\\ater Heating Average Power Range Monitor APRM and RBM Technical Specification Analysis rhe **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 I 1-2 as well as operation with f'WHOOS!f'FWTR.

Beginning Of Cycle Backup Stability Protection Detect and Suppress Solution - Confirmation Density Rod Block Monitor Downscale Trip Setpoint End of Cycle Equipment Out of Service. An analyzed option that assumes certain eljuipment to be non-operational.

End of Rated. The cycle exposure at which reactor power is equal to I 00% \\\\ ith recirculation system

!low equal to I 00%. all control rods fully withdra\\\\11, all !Ced water heating in sen ice and equilibrium Xenon.

Final Feed\\Hlter Temperature Reduction Feed water Heaters Out of Service Feedwater Temperature I ligh f'low Control Line Rod Block Monitor I ligh Trip Setpoint Increased Core Flo\\\\

Rod Block Monitor Intermediate Trip Sctpoint Linear I I cat Generation Rate AR rs LI IGR thermal limit llcl\\\\ dependent adjustments and multipliers ARTS LHGR thennal limit po\\\\er dependent adjustments and multipliers Rod Block Monitor Low Trip Setpoint Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio ARTS MCPR thennal limit flow dependent adjustments and multipliers ARTS MCPR thermal limit power dependent adjustments and multipliers Maximum Extended Load Linc Limit Analysis Mm..imum Extended Load Linc Limit Analysis Plus Main Steam Isolation Valve Out of Service Natural Circulation Linc Operating Limit Minimum Critical Power Ratio Power Load Unbalance Out ofServicc Pressure Regulator Out of Service Rod Block Monitor Rated Drive Flow Recirculation Pump Trip Out of Sen ice Rated ll1ermal Power Rod Withdrawal Error Safe!) Limit Minimum Critical Po\\\\ er Ratio Single Loop Operation Turbine B)pass System Out of Sen ic.:

Turbine Control Val' e and/or Turbine Stop Vahe Out of Sen ice

Exelon Nuclear - Nuclear Fuels P3C22 Core Operating I.i1111ts Report 2.0 General Information COLR PEACH BOTTOM 3 Rev. 13 Page 6 of24 This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 3 CYCLE 22 (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 thennal 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) the1mal 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( 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 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 (4111 and 5111 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 ofGNF2 fuel.

Exelon Nuclear - Nuclear Fuels P3C:!2 Core Operntmg l.imit5 Report 3.0 MAPLHGR LIMITS 3.1 Technical Specification Section 3.2. L 3.3.4.2. 3.4.1 and 3.7.6 3.2 Description COLR PEACH BOTTOM 3 Rev. 13 Page 7 of24 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 of AFTO on MAPLHGR is addressed in Section 10.0.

TABLE3-1 MAPLHGR 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 P3C22 Core Operutmg Lim i t~ 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. 13 Page 8 of24 The Operating Limit MCPR (OLMCPR) for GNF2 fuel is provided in Tables 4-1 and 4-2. These values are dete1mined 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 OLMCPR value if Tau is between 0.0 (Tau Option 8) and 1.0 (Tau Option A). Table 4-1 is valid for a maximum FWT reduction 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 of90 °F for FFWTR operation (bounding for FWHOOS operation). 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 I 0.0. 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 l\\uclenr - Nuclear Fuels P3C22 Core Operating l.11111ts Report TABLE4-1 COLR PEACH BOTTOM 3 Rev. 13 Page 9 of24 Operating Limit Minimum Critical Power Ratio (Reference 2)

SCRAM Cycle Exoosure Time

<EOR-3915

~ EOR-3915 EOOS Combination Option<*>

MWd/ST MWd/ST B

1.40 1.42 BASE B*(3) 1.38 1.41 A

1.48 1.50 BASE SL0'2>

B 1.43 1.45 A

1.51 1.53 RPTOOS B

1.43 1.45 A

1.60 1.62 RPTOOS SL012 >

B 1.46 1.48 A

1.63 1.65 PR/PLUOOS B

1.40 1.42 A

1.48 1.50 PR/PLUOOS SLOt2>

B 1.43 1.45 A

1.51 1.53 TB SOOS B

1.44 1.47 A

1.53 1.56 TBSOOS SLO 12i 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 operation, the MCPR operating limit is 0.03 higher than the two-loop value (Refercmce '.:).

(3) 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 i'iuclcnr-Nuclear Fuels P3C22 Core Operating l.11rnt~ Report TABLE 4-2 COLR PEACH BOTTOM 3 Rev. 13 Page 10of24 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

(%of rated 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

~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

> 60 3.02 1.392 1.288 1.237 1.130 1.067 1.000 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 3.25 TB SOOS 1.399 1.323 1.237 1.155 1.079 1.000

> 60 4.15 4.15 3.78

~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 l\\uclear-Nuclear Fuels P3C21 Core Operating l.im1ts Report TABLE 4-3 COLR PEACH BOTTOM 3 Rev. 13 Page 11 of24 Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feeclwater Heating)

(Reference 2)

~~- -.::'!ow MCPR(F)

,-:U &KU:d)

Limit 0.0 1.74 30.0 1.57 86.0 1.25 110.0 1.25 TABLE4-4 SLO Flow Dependent MCPR Limits MCPR(F)

(Symmetric Feeclwater Heating)

(Reference 2)

Core Flow MCPR(F)

(%rated)

Limit 0.0 1.77 30.0 1.60 86.0 1.28 110.0 1.28

Exelon l'iuclenr - Nuclear Fuels P3C22 Core Operating l.111111~ Report 5.0 LHGR LIMITS COLR PEACH BOTTOM 3 Rev. 13 Page 12of24 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 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 of90° 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 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 IO; 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 4 and 11)

Fuel Type LHGRLimit GNF2 See Appendix B of Reference 4 TABLE 5-2 Linear Heat Generation Rate Limits - Gad rods (References_. and 11)

Fuel Type LHGR Limit GNF2 See Appendix B of Reference 4

Exelon Nuclear - Nuclear Fuels P3C:!2 Core Opernting l.i1111ts Report COLR PEACH BOTTOM 3 Rev. 13 Page 13 of24 TABLE 5-3 Power Dependent LHGR Multiplier LHGRFAC(P)

(Symmetric Feedwater Heating)

(Reference 2)

Core Thermal Power (% of rated)

Core Flow EOOS Combination (%of rated) 0 22.6

<26.3 2::26.3 40 55 Base Base SLO RPTOOS RPTOOS SLO PR/PLUOOS PR/PLUOOS SLO TBSOOS TBSOOS SLO LHGRFAC(P) Multiplier

s 60 0.508 0.508 0.522 0.620 0.696

>60 0.508 0.508 0.522

s 60 0.508 0.508 0.522 0.620 0.696

> 60 0.508 0.508 0.522

s 60 0.508 0.508 0.522 0.696 0.620

>60 0.508 0.508 0.522

s 60 0.508 0.508 0.522 0.696 0.620

>60 0.508 0.508 0.522

s 60 0.508 0.508 0.522 0.620 0.696

> 60 0.508 0.508 0.522

s 60 0.508 0.508 0.522 0.620 0.696

>60 0.508 0.508 0.522

s 60 0.397 0.397 0.442 0.620 0.655

> 60 0.397 0.397 0.417

s 60 0.397 0.397 0.442 0.620 0.655

> 60 0.397 0.397 0.417 TABLE 5-4 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 0.71 4 0.714 EOOS Combination 0

30 33.6 70 80 LHGRFAC(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 l\\uclear - Nuclear Fuel\\

P3C22 Core Operating L.im1t~ Report COLR PEACH BOTTOM 3 Rev. 13 Page 14 of24 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.

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

Allowable Value! 1' 118.2%

113.4%

108.4%

N/A MCPRLimit

< 1.83 (l)

< 1.50 {3)

< 1.83 (~)

< 1.50 (3)

< 1.83 (l)

< 1.50 (J)

< 1.83 12>

< 1.50 (})

(1) These setpoints (with RBM filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated P.WE MCPR limit which is less than or equal to the minimum cycle OLMCPR based on other events (see COLR References 2 and 9).

(2) This is the t-!CPR limit (given THERMAL POWER is~ ~B

. 4% and< 90%) below which the RBM is required to be OPERABLE (see COLR Reference 2 and TS Table 3.3.2.1-1).

(3) This is the MCPR limit (given THERMJl.L POWER is ~ 90%) below which the RBM is required to be OPER.l\\BLE (see COLR Reference 2 and TS Table 3. 3. 2.1-1).

Exelon Nuclear - Nuclear Fuels P3C22 Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 13 Page 15 of24 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 12)

Maximum delay time before start of bypass valve opening following initial turbine inlet valve movement0 '

Maximum time after initial turbine inlet valve movement' 1' for bypass valve position to reach 80% offull flow (includes the above delay time)

(I)

First movement ofm1y TSV Q! uny TCV (\\\\hichcver 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 P3C22 Core Operating Limits Report COLR PEACH BOTTOM 3 Rev. 13 Page 16 of24 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 ji-0111 *when the turbine valves (turhine control mlve 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 Nurlear - :"luclear Fuels P3C:!2 Core Operating I i1111ts Report 9.0 ST ABILITY PROTECTION 9.1 Technical Specification Section 3.3.1. I, Table 3.3.1. I-I Function 2.f 9.2 Description COLR PEACH BOTTOM 3 Rev. 13 Page 17 of24 Per Reference 2, the Cycle 22 DSS-CD SAo 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 I 0-90°F below nominal.

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

Parameter Symbol Value Slope of ABSP APRM flow-111Tnp 1.37 biased trip linear segment.

ABSP APRM flow-biased trip setpoint power intercept.

Constant Power Line for Trip PBsP-Tnp 39.3 %RTP from zero Drive Flow to Flow Breakpoint value.

ABSP APRM flow-biased trip setpoint drive flow intercept.

WBsP-Tnp 46.5 %RDF Constant Flow Line for Trip.

Flow Breakpoint value WBSP-Break 20.0 %RDF

Exelon :"iudcar - Nuclear Fuel~

1'3C22 Core Operating l.11111ts Report TABLE 9-2( 11 COLR PEACH BOTTOM 3 Rev. 13 Page 18 of 24 Manual BSP Endpoints for Normal Feedwater Temperature (Reference 2)

Endpoint Power(%)

Flow ('Yo)

Definition Al 73.1 49.2 Scram Region Boundary, HFCL Bl 40.0 31.0 Scram Region Boundary, NCL A2 63.5 50.0 Controlled Entry Region Boundaiy. HFCL B2 27.6

30. I Controlled Entry Region Boundmy. NCL Note: The 13SP 13oundar) for Nonna! and Reduced Feedwater Temperature is defined b) the MELLLA boundar) line. per Re forence 2.

TABLE 9_3(1>

Manual BSP Endpoints for Reduced Feedwater Temperature (Reference 2)

Endpoint Power(%)

Flow(%)

Definition Al 63.0 49.4 Scram Region Boundary. HFCL Bl 33.8 30.6 Scram Region Boundary, NCL A2 65.3 52.4 Controlled Entry Region Boundary, HFCL B2 27.6 30.1 Controlled Entry Region Boundary, NCL Note: The BSP Boundary for Nonna! and Reduced Feed\\\\atcr Temperature is de tined b; the MELL LA 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 l'iuclear-Nuclear Fuels P3C22 Core Operating Lim it~ Report COLR PEACH BOTTOM 3 Rev. 13 Page 19 of24 10.0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION (AFTO)

Asymmetric feed water 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 feedwater flows entering the opposite sides of the reactor vessel. This temperature mismatch may result in e1Tors in the thermal limit values calculated by the core monitoring system. Thermal limit values for all conditions and events are impacted by these e1rnrs excluding SLO conditions. The station no longer requires SLO AFTO penalties due to a 30 MON I CORE upgrade. 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 Ref. 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% LHGR/MAPLHGR penalty and a 3% MCPR penalty, and thermal limits are unanalyzed for a difference above 55°F.

LHGRLIMITS The ARTS-based LHGR power-dependent multipliers for AFTO operation are provided in Table 10-1. The flow-dependent multipliers for AFTO in DLO are provided in Table 10-2. The power-and flow-dependent LHGR multipliers were obtained from Reference 2 and were adjusted with the appropriate penalties 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 the1mal limit penalty is 20 °F.

TABLE 10-1 AFTO Power Dependent LHGR Multiplier LHGRFAC{P) 20°F < FWT DELTA~ 55°F (Asymmetric Feedwater Heating)

(References 2, 8, and 10)

Core Core Thermal Power (fllo of rated)

EOOS Combination Flow 0

22.6

<26.3 2'.26.3 40 55 65

(%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 PR/PLUOOS 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 PR/PLUOOS + TBSOOS 0.595 0.629 0.685 0.784

>60 0.381 0.381 0.400

~60 0.488 0.488 0.501 PR/PLUOOS + RPTOOS 0.595 0.668 0.721 0.784

> 60 0.488 0.488 0.501 85 0.893 0.893 0.893 0.893 0.893 0.893 100 I I

0.960 0.960 0.960 0.960 0.960 0.960

Exelon l\\uclear - Nuclear Fuels P3C2:! Core Operatmg Lim i l~ Report COLR PEACH BOTTOM 3 Rev. 13 Page 20 of24 TABLE 10-2 AFTO Flow Dependent LHGR Multiplier LHGRF AC(F) 20°F < FWT DELTA~ 55°F (Asymmetric Feedwater Heating)

(References 2 and 10)

Core Flow (01.1 of rated)

EOOS Combination 0

I 30 I

33.6 I

70 I

80 I

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

0.934 I

0.960 I 0.960 MCPRLIMITS The OLMCPRs during asymmetric feedwater temperature operation with a feedwater temperature difference greater than 20°F are 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. 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 20°F.

TABLE 10-3 AFTO Operating Limit Minim um Critical Power Ratio 20°F < FWT DELTA~ 55°F (Asymmetric Fecd*water Heating)

(References 2, 8, and 10)

SCRAM Cycle Exposure Time

<EOR-3915

EOR - 3915 EOOS Combination Option<))

MWd/ST MWd/ST B

1.44 1.46 BASE 8*1'.! J 1.42 1.45 A

1.52 1.55 RPTOOS B

1.47 1.49 A

1.65 1.67 PR/PLUOOS B

I.44 1.46 A

1.52 1.55 TB SOOS B

1.48 1.51 A

1.58 1.6 I PR/PLUOOS + TBSOOS B

1.48 1.51 A

NIA NIA PR/PLUOOS + RPTOOS B

1.47 1.49 A

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

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

Exelon Nuclear - Nuclear Fuels P3C22 Core Operating I.i1111t5 Report TABLE 10-4 COLR PEACH BOTTOM 3 Rev. 13 Page 21 of24 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 20°F < FWT DEL TA :'.S 55°F (Asymmetric Feedwater Heating)

(References 2, 8, and 10)

Core Core Thermal Power(% of rated)

EOOS Combination Flow 0

22.6

<26.3 2::26.3 40 55 65 85

(%of 100 I I

rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp Base

~60 2.75 2.75 2.68 1.392 1.288 1.237 1.130

> 60 3.08 3.08 2.91

~60 2.75 2.75 2.68 1.288 1.130 RPTOOS 1.392 1.237

> 60 3.08 3.08 2.91

~60 2.75 2.75 2.68 PR/PLUOOS 1.392 1.288 1.237 1.210

> 60 3.08 3.08 2.91

~60 3.75 3.75 3.35 TB SOOS 1.399 1.323 1.237 1.155

> 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

> 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

> 60 3.08 3.08 2.91 TABLE 10-5 AFTO Flow Dependent MCPR Limits MCPR(F) 20°F < FWT DELTA::::; 55°F (Asymmetric Feedwater Heating)

(References 2 and 10)

Flow MCPR(F)

(%rated)

Limit 0.0 1.79 30.0 1.62 86.0 1.29 110.0 1.29 MAPLHGR LIMITS 1.067 1.067 1.147 1.079 1.147 1.147 An appropriate penalty must be applied to MAPLHGR limits under asymmetric feedwater temperature operation for va1ying temperature differentials per Reference I 0. The reduction factor listed in Table 10-6 is the maximum penalty for the full range ofanalyzed FWT mismatches, bounding all smaller temperature deltas.

TABLE 10-6 AFTO MAPLHGR Reduction Factor (Asymmetric Feeclwater Heating)

(References 2 and 10)

AFTO Reduction Factor 20°F < FWT DELTA::::; 55°FJ 0.960 1.000 1.000 1.000 1.000 1.000 1.000 I

Exelon Nuclear - Nuclear Fuels P3C:!2 Cor~ Operating l.im1ts R~port COLR PEACH BOTTOM 3 Rev. 13 Page 22 of24 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 suppo11ed. Table 11-1 provides allowed modes ofoperation with thermal limit sets in the COLR.

Table 11-2 provides al lowed 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 Speed Option Loop Operation AorB DLO or SL03 A or B DLO or SL01 AorB DLO or SL03 A orB DLO or SL03 A orB DLO or SL03 B

DLO B

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

EOOS Condition TCV/TSVOOS5 MSIYOOS 5 SRVOOS TBVOOS Supported SFTO/AFTO SFTO or AFTO SFTO or AFTO SFTO or AFTO SFTO or AFTO SFTO or 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-24011-P-A-25, August 2017 and U.S. Supplement NEDE-24011-P-A-25-US, August 2017.

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

~ -

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 Jl.FTO limits bound SFTO limits.

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

Exelon l\\uclear-Nuclear Fuels P3C'.!2 Core Operating Limits Report

13.0 REFERENCES

COLR PEACH BOTTOM 3 Rev. 13 Page 23 of24 I.

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

"Supplemental Reload Licensing Report for Peach Bottom Unit 3 Reload 21 Cycle 22," Global Nuclear Fuel Document No. 003N 1452. Revision 0, September 2017.

3. *'General Electric Standard Application for Reactor Fuel (GEST AR II),'" Global Nuclear Fuel Document No. NEDE-240 I J-P-A-25, August 20 I 7 and U.S. Supplement NEDE-240 I l-P-A-25-US, August 2017.
4.
  • 'GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GEST AR II);' Global Nuclear Fuel Document No. NEDC-33270P. Revision 8. April 2017.
5.

Peach Bottom EPU Evaluation ofFeedwater Temperature vs. Reactor Power for Feed water Temperature Conditions of Nominal Rated, FWHOOS (Nominal -55°F) and FFWTR (Nominal -90"F)."' General Electric Hitachi Nuclear Energy Document No. OOIN2494-RO, Revision 0, July 2014. This document is searchable in Exelon EDMS under document number '*PEAM-EPU-I Rev. oA.*'

6.

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

7.

"Dete1mination 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 I, December 1998.

8. Peach Bottom Atomic Pow*er Station Units 2 and 3 TRACG Implementation for Reload Licensing Transient Analysis"', Global Nuclear Fuel Document Number OOOO-Ol 35-9000-R2, June 2017.
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 4, July 2017.

I 0. *'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 Number 001 N6733 Rev. 2, Sept.

2017. This is searchable in EDMS as --PEAM-MUR-PCR-E03'" Rev. 0.

11. "Fuel Bundle Information Repo1t for Peach Bottom Unit 3 Reload 21 Cycle 22," Global Nuclear Fuel Document No. 003N 1453, Revision 0. August 2017.
12. **Final Resolved OPL-3 Parameters for Peach Bottom Unit 3 Cycle 22;* Exelon TODI ENSAF ID#

ESl700007. Revision I. June 2017.

Exelon Nuclear - Nuclear Fuels P3C22 Core Operating L.1111115 Report APPENDIX A COLR PEACH BOTTOM 3 Rev. 13 Page 24 of24 Power/Flow Operating Map for MELLLA+ with Thermal Power Optimization (Reference 6)

Co1-e Fluu ()'Jlbm/hr) 0 10 20 30 40 50 60 70 80 90 100 110 120 120 i' 4819 101.66% CLTP

= 4016 Ml'lt i

100%CLTP

= 3951 MWt

} 4418 l(l<l'l::i Core Flow

= 102.5 Mlb/hr B 30% Minimum Pu 100 c ~

54.0 mumr { 4016 0

101.5 100.0

,..Q'...

99.0 98.4

.. "!=I ll\\\\I I E'

100.0 984 l 3614 90 E

100.0 100.0 T

110.0

~-

I L __ 11.Q...!l_

984 I

80 G

110 0 21.0 3213

H 100.0 21.0 J -

37.4 21._0 __

~

~ 70 I ;

85.2 100

  • 2811 ~

1 83.0 98.4 T

55.0 n.s s 60 L

55.0 67.3

!JU]

2410

~

i Q

M 56.0 67 3

~

i

]

50 i

2008 ::

40 +

I 1606 I

i 30 i I 1205 I

20 i 803 I

j Ca\\113lll'll hll<rloc~ I I

10 l 402 0

~*- ;*****: ***"~

0 0

10 20 30 40 50 60 70 80 90 100 110 120 Co1-e Flow(%)

Retrieved from "https://kanterella.com/w/index.php?title=ML18023A137&oldid=5039175"