ML18179A359
| ML18179A359 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/27/2018 |
| From: | Herr M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TS 5.6.5.d | |
| Download: ML18179A359 (27) | |
Text
Exelon Generation TS 5.6.5.d June 27, 2018 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
Subject:
Issuance of the Core Operating Limits Report for Reload 21, Cycle 22 Enclosed is a copy of Revision 13 of the Core Operating Limits Report (COLR) for Peach Bottom Atomic Power Station (PBAPS) Unit 2 for Reload 21, Cycle 22. This midcycle revision incorporates alternate LHGR limits in order to recover MFLPD margin.
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.
Respectfully, r<l~71--
Matthew J. Herr Plant Manager Peach Bottom Atomic Power Station CCN: 18-62
Attachment:
Unit 2 Core Operating Limits Report for Reload 21, Cycle 22, Revision 13 cc: Regional Administrator, Region I, USNRC (without attachment)
USNRC Senior Resident Inspector, PBAPS (without attachment)
Project Manager - PBAPS, USN RC (with attachment)
R. R. Janati, Pennsylvania Bureau of Radiation Protection (without attachment)
S. T. Gray, State of Maryland (without attachment)
E~clon Nuclear - Nuclear Fuel! COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limns Report Page I of26 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 2 RELOAD 21, CYCLE 22 Prepared By: ~ Date:
5123/18 M. Doerzbacher - Nuclear Fuels 0 I Reviewed By: ~f.tpal. Date: S-/J'3/J8 M. Miller
- Reactor Engineering Reviewed By: ~9w7r- Date:
05/23/2018
- 8. Sarikaya - Engineering Safety Analysis Reviewed By:
Ike A. OJson* Engmeenng Safiety* AnaIys1s' Date: 05/23/18 Independent Review By: ~~~ Date: s1231201a K. Pfingsten - Nuclear Fuels Approved By:
~jJlf&l{J Date: 29MAY1B A. Jolmson - NF Sr. Manager Station Qualified Reviewer:
Htiu.:so1Jdl+ Date:
r'/jd /11
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 2 of26 Table of Contents Page Revision History 3 List of Tables 4 1.0 Terms and Definitions 5 2.0 General Infonnation 6 3.0 MAPLHGR Limits 7 4.0 MCPRLimits 8 5.0 LHGRLimits 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 0 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. 13 P2C22 Core Operating Limits Report Page 3 of26 0 Revision History Revision Description Revision 13 Revised to incorporate alternate LHGR limits Revision 12 Revised for Rated Thermal Power of 4016 MWth Revision 11 New Issue for Cycle 22 0
Exelon Nuclear- Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 4 of26 0 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 LHGRFAC(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 0 Table 9-3 Manual BSP Endpoints for Reduced Feedwater Temperature Table 10-1 AFTO Power Dependent LHGR Multiplier LHGRF AC(P) 20F < FWT DELTA :5 55F 18 20 Table 10-2 AFTO Flow Dependent LHGR Multiplier LHGRF AC(F) 20F < FWT DELTA :5 55F 20 Table 10-3 AFTO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTA :5 55F 21 Table 10-4 AFTO Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) 20F < FWT DELTA :5 55F 22 Table 10-5 AFTO Flow Dependent MCPR Limits MCPR(F) 20F < FWT DELTA :5 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. 13 P2C22 Core Operating Limits Report Page 5 of26 0 1.0 ABSP TERMS AND DEFINITIONS Automatic Backup Stability Protection AFTO Asymmetric Feedwater Temperature Operation AFTOLFWH Asymmetric Feedwater Temperature Operation Loss-of-Feedwater Heating APRM Average Power Range Monitor ARTS APRM and RBM Technical Specification Analysis BASE The "BASE" condition is defined by a group of individual operating conditions that arc 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 Begiruiing Of Cycle BSP Backup Stability Protection DSS-CD Detect and Suppress Solution - Confirmation Density DTSP Rod Block Monitor Downscale Trip Setpoint EOC End of Cycle EOOS Equipment Out of Service. An analyzed option that assumes certain equipment to be non-operational EOR End of Rated. The cycle exposure at which reactor power is equal to I00% with recirculation system flow equal to I 00%, alJ control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.
FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service FWT Feedwater Temperature HFCL High Flow Control Line HTSP Rod Block Monitor High Trip Setpoint ICF Increased Core Flow ITSP Rod Block Monitor Intermediate Trip Setpoint LHGR Linear Heat Generation Rate 0 LHGRFAC(F)
LHGRFAC(P)
ARTS LHGR thermal limit flow dependent adjustments and multipliers ARTS LHGR thermal limit power dependent adjustments and multipliers LTSP Rod Block Monitor Low Trip Setpoint MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F} ARTS MCPR thermal limit flow dependent adjustments and multipliers MCPR(P) ARTS MCPR thermal limit power dependent adjustments and multipliers MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ Maximum Extended Load Line Limit Analysis Plus MSIVOOS Main Steam Isolation Valve Out of Service NCL Natural Circulation Line OLMCPR Operating Limit Minimum Critical Power Ratio PLUOOS Power Load Unbalance Out of Service PROOS Pressure Regulator Out of Service RBM Rod Block Monitor RDF Rated Drive Flow RPTOOS Recirculation Pump Trip Out of Service RTP Rated Thermal Power RWE Rod Withdrawal Error SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation SRVOOS Safety Relief Valve Out of Service TBVOOS Turbine Bypass Valve Out of Service TB SOOS Turbine Bypass System Out of Service 0 Tcvrrsvoos TPO Turbine Control Valve and/or Turbine Stop Valve Out of Service Thermal Power Optimization, also known as Measurement Uncertainty Recapture
Exelon Nuclear- Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 6 of26 0 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 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%
0 of rated 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 (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 thermal-mechanical analysis documented in Reference 13. Supporting documentation for the ARTS-based limits is provided in Reference 2. The off-rated limits assumed in the ECCS-LOCA analyses bound the cycle-specific limits calculated for MELLLA+
operation. The Allowable Values documented in Reference 5 for feedwater temperature as a function of thermal power for both FWHOOS and FFWTR are specified in the appropriate Peach Bottom procedures. The Peach Bottom Unit 2 Cycle 22 core is comprised entirely of GNF2 fuel.
0
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 7 of26 0 3.0 MAPLHGR LIMITS 3.1 Technical Specification Section 3.2.1, 3.3.4.2, 3.4.l 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 3-1. 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 l 0.0.
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 0 TABLE3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2)
SLO Multiplier 0.73
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 8 of26 0 4.0 MCPRLIMITS 4.1 Technical Specification Section 2.1.1.2, 3.2.2, 3.3.4.2, 3.4.1 and 3.7.6 4.2 Description The Operating Limit MCPR (OLMCPR) for GNF2 fuel is provided in Table 4-1. These values are determined 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 Hof 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 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 PRIPLUOOS + 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) 0 (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 COLRPEACH BOTTOM2 Rev.13 P2C22 Core Operating Limits Report Page 9 of26 0 TABLE4-1 Operating Limit Minimum Critical Power Ratio (Reference 2)
SCRAM Cycle Exposure Time < EOR- 4096 ;:::EOR-4096 EOOS Combination Ootion<I) 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 RPTOOSSLO A 1.60 1.63 B 1.38 1.42 PR/PLUOOS A 1.44 1.50 B 1.42 1.44 PR/PLUOOSSLO A 1.46 1.52 B 1.42 1.47 TB SOOS A 1.51 1.56 B 1.44 1.49 TBSOOS SLO A 1.53 1.58 0
0 (1) When Tau does not equal 0 or l, use linear interpolation.
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 10 of26 0 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 ~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 RPTOOSSLO 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/PLUOOSSLO 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 0 TBSOOS SLO
.::;:60 3.66 3.66 3.27 1.399 1.323 1.237 1.155 1.079 1.000
>60 4.17 4.17 3.80 0
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 11 of26 0 TABLE4-3 Flow Dependent MCPR Limits MCPR(F)
(Symmetric Feedwater Heating)
(Reference 2)
-*~*,...
.&* au 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) eference 2 Co 0.0 1.76 30.0 1.59 86.0 1.27 110.0 1.27 0
0
Exelon Nuclear- Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 12 of26 0 5.0 5.1 LHGRLIMITS Technical Specification Section 3.2.3, 3.3.4.2, 3.4.l 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 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 PRIPLUOOS + 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.
TABLE5-1 Linear Heat Generation Rate Limits - U02 rods (References 10 and 13) 0 Fuel Type LHGRLimit GNF2 See Reference 13 TABLE 5-2 Linear Heat Generation Rate Limits - Gad rods (References 10 and 13)
Fuel Type LHGRLimit GNF2 See Reference 13 0
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 13 of26 0 TABLE5-3 Power Dependent LHGR Multiplier LHGRFAC(P)
(Symmetric Feedwater Heating)
(Reference 2)
Core Flow Core Thermal Power (% of rated)
(%of 0 22.6 <26.3 ;::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 0 TB SOOS
>60
~60 0.397 0.397 0.397 0.397 0.417 0.442 0.620 0.655 0.714 0.817 0.930 1.000 TBSOOS SLO 0.620 0.655 0.714 0.817 0.930 1.000
>60 0.397 0.397 0.417 TABLE5-4 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 0
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 14 of26 0 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.
TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 8)
Power Level Allowable Value<!) MCPRLimit LTSP 118.2% < 1.83 <2>
<I.SO <3>
ITSP 113.4% < 1.83 <2>
< l.SO <3>
0 HTSP 108.4% < 1.83 <2>
< 1.50 <3>
INOP NIA < 1.83 <2>
<I.SO <3>
(1) 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 OLMCPR based on other events (see COLR References 2 and 8).
(2) This is the MCPR limit (given TIIERMAL POWER is ~28.4% and< 90%) below which the RBM is required to be 0 OPERABLE (see COLR Reference 2 and TS Table 3.3.2.1-1).
(3) This is the MCPR limit (given TIIERMAL 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. 13 P2C22 Core Operating Limits Report Page 15 of26 0 7.0 7.1 TURBINE BYPASS VALVE PARAMETERS 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(I> for bypass valve position to reach 80% of full flow (includes the 0.30 sec above delay time) 0 (1) 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 P~22.6% 7 0
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 16 of26 0 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.
TABLES-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.
0 0
Exelon Nuclear* Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 17 of26 0 9.0 STABILITY PROTECTION 9.1 Technical Specification Section 3.3.1.1, Table 3.3.1.1-1 Function 2.f 9.2 Description Per Reference 2, the Cycle 22 DSS-CD SAD 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 Feed water 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.
TABLE9-1 Automatic BSP Setpoints for the Scram Region (Reference 2)
Parameter Symbol Value Slope of ABSP APRM flow-ffiTrip 1.62 biased trip linear segment.
ABSP APRM flow-biased trip setpoint power intercept.
0 Constant Power Line for Trip from zero Drive Flow to Flow Breakpoint value.
PasP-Trip 39.8 %RTP ABSP APRM flow-biased trip setpoint drive flow intercept. WasP-Trip 46.7 %RDF Constant Flow Line for Trip.
Flow Breakpoint value WasP-Break 25.0 %RDF 0
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 18 of26 0 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< 1>
0 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 30.1 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.
0 (1) 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. 13 P2C22 Core Operating Limits Report Page 19 of26 0 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 below 20°F, for a difference between 20 and 55°F there is a 4% LHGRIMAPLHGR 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 talcing 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 0 are required for AFTO while in SLO as previously discussed.
0
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 20 of26 0 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
$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 0 >60 0.488 0.488 0.501 TABLE 10-2 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTA::; 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 0
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 21 of26 0 10.2 MCPR LIMITS 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. 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 10-3 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 AFfO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTAS 55F (Asymmetric Feedwater Heating)
<References 2, 9 and 11)
SCRAM Cycle Exposure Time <EOR-4096 ::::,EOR-4096 EOOS Combination OptionC 1> 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 0 PRIPLUOOS TB SOOS A
B 1.48 1.46 1.55 1.51 A 1.56 1.61 B 1.46 1.51 PR/PLUOOS + TBSOOS A NIA NIA B 1.45 1.48 PR/PLUOOS + RPTOOS A NIA NIA 0 (1) When Tau does not equal 0 or 1, use linear interpolation.
Exelon Nuclear- Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 22 of26 0 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 ~26.3 40 55 65 85 100 EOOS Combination
(%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 0 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 0
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 23 of26 0
I 0.3 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 :S55F I 0.960 0
0
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 24 of26 0 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 of operation with thennal 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 Sneed Ootion Loop Operation SFTO/AFTO Base 1*2 AorB DLO or SL03 SFTO or AFTO TB SOOS A orB DLO orSL03 SFTOor AFTO RPTOOS AorB DLO or SL03 SFTO orAFTO PLUOOS A orB DLO or SL03 SFTOorAFTO PROOS A orB DLO orSL0 3 SFTOorAFTO PR/PLUOOS and TBSOOS B DLO AFT0 4 PR/PLUOOS and RPTOOS B DLO AFT04 TABLE 11-2 0 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 l l-2.
2 The 'Base' condition includes operation with FWHOOS/FFWTR. Operation not pennitted in the J\.1ELLLA+ Region for reduced FWT conditions as controlled by station procedures.
0 3
Operation in SLO not permitted in the J\.1ELLLA + Region as controlled by station procedures.
4 AFTO limits bound SFTO limits.
5 Pennitted at power levels provided in the applicable station procedure.
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 25 of26 0 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-24011-P-A-25, August 2017 and U.S. Supplement NEDE-24011-P-A-25-US, August 2017.
13.0 REFERENCES
- 1. "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-0 6.
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.
- 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 001 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 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 002N6786, "Fuel Bundle Information Report for Peach Bottom Unit 2 Reload 21 Cycle 22", Revision 1, May 2018.
- 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 TODI ENSAF ID# ES1700008, Rev. 0, "Final Resolved OPL-3 Parameters for Peach Bottom Unit 2 Cycle 22 TPO", 5/30/2017.
- 13. Global Nuclear Fuel Document 004N7833-P, Rev. 0, "PRIME-Based GNF2 LHGR Envelopes for Peach 0 Bottom Atomic Power Station Units 2 and 3, April 2018
Exelon Nuclear- Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 13 P2C22 Core Operating Limits Report Page 26 of26 0 APPENDIX A POWER/FLOW OPERATING MAP FOR MELLLA+ with TPO (Reference 6)
C01~ flow (:'\tlbm/hr) 0 10 20 30 40 50 60 70 80 90 100 110 120 120 i-,,..-.-...,,,..-=:;;=~:-=:;:=:;?---,,,.,..,..--1
- - ,.~~1~;~-~;;--* -:.-~~~~~----- *-*--~- -- -** : **~- *-*-*,.-** *-'--- - *-*i 4819 100%CLTP
- 3951 MWt l' 110 100% Core Flow
- 102.5 Mlb/hr 4418 l
100 _,O;:::::..----'=::"Qc:F:.===() 4UIO\l\11 J 4016
~*~* :U\\t l i 3614 I
I 3213 I
- f I
- :
-- 70 7 2811 ~
~I ~
I.
~
BSP Boundary
~
2410 l 60 s:; ti 1l Qi! 50 ~
.. 2008 ~
i 40 t 1 1606 0 30 otJ f
I 1205 20 il 803 10 - I 402 a
0 10 20 30 40 50 60 70 80 90 100 110 I
120 o
Core Flow(%)
0