ML19064A193
| ML19064A193 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/04/2019 |
| From: | Pat Navin Exelon Generation Co |
| To: | Document Control Desk |
| References | |
| Download: ML19064A193 (26) | |
Text
Exelon Generation March 4, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Unit 2 Renewed Facility Operating License No. DPR-44 NRC Docket No. 50-277 TS 5.6.5.d
Subject:
Issuance of the Core Operating Limits Report for Reload 22, Cycle 23 Enclosed is a copy of Revision 14 of the Core Operating Limits Report (COLR) for Peach Bottom Atomic Power Station (PBAPS) Unit 2 for Reload 22, Cycle 23. This revision incorporates the revised cycle specific parameters resulting from the new core configuration as a result of the PBAPS Unit 2 refueling outage.
This COLR is being submitted to the NRC as required by the PBAPS, Unit 2 Technical Specifications (TS) Section 5.6.5.d.
If you have any questions concerning this letter, please contact Dan Dullum at (717) 456-3339.
Resp~
L Patrick D. Navin Site Vice President Peach Bottom Atomic Power Station CCN: 18-112
Attachment:
Unit 2 Core Operating Limits Report for Reload 22, Cycle 23 cc:
Regional Administrator, Region I, USNRC (without attachment)
USNRC Senior Resident Inspector, PBAPS (without attachment)
Project Manager-PBAPS, USNRC (with attachment)
R. R. Janati, Pennsylvania Bureau of Radiation Protection (without attachment)
S. T. Gray, State of Maryland (without attachment)
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Exelon Nudear* Nuclear Fuels P2C23 Core Open1in11 l.iJni11i Report COLR PEACH BOTIOM 2 Rev. 14 Page I of25 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 2 Prepared By:
Prepared By:
Reviewed By:
Reviewed By:
Independent Review By:
Approved By:
Station Qualified Reviewer:
RELOAD 22, CYCLE 23 F. Qureshi - Nuclear Fuels M. Doerzbacher-Nuclear Fuels M. Miller
- Reactor Engineering
~~
B. Sarikaya - Engineering Safety Analysis R. Potter
- Nuclear Fuels
~~
A. Johnson *NF Sr. Manager Nf:t:s01f!1 Date:
10/5/2018 Date:
10/5/1B Date: 1°11/1&
10/5/18 Date: ___
10/8/2018 Date: ___
Date: 080CT18 Date:
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E:uloo Nuclear-Nuclear Fuels P2C23 Core Operating Limits Report Table of Contents Revision History List of Tables 1.0 Tenns and Definitions 2.0 General Information 3.0 MAPLHGR Limits 4.0 MCPRLimits 5.0 LHGRLimits 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. 14 Page 2 of25 Page 3
4 5
6 7
8 12 14 15 16 17 19 23 24 24 Appendix A: Power/Flow Operating Map for MELLLA + with TPO 25
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Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report Revision Revision 14 Revision History COLR PEACH BOTTOM 2 Rev. 14 Page 3 of25 Description New Issue for Cycle 23
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Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 14 Page 4 of25 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 F eedwater Temperature 18 Table 9-3 Manual BSP Endpoints for Reduced Feedwater Temperature 18 Table 10-1 AFTO MAPLHGR Reduction Factor 19 Table 10-2 AFTO Operating Limit Minimum Critical Power Ratio 20°F < FWT DELTA :5 55'F 20 Table 10-3 AFTO Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) 21 20'F < FWT DELTA :5 55'F Table 10-4 AFTO Flow Dependent MCPR Limits MCPR(F) 20'F < FWT DEL TA :5 55'F 21 Table 10-5 AFTO Power Dependent LHGR Multiplier LHGRF AC(P) 20'F < FWT DEL TA :5 55'F 22 Table 10-6 AFTO Flow Dependent LHGR Multiplier LHGRF AC(F) 20°F < FWT DELTA :::; 55'F 22 Table 11-1 Modes of Operation 23 Table 11-2 EOOS Options Included in 'Base' Conditions 23
0 Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 14 Page 5 of25 1.0 TERMS AND DEFINITIONS ABSP AFTO AFTOLFWH APRM ARTS BASE BOC BSP DSS-CD DTSP EOC EOOS EOR FFWfR FWHOOS FWf HFCL HTSP
!CF
LHGRFAC(P)
MCPR(P)
MELLLA MELLLA+
MSIVOOS NCL OLM CPR PLUOOS PROOS RBM RDF RPTOOS RTP RWE SLM CPR SLO SFTO SRVOOS TBVOOS TB SOOS TCVfTSVOOS TPO Automatic Backup Stability Protection Asymmetric Feedwater Temperature Operation Asymmetric Feedwater Temperature Operation Loss-of-Feedwater 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 Downscale 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 recirculation system flow equal to I 00%, all control rods fully withdrawn, all feedwater heating m service and equilibrium Xenon.
Final Feedwater Temperature Reduction Feedwater 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 dei>c:.ndent 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 Symmetric Feedwater Temperature 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 known as Measurement Uncertainty Recapture
Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report 2.0 GENERAL INFORMATION COLR PEACH BOTTOM 2 Rev. 14 Page 6 of25 This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 2 CYCLE 23 (RELOAD 22):
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Single Loop Operation (SLO) MAPLHGR multipliers Operating Limit Minimum Critical Power Ratio (OLMCPR)
AR TS 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 thermal 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%
ofrated core flow during full power (4016 MWt) operation (Appendix A)
Increased Core Flow (ICF), up to 110% of rated core flow End-of-Cycle Power Coastdown to a minimum power level of 40%
Feedwater Heaters Out of Service (FWHOOS) 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 (4lh 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 thermal-mechanical analysis documented in Reference 13. Supporting documentation for the ARTS-based limits is provided in Reference 2. The off-rated limits assumed in the ECCS-LOCA analyses bound the cycle-specific limits calculated for MELLLA+
operation. The Allowable Values documented in Reference 5 for feed water 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 23 core is comprised entirely of GNF2 fuel.
Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report 3.0 MAPLHGR LIMITS 3.1 Technical Specification Section 3.2.l, 3.3.4.2, 3.4.1and3.7.6 3.2 Description COLR PEACH BOTTOM 2 Rev. 14 Page 7 of25 The limiting MAPLHGR value for the most limiting lattice of GNF2 fuel as a function of average planar exposure is given in Table 3-1. For single loop operation, a multiplier is used, which is shown in Table 3-2. The impact of AFTO on MAPLHGR is addressed in Section I 0.0. The power and flow dependent LHGR multipliers are sufficient to provide adequate protection for the off-rated conditions from an ECCS-LOCA analysis perspective. The MAPLHGR multipliers can either be set to unity or set equal to the LHGR multipliers, which remain compliant with the basis of the ECCS-LOCA analysis with no loss ofECCS-LOCA margin.
TABLE 3-1 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
0 Exelon Nuclear - Nuclear Fue!J P2C23 Core Operating Limits Report 4.0 MCPR LIMITS 4.1 Technical Specification Section 2.1.1.2, 3.2.2, 3.3.4.2, 3.4.1and3.7.6 4.2 Description COLR PEACH BOTTOM 2 Rev. 14 Page 8 of25 The Operating Limit MCPR (OLMCPR) for GNF2 fuel is provided in Table 4-1. These values are determined by the cycle-specific fuel reload analyses in Reference 2. Control rod scram time verification is required as per Technical Specification 3.1.4, "Control Rod Scram Times". Tau (t), a measure of scram time performance to notch position 36 throughout the cycle, is determined based on the cumulative scram time test results.
The calculation of Tau shall be performed in accordance with site procedures. Linear interpolation shall be used to calculate the OLM CPR value if Tau is between 0.0 (Tau Option B) and 1.0 (Tau Option A). Table 4-1 is valid for a maximum FWT reduction of 90°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 10.0; 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 of 90°F for FFWTR operation (bounding for FWHOOS operation)
(Reference 2). The flow-dependent MCPR limits are provided in Tables 4-3 and 4-4. Table 4-3 is valid for dual loop operating conditions with symmetric feedwater temperature operation, and Table 4-4 is valid for single loop operating conditions with symmetric feedwater temperature operation.
0 Exelon Nuclear-Nuclear Fuels P2C23 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 14 Page 9 of25 TABLE4-1 Operating Limit Minimum Critical Power Ratio (Reference 2)
SCRAM Cvcle Exposure Time
< EOR-3946
~EOR-3946 EOOS Combination Option<1>
MWd/ST MWd/ST B
1.40 1.43 BASE A
1.46 1.51 B
1.43 1.46 BASESLO A
1.49 1.54 B
1.42 1.44 RPTOOS A
1.59 1.61 B
1.45 1.47 RPTOOSSLO A
1.62 1.64 B
1.40 1.43 PR/PLUOOS A
1.46 1.51 B
1.43 1.46 PR/PLUOOSSLO A
1.49 1.54 B
1.46 1.47 TB SOOS A
1.52 1.56 B
1.49 1.50 TBSOOS SLO A
1.55 1.59 (1) When Tau does not equal 0 or 1, use linear interpolation.
0 Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Lunits Report TABLE 4-2 COLR PEACH BOTTOM 2 Rev. 14 Page 10 of25 Power Dependent MCPR(P) Limit Adjustments and Multipliers (Symmetric Feedwater Heating)
<Reference 2)
Core Core Thermal Power (% of rated)
EOOS Combination Flow(%
0 22.6
~26.3 >26.3 40 55 65 85 100 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 2: 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 2: 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 2: 60 2.99 2.99 2.83
<60 2.70 2.70 RPTOOSSLO 2: 60 3.02 3.02 2.63 2.86 1.392 1.288 1.237 1.130 1.067 1.000
<60 2.67 2.67 2.60 PRIPLUOOS 1.392 1.288 1.237 1.210 1.147 1.000 2: 60 2.99 2.99 2.83
<60 2.70 2.70 2.63 PR/PLUOOSSLO 1.392 1.288 1.237 1.210 1.147 1.000 2: 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 2: 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 2: 60 4.18 4.18 3.81
c Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report TABLE4-3 COLR PEACH BOTTOM 2 Rev. 14 Page 11 of25 Flow Dependent MCPR Limits MCPR(F)
(Symmetric Feedwater Heating)
(Reference 2)
Core Flow MCPR(F)
(%rated)
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 Feedwater 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
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Exelon Nuclear* Nuclear Fuels P2C23 Core Operating Limits Report 5.0 LHGR LIMITS COLR PEACH BOTTOM 2 Rev. 14 Page 12of25 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 of 90° F for FFWTR operation (bounding for FWHOOS operation) (Reference 2). The flow-dependent multipliers are provided in Table 5-4 as a function of the number of recirculation loops in operation. The SLO LHGR multiplier is provided and accounted for in Table 5-4. The power-and flow-dependent LHGR multipliers were obtained from Reference 2. The impact of AFTO on LHGR is addressed in Section 10.0. 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.
TABLES-1 Linear Heat Generation Rate Limits - U02 Rods (References 10 and 13)
Fuel Type LHGRLimit GNF2 See Reference 13 TABLES-2 Linear Heat Generation Rate Limits - Gad Rods (References 10 and 13)
Fuel Type LHGRLimit GNF2 See Reference 13
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u Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report TABLES-3 COLR PEACH BOTTOM 2 Rev. 14 Page 13 of25 Power Dependent LHGR Multiplier LHGRFAC(P)
(Symmetric Feedwater Heating)
(Reference 2)
Core Flow Core Thermal Power(% of rated)
(%of Combination rated)
<60 Base
~60
<60 Base SLO
~60
<60 RPTOOS
~60
<60 RPTOOSSLO
~60
<60 PR/PLUOOS
~60
<60 PR/PLUOOS SLO
~60
<60 TB SOOS
~60
<60 TBSOOS SLO
~60 EOOS Combination Dual Loop Single Loop 0
22.6
$26.3
>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 0.620 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 0.508 0.508 0.522 0.397 0.397 0.442 0.620 0.655 0.397 0.397 0.417 0.397 0.397 0.442 0.620 0.655 0.397 0.397 0.417 TABLES-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
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Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 14 Page 14of25 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 8. These values correspond to the OLMCPR values provided in Table 4-1.
Power Level LTSP ITSP HTSP INOP TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 8)
Allowable ValueC1>
118.2%
113.4%
108.4%
NIA MCPRLimit
< 1.83 <2>
< 1.50 <3>
< 1.83 c2>
< 1.50 <3>
< 1.83 <2>
< 1.50 <3>
< 1.83 C2>
< 1.50 C3>
(I) These setpoints (with RBM filter time constant between 0.1 seconds and 0.55 seconds) are based on cycle-specific rated RWE MCPR limits which are bounded by the OLMCPRs listed in Table 4-1.
(2) This is the MCPR limit (given TIIERMAL POWER is 2'._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 TIIERMAL POWER is 2'.. 90%) below which the RBM is required to be OPERABLE (see COLR Reference 2 and TS Table 3.3.2.1-1).
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u Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 14 Page 15of25 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 (TB SOOS) must be used. Additionally, the OLM CPR for TB SOOS 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<1J Maximum time after initial turbine inlet valve movement(!) for bypass valve position to reach 80% of full flow (includes the above delay time)
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 (I) First movement of any TSV or any TCV (whichever occurs first)
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Exelon Nuclear-Nuclear Fuels P2C23 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 14 Page 16 of25 8.0 EOC RECffiCULATION 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.
TABLE8-1 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
u Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 14 Page 17 of25 9.0 STABILITY PROTECTION 9.1 Technical Specification Section 3.3.1.1, Table 3.3.1.1-1 Function 2.f 9.2 Description Per Reference 2, the Cycle 23 DSS-CD SAD Setpoint was confinned 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 Nonna! 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 10-90°F below nominal.
TABLE 9-1 Automatic BSP Setpoints for the Scram Region (Reference 2)
Parameter Symbol Slope of ABSP APRM flow-biased trip mrrip linear segment.
ABSP APRM flow-biased trip setpoint power intercept.
PasP-Trip Constant Power Line for Trip from zero Drive Flow to Flow Breakpoint value.
ABSP APRM flow-biased trip setpoint drive flow intercept. Constant Flow Line WasP-Trip for Trip.
Flow Breakpoint value WasP-Brcak Value 1.62 39.8 %RTP 46.7%RDF 25.0 %RDF
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Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report TABLE 9-2<1>
COLR PEACH BOTTOM 2 Rev. 14 Page 18 of25 Manual BSP Endpoints for Normal Feedwater Temperature (Reference 2)
Endpoint Power(%)
Flow(%)
Definition Al 73.9 50.l 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.l Controlled Entry Region Boundary, NCL Note: The BSP Boundary for Nonna! and Reduced Feedwater Temperature is defined by the MELLLA boundary line, per Reference 2.
TABLE 9.3<1>
Manual BSP Endpoints for Reduced Feedwater Temperature (Reference 2)
Endpoint Power(%)
Flow(%)
Definition Al' 64.3 51.l Scram Region Boundary, HFCL Bl' 33.6 30.6 Scram Region Boundary, NCL A2' 67.2 54.8 Controlled Entry Region Boundary, HFCL B2' 27.6 30.l Controlled Entry Region Boundary, NCL Note: The BSP Boundary for Nonna! and Reduced Feedwater Temperature is defined by the MELLLA boundary line, per Reference 2.
(I) Station may elect to place additional administrative margin on the endpoints provided in Table 9-2 and Table 9-3.
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Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 14 Page 19of25 10.0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION (AFTO)
Asymmetric feedwater heating is the result of the specific configuration of the feedwater lines at Peach Bottom. A reduction in heating in either the 'A' or the 'C' heater strings will result in a temperature mismatch between the 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 less than or equal to 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.l 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 10-1 is the maximum penalty for the full range of analyzed FWT mismatches, bounding all smaller temperature deltas.
TABLE 10-1 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)
(References 2 and 9)
AFTO Reduction Factor 20"F < FWT DELTA :s 55°F I 0.960
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u Exelon Nuclear-Nuclear Fuels P2C23 Core Operating Limits Report 10.2 MCPR LIMITS COLR PEACH BOTTOM 2 Rev. 14 Page20 of25 The OLMCPRs during asymmetric feedwater temperature operation with a feed water temperature difference greater than 20°F are provided in Table 10-2. The ARTS-based power-dependent MCPR limits for use during AFTO conditions are provided in Table 10-3. The flow-dependent MCPR limits for AFTO are provided in Table 10-4. The power-and flow-dependent OLM CPR curves were obtained from Reference 2 and were adjusted with a penalty for feedwater temperature difference greater than 20°F as per Reference 9.
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.
TABLEl0-2 AFIO Operating Limit Minimum Critical Power Ratio 20'F < FWT DELTA :5 55°F (Asymmetric Feedwater Heating)
<References 2, 9 and 11)
SCRAM Cvcle Exposure Time
<EOR-3946 ;:::EOR-3946 EOOS Combination Option <1>
MWdlST MWd/ST BASE B
1.44 1.47 A
1.50 1.56 RPTOOS B
1.46 1.48 A
1.64 1.66 PRIPLUOOS B
1.44 1.47 A
1.50 1.56 TB SOOS B
1.50 1.51 A
1.57 1.61 PR/PLUOOS + TBSOOS B
1.50 1.51 A
NIA NIA PR/PLUOOS + RPTOOS B
1.46 1.48 A
NIA NIA (1) When Tau does not equal 0 or 1, use linear interpolation.
0 Exelon Nuclear-Nuclear Fuels P2C23 Core Operating Limits Report TABLE 10-3 COLR PEACH BOTTOM 2 Rev. 14 Page 21of25 AFI'O Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 20°F < FWT DELTA$ 55°F (Asymmetric Feedwater Heating)
(References 2, 9 and 11)
Core Core Thermal Power (% of rated)
EOOS Combination Flow 0
22.6
$26.3
>26.3 40 55 65 85 100
(%of rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp
<60 2.75 2.75 2.68 Base 1.392 1.288 1.237 1.130
~60 3.08 3.08 2.91
<60 2.75 2.75 2.68 RPTOOS 1.392 1.288 1.237 1.130
~60 3.08 3.08 2.91
<60 2.75 2.75 2.68 PR/PLUOOS
~60 1.392 1.288 1.237 1.210 3.08 3.08 2.91
<60 3.75 3.75 3.35 TB SOOS
~60 1.399 1.323 1.237 1.155 4.27 4.27 3.89
<60 3.75 3.75 3.35 PR/PLUOOS + TBSOOS
~60 1.399 1.323 1.237 1.210 4.27 4.27 3.89
<60 2.75 2.75 2.68 PR/PLUOOS + RPTOOS 1.392 1.288 1.237 1.210
~60 3.08 3.08 2.91 TABLE 10-4 AFI'O Flow Dependent MCPR Limits MCPR(F) 20°F < FWT DELTA$ 55°F (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
0 Exelon Nuclear - Nuclear Fuels P2C23 Core Operatmg Limits Report 10.3 LHGR LIMITS COLR PEACH BOTTOM 2 Rev. 14 Page 22 of25 The ARTS-based LHGR power-dependent multipliers for AFTO operation are provided in Table 10-5. The flow-dependent multipliers for AFTO in DLO are provided in Table 10-6. The power-and flow-dependent LHGR multipliers were obtained from Reference 2 and were adjusted with the appropriate' penalties 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.
TABLE 10-5 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20'F < FWT DELTA:::; 55°F (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
<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
<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
<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
<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
<60 0.488 0.488 0.501 PR/PLUOOS + RPTOOS 0.595 0.668 0.721 0.784 0.893
(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
0 Exelon Nuclear-Nuclear Fuels P2C23 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 14 Page 23 of25 11.0 MODES OF OPERATION The following conditions are supported by the Peach Bottom 2 Cycle 23 licensing analysis; operation in a condition (or conditions) is controlled by station procedures. If a combination of options is not listed, it is not supported.
Table 11-1 provides allowed modes of operation with thermal limit sets in the COLR. Table 11-2 provides allowed modes of operation that do not contain explicit thermal limit sets in the COLR.
EOOS Options BaseC1*2>
TB SOOS RPTOOS PLUOOS PROOS PRIPLUOOS and TBSOOS PRIPLUOOS and RPTOOS TABLE 11-1 Modes of Operation (Reference 2)
Supported Scram Supported Recirculation Speed Option Loop Operation AorB DLO or SL0C3l AorB DLO or SL0C3>
AorB DLO or SL0<3>
AorB DLO or SL0<3>
AorB DLO or SLoc3>
B DLO B
DLO TABLE 11-2 EOOS Options Included in 'Base' Conditions (Reference 2)
Condition TBVOOS SRVOOS MSIVOOS<5>
TCV /TSVOOsC5>
(1) The 'Base' condition includes the options listed in Table 11-2.
Supported SFTO/AFTO SFTOor AFTO SFTOor AFTO SFTO orAFTO SFTO or AFTO SFTO or AFTO AFToc4>
AFT0C4>
(2) The 'Base' condition includes operation with FWHOOS/FFWTR. Operation not permitted in the MELLLA+
Region for reduced FWT conditions as controlled by station procedures.
(3) Operation in SLO not permitted in the MELLLA+ Region as controlled by station procedures.
(4) AFTO limits bound SFTO limits.
(5) Permitted at power levels provided in the applicable station procedure.
0 u
Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 14 Page 24 of25 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 l l-P-A-26, January 2018 and U.S. SupplementNEDE-24011-P-A-26-US, January 2018.
13.0 REFERENCES
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
"Technical Specifications for Peach Bottom Atomic Power Station Unit 2", Exelon Document, Docket No. 50-277, License No. DPR-44.
Global Nuclear Fuel Document "Supplemental Reload Licensing Report for Peach Bottom Unit 2 Reload 22 Cycle 23, GNF Document No. 004N2745, Revision 0, August 2018.
Global Nuclear Fuel Document "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-26, January 2018 and U.S. SupplementNEDE-24011-P-A-26-US, January 2018.
Global Nuclear Fuel Document NEDC-33270P Rev. 9, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," December 2017.
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.
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.
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. 1dated12/22/98.
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.
General Electric Hitachi Document 001N6733, "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+, Revision 2, September 2017. This document is searchable in Exelon EDMS under document number "PEAM-MUR-PCR-E03" Rev. 0.
- 10. Global Nuclear Fuel Document, "Fuel Bundle Information Report for Peach Bottom Unit 2 Reload 22 Cycle 23",
Revision 0, Document No. 004N2746, August 2018.
- 11. General Electric Hitachi 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 TODI ENSAF ID# ES1800017, Rev. 0, "Final Resolved OPL-3 Parameters for Peach Bottom Unit 2 Cycle 23, 6/26/2018.
- 13. Global Nuclear Fuel Document 004N7833-P, Rev. 0, "PRIME-Based GNF2 LHGR Envelopes for Peach Bottom Atomic Power Station Units 2 and 3", April 2018
n
(
Exelon Nuclear - Nuclear Fuels P2C23 Core Operating Limits Report APPENDIX A COLR PEACH BOTTOM 2 Rev. 14 Page 25 of25 POWER/FLOW OPERATING MAP FOR MELLLA+ with TPO (Reference 6)
Core Flow ('.\\tlbm/hr) 0 10 20 30 40 50 60 70 80 90 100 110 120 120 r*r-
- ."""'"_._,_,_,......_...._.~....... ""'"'"-......,._""'-*=-*..t-.. -;-*-* *-........,_~*- * -
- _.............
,....,~........... --.-*-* ~ -+-*, _ ___,__,. J 4819 I 4418 ii;::::...----!::::!::::::!n(J:::=;l=!=.b -19.. "'" f 4016 100 50 l t
40 +
f l
30 J l
20 1 I
10 t 0
)
0 30 i
I
°F 40 I Ca\\ illllion lntcrl<X:k I I
i I
- *t
- -+-*
50 60 70 80 90 100 Co1-e f"low (%)
J~l~IWI 110 t 3614 l
3213 ~
~
1 2811 ~
t 2410 ~
r
-=
... 2008 ~
I
~
+ 1606 I *~*
! 803 t 402
. ! 0 120