ML18023A137
| ML18023A137 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| 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) | |
Text
Exelon Generation .
TS 5.6.5.d 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
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 COLR PEACH BOTTOM 2 Re\'. 12 P~C2.J Cun.: O~~rJlmg l..11m1 .. R... ,.... n Page I of26 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOl\1 ATOlWIC POWER STATION UNIT 2 RELOAD 21, CYCLE 22 (This is a Complete Re-write)
Prepared By Date: 11/16117 M. Doerzbachcr Nuck::ir Fuels Prepnred By: Date: 11/17/2017 C. Bums Nuclc:ar Fuels Reviewed By:
/ i Cihah. - Renc!or Engineeting om,. JJjdJ 7 Re\ iewed By: ~v-T. l3ement - Engineering Safety Analysis Date: 11/17/17 Independent Review By: Date: 11/17/2017 K. Mccoskey - Nuclear Fuels
,Jnn~jJrm;~
Approved By* ---- -----~---
Date. 27NOV1 7 A Johnson - NI" Sr. 1\-fanaget Station Qualified Reviewer:
11/3()/1?
Date: _ _ __
Enlon Nuclc11r - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 2 of26 Table of Contents Page Revision History 3 List of Tables 4 1.0 Tenns and Definitions 5 2.0 General Infonnation 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 24 12.0 Methodology 25 13.0 References 25 Appendix A (Power/Flow Operating Map for MELLLA+ with TPO) 26
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 3 of26 Revision History Revision Description Revision 12 Revised for Rated Thermal Power of 4016 MWth Revision 11 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 5 of26 1.0 TERMS AND DEFINITIONS ABSP Automatic Backup Stability Protection AFTO Asymmetric Feedwater Temperature Operation AFTOLFWH Asymmetric Feedwater Temperature Operation Loss-of-Feed water Heating APRM Average Power Range Monitor ARTS APRM and RBM Technical Specification Analysis BASE The "BASE" condition is defined by a group of individual operating conditions that are applicable to all Modes of Operation discussed in Section 11. The "BASE" condition includes the EOOS conditions provided in Table 11-2 as well as operation with FWHOOS/FFWTR.
BOC Beginning Of Cycle BSP Backup Stability Protection DSS-CD Detect and Suppress Solution - Confirmation Density DTSP Rod Block Monitor DO\mscale Trip Setpoint EOC End of Cycle EOOS Equipment Out of Service. An analyzed option that assumes certain equipment to be non-operational EOR End of Rated. The cycle exposure at which reactor power is equal to I00% with recirculatlon system flow equal to I00%. all control rods fully withdra\m, all feedwater heating in service and equilibrium Xenon.
FFWTR Final Feed water Temperature Reduction FWHOOS Feedwater Heaters Out of Service FWT Feedwater Temperature l-IFCL High Flow Control Line HTSP Rod Block Monitor High Trip Setpoint ICF Increased Core Flow ITSP Rod Block Monitor Intermediate Trip Setpoint LHGR Linear Heat Generation Rate LHGRFAC(F) ARTS LHGR thermal limit flow dependent adjustments and multipliers LHGRFAC(P) ARTS LHGR thermal limit power dependent adjustments and multipliers LTSP Rod Block Monitor Low Trip Setpoint MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) ARTS MCPR thermal limit flow dependent adjustments and multipliers MCPR(P) ARTS MCPR thermal limit power dependent adjustments and multipliers MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ Maximum Extended Load Line Limit Analysis Plus MSIVOOS Main Steam Isolation Valve Out of Service NCL Natural Circulation Line OLM CPR Operating Limit Minimum Critical Power Ratio PLUOOS Power Load Unbalance Out of Service PROOS Pressure Regulator Out of Service RBM Rod Block Monitor RDF Rated Drive Flow RPTOOS Recirculation Pump Trip Out of Service RTP Rated Thermal Power RWE Rod Withdrawal Error SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation SRVOOS Safety Relief Valve Out of Service TBVOOS Turbine Bypass Valve Out of Service TB SOOS Turbine Bypass System Out of Service TCV/TSVOOS Turbine Control Valve and/or Turbine Stop Valve Out of Service TPO Thermal Power Optimization, also knO\\TI as Measurement Uncertainty Recapture
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 6 of26 2.0 GENERAL INFORMATION 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)
- Operating Limit Minimum Critical Power Ratio (OLMCPR)
- Linear Heat Generation Rate (LHGR)
- Turbine Bypass Valve 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%
- 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 7 of26 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 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 8 of26 4.0 MCPR LIMITS 4.1 Technical Specification Section 2.1.1.2, 3.2.2, 3.3.4.2, 3.4.1 and 3.7.6 4.2 Description The Operating Limit MCPR (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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 10 of26 TABLE 4-2 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
~60 2.69 2.69 2.62 PR/PLUOOS SLO 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 - Nuclea r Fuels COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 11 of26 TABLE 4-3 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 12 of26 5.0 LHGR LIMITS 5.1 Technical Specification Section 3.2.3, 3.3.4.2, 3.4.1 and 3.7.6 5.2 Description The 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 13 of26 TABLE 5-3 Power Dependent LHGR Multiplier LHGRFAC(P)
(Symmetric Feedwater Heating)
(Reference 2)
Core Flow Core Thermal Power (% of rated)
(%of 0 22.6 <26.3 2:26.3 40 55 65 85 100 Combination rated) LHGRFAC(P) Multiplier
- 60 0.508 0.508 0.522 Base 0.620 0.696 0.751 0.817 0.930 1.000
> 60 0.508 0.508 0.522
- 60 0.508 0.508 0.522 Base SLO 0.620 0.696 0.751 0.817 0.930 1.000
>60 0.508 0.508 0.522
- 60 0.508 0.508 0.522 RPTOOS 0.620 0.696 0.751 0.817 0.930 1.000
>60 0.508 0.508 0.522
- 60 0.508 0.508 0.522 RPTOOS SLO 0.620 0.696 0.751 0.817 0.930 1.000
> 60 0.508 0.508 0.522
- 60 0.508 0.508 0.522 PR/PLUOOS 0.620 0.696 0.751 0.817 0.930 1.000
> 60 0.508 0.508 0.522
- 60 0.508 0.508 0.522 PR/PLUOOS SLO 0.620 0.696 0.751 0.817 0.930 1.000
>60 0.508 0.508 0.522
- 60 0.397 0.397 0.442 TB SOOS 0.620 0.655 0.714 0.817 0.930 1.000
>60 0.397 0.397 0.417
- 60 0.397 0.397 0.442 TBSOOSSLO 0.620 0.655 0.714 0.817 0.930 1.000
> 60 0.397 0.397 0.417 TABLE 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)
(Symmetric Feedwater Heating)
(Reference 2)
Core Flow(% of rated)
EOOS Combination 0 30 33.6 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.506 0.706 0.730 0.973 1.000 1.000 Single Loop 0.506 0.706 0.730 0.730 0.730 0.730
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report 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.
TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 8)
Power Level Allowable Valuel'> MCPR Limit LTSP 118.2% < 1.83 <2 >
< 1.50 <3 >
!TSP 113.4% < 1.83 (2)
< 1.50 (3)
HTSP 108.4% < 1.83 (2)
< 1.50 (3)
< 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report 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(!) 0.10 sec Maximum time after initial turbine inlet valve movement(!) for bypass valve position to reach 80% offull flow (includes the 0.30 sec above delay time)
(I) First movement of any TSV or any TCV (whichever occurs first)
TABLE 7-2 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report 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 0.175 sec turbine stop valve) start to close until complete arc suppression ofthe EOC-RPT circuit breakers as described in Reference 7.
Exelon Nuclear- Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 17 of26 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 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 18 of26 TABLE 9-2<1)
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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 20 of26 TABLE 10-1 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)
Flow 0 22.6 <26.3 ~26.3 40 55 65 85 100 EOOS Combination
(%of rated) LHGRFAC(P) Multiplier
~60 0.488 0.488 0.501 Base 0.595 0.668 0.721 0.784 0.893 0.960
> 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 0.960
> 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 0.960
> 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 0.960
> 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 0.960
>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 0.960
> 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
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 21 of26 I 0.2 MCPR LIMITS 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 B 1.42 1.46 BASE A 1.48 1.55 B 1.45 1.48 RPTOOS A 1.63 1.66 B 1.42 1.46 PR/PLUOOS A 1.48 1.55 B 1.46 1.51 TB SOOS A 1.56 1.61 B 1.46 1.51 PR/PLUOOS +TB SOOS A NIA NIA B 1.45 1.48 PR/PLUOOS + RPTOOS A NIA NIA (I) When Tau does not equal 0 or I, use linear interpolation.
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 22 of26 TABLE 10-4 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)
Flow 0 22.6 <26.3 2:26.3 40 65 85 100 EOOS Combination 55
(%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 1.067 1.000
> 60 3.08 3.08 2.91
- 60 2.75 2.75 2.68 RPTOOS 1.392 1.288 1.237 1.130 1.067 1.000
>60 3.08 3.08 2.91
- 60 2.75 2.75 2.68 PR/PLUOOS 1.392 1.288 1.237 1.210 1.147 1.000
>60 3.08 3.08 2.91
- 60 3.75 3.75 3.35 TB SOOS 1.399 1.323 1.237 1.155 1.079 1.000
>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 1.147 1.000
> 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 1.147 1.000
>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
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 23 of26 10.3 MAPLHGR LIMITS 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating L1m1ts Report 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.
TABLE 11-1 Modes of Operation (Reference 2)
Supported Scram Supported Recirculation Supported EOOS Options Speed Option Loop Operation SFTO/AFTO Base'.2 A orB DLO or SL03 SFTO or AFTO TB SOOS A orB DLO or SL0 3 SFTO or AFTO RPTOOS A or B DLO or SL0 3 SFTO or AFTO PLUOOS A orB DLO or SL0 3 SFTOor AFTO PROOS A or B DLO or SL03 SFTO or AFTO PR/PLUOOS and TBSOOS B DLO AFT0 4 PR/PLUOOS and RPTOOS B DLO AFT04 TABLE 11-2 EOOS Options Included in 'Base' Conditions (Reference 2)
Condition TBVOOS SRVOOS MSIVOOS 5 TCV/TSVOOS 5 1
The 'Base' condition includes the options listed in Table 11-2.
2 The 'Base' condition includes operation with FWHOOS/FFWTR. Operation not permitted in the MELLILA+ Region for reduced FWT conditions as controlled by station procedures.
3 Operation in SLO not perm itted in the MELLLA + Region as controlled by station procedures.
4 AFTO limits bound SFTO limits.
5 Permitted at power levels provided in the applicable station procedure.
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Lim its Report Page 25 of26 12.0 METHODOLOGY The analytical methods used in determining the core operating limits have been previously reviewed and approved by the NRC, specifically those described in the following document:
- 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 COLR PEACH BOTTOM 2 Rev. 12 P2C22 Core Operating Limits Report Page 26 of26 APPENDIX A POWER/FLOW OPERATING MAP FOR MELLLA+ with TPO (Reference 6)
Core Flow (Mihm/hr) 0 10 20 120 r ~ --*-*-~;;;~;;;;t ---*- .
1 Pt Ccre Flow' 'lb 30 l'l:>wet. 'lb 40 50 60 70 80
--*- ~ ~~:.i:-~~~;* -*- ~-:i~~~*~;~;-.-.---*--*-*--
11 100\u CLTP " 3951 MWt 90 100 110 120
.... *-- *-*-~*---*-*....._.._.--*-* l 4819 110 ~ .,.!£E. Increa$ed Core Flow Reg.on ! o&lb Core Flow " 102. S Mlb/hr 4418
- _A_ tlab.Jral_Cu"!_~tioo [ _ _ _ _ _
l j __!!_ 30% MlnimU'l'I Pu~
100 J ._f;___ _J_!O_ _ ,_ _Ji.Q__
! 0 ll r:t 101.S 99.0 100.0
,-=----
- 100.0 96.4 98.4
~01~ \l\\f
.\9!'1'.U\\t ! 4016 90 *; E 100.0 100.0 3614 IF
' F' 110.0 110.0 I 100.0 98
~.4_ _ _ ,
T 3213 80 -; 110.0 - -21.0 ii _ H!_ --
lO37.4 AOO _ _2.!_.o_ _
21.0
~
70
- l 85.2 100 2811 1-------*
J _!_
- K 83.0 55.o
_I ~~--
n .s BSP Boundary i l
~
~
60 L 55.0 67.3 2410
- M 56.0 67.3 i f 2008 -=~
50 f ~
40 lf r 1606 l
30 .! r 1205 20 1 f
I 803 1
_../ I I ta' uanon ln1erlock I I 10 l 402
,......'* l 0
_....................... !0 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Floll (%)
E~clnn Nucle~*r - Nuch!:1r FuL*I-= COLR PEACH BOTTOM 3 Rcv.13 P3C:!2 C"ur~ Opcra1ing Lnml' Rcpwt Page I of 24 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATO MIC POWER ST ATI ON UNIT 3 RELOAD 21, CYCLE 22 Prepared By: Date: 11/1/2017 Reviewed By: ~/- ~ __________ _ Date: J _VID/J()//
Matthew Miller Reactor En1:,rineering Rov;,,,.dBy' ~~
Trm*is Bem*e~l--E~gT;~-eri;;g s~fet-y"/;:;-1-;lysis Date: 11 i2i17 independent Review By: J~~ Date: 11 /8/17 Tamara Stathes Nuclear Fuels ApprovedBy: _ _ _ ~~0 Armando Johnson NF Senior Manager
_________ Date: 13NOV17_
J~-4'--_,,,~tio_n_Q-~-ia-li-fi~-d~ /13/ 1')
1 SQR By: Date: '
Exelon l'luclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operutmg Lim i t~ Report 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 COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operating l.11111ts R~port Page 3 of24 Revision History Revision Description Revision 13 Update of Cycle 22 COLR to allow for implementation of Thermal Power Optimization/Measurement Uncertainty Recapture (TPO/MUR) to 4016 MW1 Revision 12 New issue for Cycle 22
Exelon i'iurlear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 13 P3C'22 Cor~ Opcmtmg I 111111~ R~port Page 4 of24 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 IO 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) 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 I0-4 AFTO Power Dependent MCPR Limit Adjustments and Multipliers 21 MCPR(P) 20°F < FWT DELTA~ 55°F Table I0-5 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 COLR PEACH BOTTOM 3 Rev. 13 P3C ~2 Core Operating Lim its Report Page 5 of24 1.0 Terms and Definitions ABS!' Automatic Backup Stabilit) Protection AFIO As) mmetric Feed water I emperature Operation AFTO Lf'WH Asymmetric f'ccd\\atcr Temperature Operation Loss-ot~f'eed\\ater Heating APRM Average Power Range Monitor AR rs APRM and RBM Technical Specification Analysis BASE 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.
BOC Beginning Of Cycle BS!' Backup Stability Protection DSS-CD Detect and Suppress Solution - Confirmation Density DTSP Rod Block Monitor Downscale Trip Setpoint EOC End of Cycle EOOS Equipment Out of Service. An analyzed option that assumes certain eljuipment to be non-operational.
EOR End of Rated. The cycle exposure at which reactor power is equal to I 00% \\ ith recirculation system
!low equal to I00%. all control rods fully withdra\\11, all !Ced water heating in sen ice and equilibrium Xenon.
FFWTR Final Feed\Hlter Temperature Reduction FWHOOS Feed water Heaters Out of Service f'WT Feedwater Temperature Hf'CL I ligh f'low Control Line llTSP Rod Block Monitor I ligh Trip Setpoint ICF Increased Core Flo\\
ITSP Rod Block Monitor Intermediate Trip Sctpoint LllGR Linear I Icat Generation Rate LI IGRF AC(F) AR rs LI IGR thermal limit llcl\\ dependent adjustments and multipliers Ll-IGRFAC(I') ARTS LHGR thennal limit po\\er dependent adjustments and multipliers LTSP Rod Block Monitor Low Trip Setpoint MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) ARTS MCPR thennal limit flow dependent adjustments and multipliers MCPR(P) ARTS MCPR thermal limit power dependent adjustments and multipliers MELL LA Maximum Extended Load Linc Limit Analysis MELI.LA+ Mm..imum Extended Load Linc Limit Analysis Plus MSIVOOS Main Steam Isolation Valve Out of Service NCL Natural Circulation Linc OLM CPR Operating Limit Minimum Critical Power Ratio PLUOOS Power Load Unbalance Out ofServicc PROOS Pressure Regulator Out of Service RBM Rod Block Monitor RDf' Rated Drive Flow RP TO OS Recirculation Pump Trip Out of Sen ice RTP Rated ll1ermal Power RWE Rod Withdrawal Error SLMCPR Safe!) Limit Minimum Critical Po\\ er Ratio Sl.O Single Loop Operation TB SOOS Turbine B)pass System Out of Sen ic.:
TCV/TSVOOS Turbine Control Val' e and/or Turbine Stop Vahe Out of Sen ice
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operating I .i1111ts Report Page 6 of24 2.0 General Information 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)
- Operating Limit Minimum Critical Power Ratio (OLMCPR)
- Linear Heat Generation Rate (LHGR)
- Turbine Bypass Valve 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%
- Final Feedwater Temperature Reduction (FFWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) to 90° F temperature reduction (4 111 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 COLR PEACH BOTTOM 3 Rev. 13 P3C:!2 Core Operntmg l.im it5 Report Page 7 of24 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 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 COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operutmg Lim i t~ Report Page 8 of24 4.0 MCPR LIMITS 4.1 Technical Specification Section 2.1.1.2, 3.2.2, 3.3.4.2, 3.4.1 and 3.7.6 4.2 Description The Operating Limit MCPR (OLMCPR) for GNF2 fuel is provided in 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 COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operating l.11111ts Report Page 9 of24 TABLE4-1 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 B 1.43 1.45 BASE SL0' 2 >
A 1.51 1.53 B 1.43 1.45 RPTOOS A 1.60 1.62 B 1.46 1.48 RPTOOS SL012 >
A 1.63 1.65 B 1.40 1.42 PR/PLUOOS A 1.48 1.50 B 1.43 1.45 PR/PLUOOS SLOt2>
A 1.51 1.53 B 1.44 1.47 TB SOOS A 1.53 1.56 B 1.47 1.50 TBSOOS SLO 12i 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 COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operating l .11rnt~ Report Page 10of24 TABLE 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers (Symmetric Feedwater Heating)
(Reference 2)
Core Core Thermal Power(% of rated)
Flow EOOS Combination 0 22.6 <26.3 ?: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 2.70 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 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 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 1.392 1.288 1.237 1.210 1.147 1.000
> 60 2.99 2.99 2.83
~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 COLR PEACH BOTTOM 3 Rev. 13 P3C21 Core Operating l.im1ts Report Page 11 of24 TABLE 4-3 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 COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operating l.111111~ Report Page 12of24 5.0 LHGR LIMITS 5.1 Technical Specification Section 3.2.3, 3.3.4.2, 3.4. 1 and 3.7.6 5.2 Description The 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 COLR PEACH BOTTOM 3 Rev. 13 P3C:!2 Core Opernting l.i1111ts Report 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 0 22.6 <26.3 2::26.3 40 55 65 85 100
(%of rated)
LHGRFAC(P) Multiplier Base
- s 60 0 .508 0 .508 0.522 0.620 0.696 0.751 0.817 0.930 1.000
>60 0.508 0 .508 0.522 Base SLO
- s 60 0.508 0.508 0.522 0.620 0.696 0.751 0.817 0.930 1.000
> 60 0.508 0.508 0.522 RPTOOS
- s 60 0.508 0 .508 0 .522 0.620 0.696 0.751 0.817 0.930 1.000
>60 0.508 0.508 0.522 RPTOOS SLO
- s 60 0.508 0.508 0.522 0.620 0.696 0.751 0.817 0.930 1.000
>60 0.508 0.508 0.522 PR/PLUOOS
- s 60 0.508 0.508 0.522 0.620 0.696 0.751 0.817 0.930 1.000
> 60 0.508 0.508 0.522 PR/PLUOOS SLO
- s 60 0.508 0.508 0.522 0.620 0.696 0.751 0.817 0.930 1.000
>60 0.508 0.508 0 .522 TBSOOS
- s 60 0 .397 0.397 0.442 0.620 0.655 0.71 4 0.817 0.930 1.000
> 60 0.397 0.397 0.417
- s 60 0.397 0.397 0.442 TBSOOS SLO 0.620 0.655 0.714 0.817 0.930 1.000
> 60 0.397 0.397 0.417 TABLE 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)
(Symmetric Feedwater Heating)
(Reference 2)
Core Flow (% of rated)
EOOS Combination 0 30 33 .6 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.506 0.706 0.730 0.973 1.000 1.000 Single Loop 0.506 0.706 0.730 0.730 0.730 0.730
Exelon l\uclear - Nuclear Fuel\ COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operating L.im1t~ Report 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.
TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 9)
Power Level Allowable Value! 1' MCPRLimit LTSP 118.2% < 1.83 (l)
< 1.50 {3)
ITSP 113.4% < 1.83 (~)
< 1.50 (3)
HTSP 108.4% < 1.83 (l)
< 1.50 (J)
INOP N/A < 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 COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operating Lim its Report 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 0.10 sec initial turbine inlet valve movement0 '
Maximum time after initial turbine inlet valve movement' 1' for bypass 0.30 sec 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 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 COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operating Limits Report 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 0.175 sec turbine stop valve) start to close until complete arc suppression of"the EOC-RPT circuit breakers as described in Reference 7.
Exelon Nurlear - :"luclear Fuels COLR PEACH BOTTOM 3 Rev. 13 P3C:!2 Core Operating I i1111ts Report Page 17 of24 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 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~ COLR PEACH BOTTOM 3 Rev. 13 1'3C22 Core Operating l.11111ts Report Page 18 of 24 TABLE 9-2( 11 Manual BSP Endpoints for Normal Feedwater Temperature (Reference 2)
Endpoint Power(%) Flow ('Yo) Defi nition 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 COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operating Lim it~ Report 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 85 100 I
(%of I rated) LHGRFAC{P) Multiplier
~60 0.488 0.488 0.501 Base 0.595 0.668 0.721 0.784 0.893 0.960
> 60 0.488 0.488 0.501
~60 0.488 0.488 0.501 RPTOOS 0.595 0.668 0.721 0.784 0.893 0.960
>60 0.488 0.488 0.501
~60 0.488 0.488 0.501 PR/PLUOOS 0.595 0.668 0.721 0.784 0.893 0.960
> 60 0.488 0.488 0.501
~60 0.381 0.381 0.424 TB SOOS 0.595 0.629 0.685 0.784 0.893 0.960
>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 0.893 0.960
>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 0.893 0.960
> 60 0.488 0.488 0.501
Exelon l\uclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 13 P3C2:! Core Operatmg Lim i l~ Report 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 110 LHGRFAC(F) Multiplier 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 B 1.47 1.49 RPTOOS A 1.65 1.67 B I .44 1.46 PR/PLUOOS A 1.52 1.55 B 1.48 1.51 TB SOOS A 1.58 1.6 I B 1.48 1.51 PR/ PLUOOS + TBSOOS A NIA NIA B 1.47 1.49 PR/ PLUOOS + RPTOOS 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 COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operating I .i111 1t5 Report Page 21 of24 TABLE 10-4 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 20°F < FWT DELTA :'.S 55°F (Asymmetric Feedwater Heating)
(References 2, 8, and 10)
Core Core Thermal Power(% of rated)
Flow EOOS Combination
(%of 0 22.6 <26.3 2::26.3 40 55 65 85 100 I I
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 1.067 1.000
> 60 3.08 3.08 2.91
~60 2.75 2.75 2.68 RPTOOS 1.392 1.288 1.237 1.130 1.067 1.000
> 60 3.08 3.08 2.91
~60 2.75 2.75 2.68 PR/PLUOOS 1.392 1.288 1.237 1.210 1.147 1.000
> 60 3.08 3.08 2.91
~60 3.75 3.75 3.35 TB SOOS 1.399 1.323 1.237 1.155 1.079 1.000
> 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 1.147 1.000
> 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 1.147 1.000
> 60 3.08 3.08 2.91 TABLE 10-5 AFTO Flow Dependent MCPR Limits MCPR(F) 20°F < FWT DELTA::::; 55°F I
(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 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
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 13 P3C:!2 Cor~ Operating l.im1ts R~port 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.
TABLE 11-1 Modes of Operation (Reference 2)
Supported Scram Supported Recirculation Supported EOOS Options Speed Option Loo p Operation SFTO/AFTO Base 1*2 AorB DLO or SL0 3 SFTO or AFTO TB SOOS A or B DLO or SL0 1 SFTO or AFTO RPTOOS AorB DLO or SL03 SFTO or AFTO PLUOOS A orB DLO or SL0 3 SFTO or AFTO PROOS A orB DLO or SL03 SFTO or AFTO PR/PLUOOS and TBSOOS B DLO AFT0 4 PR/PLUOOS and RPTOOS B DLO AFT0 4 TABLE 11-2 EOOS Options Included in 'Base' Conditions (Reference 2)
EOOS Condition TCV/TSVOOS 5 MSIYOOS 5 SRVOOS TBVOOS 12.0 METHODOLOGY The analytical methods used in determining the core operating limits have been previously reviewed and approved by the NRC. specifically those described in the following 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 COLR PEACH BOTTOM 3 Rev. 13 P3C'.!2 Core Operating Lim its Report Page 23 of24
13.0 REFERENCES
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 COLR PEACH BOTTOM 3 Rev. 13 P3C22 Core Operating L.1111115 Report Page 24 of24 APPENDIX A 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 l(l<l'l::i Core Flow = 102.5 Mlb/hr } 4418 B 30% Minimum Pu c ~ 54.0 100 0 101.5 100.0 mumr {
.."!=I ll\\I I 4016
, ..Q'... 99.0 98.4 90 E'
E 100.0 100.0 984 100.0 l 3614 T 110.0 ~-
I L _ _ 11.Q...!l_ 984 I 3213 80
- H J-G 110 0 100.0 37.4 21.0 21.0 21._0 _ _ -
~
~
- 2811
... 70 I ;
T 1
85.2 83.0 100 98.4 n.s
~
s
- ... 60 M
L 55.0 55.0 56.0 67.3 67 3
!JU]
i 2410 ~
Q
~:: i ]
50 2008 ::
i :::::
40 + I 1606 I i 30 i I 1205 I
20 . I j Ca\113lll'll hll<rloc~ I i 803 I
10 l 402 0 ~*-;*****:***"~ . -' 0 0 10 20 30 40 50 60 70 80 90 100 110 120 Co1-e Flow(%)