ML14337A048
| ML14337A048 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/02/2014 |
| From: | Massaro M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TS 5.6.5.d | |
| Download: ML14337A048 (23) | |
Text
1IOExelon Generation.
TS 5.6.5.d December 2, 2014 U.S. Nuclear Regulatory Commission Attention: 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 20, Cycle 21, Revision 9 Enclosed is a copy of Revision 9 of the Core Operating Limits Report (COLR) for Peach Bottom Atomic Power Station (PBAPS) Unit 2 for Reload 20, Cycle 21.
Revision 9 of this report 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.
Should you have any questions concerning this letter, please contact Dave Foss at (717) 456-4311.
Michael J. Massaro Site Vice President Peach Bottom Atomic Power Station CCN: 14-99 Attachment Core Operating Limits Report for Reload 20, Cycle 21, Revision 9 cc:
Regional Administrator, Region I, USNRC (without attachments)
USNRC Senior Resident Inspector, PBAPS (without attachments)
Project Manager - PBAPS, USNRC (with attachments)
R. R. Janati, Pennsylvania Bureau of Radiation Protection (without attachments)
S. T. Gray, State of Maryland (without attachments)
ATTACHMENT Core Operating Limits Report for Reload 20, Cycle 21, Revision 9
Exnia Nudlr -Nuder Fuels P2C21 Com Opeming imkts Rept COLR PEACH BOTTOM 2 Rev. 9 Page t of 21 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 2 RELOAD 20, CYCLE 21 (This is a Complete Re-write)
Prepared By:
P. Henriy Reviewed By: 14.A*1 -. t A 6Reactor Engineering Reviewed By:
Engineering Safety Analysis Date:
- 6 Date: t!ZI/21/
Date:___ý/
Independent Review By: /
Yl' oos Date:____
Approved By:
Date:
Date: 0/,z 9/)
Reviewer.
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 9 P2C21 Core Operating Limits Report Page 2 of 21 Table of Contents Page 1.0 Terms and Definitions 4
2.0 General Information 5
3.0 MAPLHGR Limits 6
4.0 MCPR Limits 7
5.0 Linear Heat Generation Rate Limits 10 6.0 Rod Block Monitor Setpoints 12 7.0 Turbine Bypass Valve Parameters 13 8.0 EOC Recirculation Pump Trip (EOC-RPT) Operability 14 9.0 Stability Protection Oscillation Power Range Monitor (OPRM) 15 10.0 Asymmetric Feedwater Temperature Operation (AFTO) 16 11.0 Modes of Operation 20 12.0 Methodology 20 13.0 References 21
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 9 P2C21 Core Operating Limits Report Page 3 of 21 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure 6
Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier 6
Table 4-1 Operating Limit Minimum Critical Power Ratio 8
Table 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers 9
Table 4-3 Flow Dependent MCPR Limits MCPR(F) 9 Table 4-4 SLO Flow Dependent MCPR Limits MCPR(F) 9 Table 5-1 Linear Heat Generation Rate Limits - U02 rods 10 Table 5-2 Linear Heat Generation Rate Limits - Gad rods 10 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 11 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) 11 Table 6-1 Rod Block Monitor Setpoints 12 Table 7-1 Turbine Bypass System Response Time 13 Table 7-2 Minimum Required Bypass Valves to Maintain System Operability 13 Table 9-1 OPRM PBDA Trip Settings 15 Table 9-2 OPRM PBDA Trip Settings - SLO 15 Table 10-1 AFTO Thermal Limit Penalties 16 Table 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTA!5 55F 17 Table 10-3 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTA _ 55F 17 Table 10-4 AFTO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTA__ 55F 18 Table 10-5 AFTO Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) 20F < FWT DELTA 5 55F 18 Table 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 20F < FWT DELTA _ 55F 19 Table 10-7 AFTO MAPLHGR Reduction Factor 19 Table 11-1 Modes of Operation 20 Table 11-2 Additional Equipment Out Of Service Modes of Operation 20
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 9 P2C21 Core Operating Limits Report Page 4 of 21 1.0 Terms and Definitions AFTO Asymmetric Feedwater Temperature Operation AFTO LFWH Asymmetric Feedwater Temperature Operation Loss-of-Feedwater Heating ARTS APRM and RBM Technical Specification Analysis BASE Defines two (2) loop operation with at least seven turbine bypass valves in service and the reactor recirculation pump trip system in service.
BOC Beginning Of Cycle 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 100% (3951 MWth) with recirculation system flow equal to 100%, all 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 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 MSIVOOS Main Steam Isolation Valve Out of Service OLMCPR Operating Limit Minimum Critical Power Ratio OPRM PBDA Oscillation Power Range Monitor Period Based Detection Algorithm PLUOOS Power Load Unbalance Out of Service PROOS Pressure Regulator Out of Service RPTOOS Recirculation Pump Trip Out of Service RWE Rod Withdrawal Error SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation TBVOOS Turbine Bypass Valves Out of Service TCV/TSVOOS Turbine Control Valve/Turbine Stop Valve Out of Service
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 9 P2C21 Core Operating Limits Report Page 5 of 21 2.0 General Information This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 2 CYCLE 21 (RELOAD 20):
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Single Loop Operation (SLO) MAPLHGR multipliers Operating Limit Minimum Critical Power Ratio (OLMCPR)
ARTS MCPR thermal limit adjustments and multipliers Single Loop Operation (SLO) MCPR adjustment Linear Heat Generation Rate (LHGR)
ARTS LHGR thermal limit multipliers Single Loop Operation (SLO) LHGR multipliers Rod Block Monitor (RBM) Analytical Limits, Allowable Values and MCPR Limits Turbine Bypass Valve Parameters EOC Recirculation Pump Trip (EOC-RPT) Parameters Dual Loop Stability Protection - Oscillation Power Range Monitor (OPRM) Trip Setpoints Single Loop Stability Protection - Oscillation Power Range Monitor (OPRM) Trip 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.
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 Maximum Extended Load Line Limit (MELLL) down to 99% of rated core flow during full power (3951 MWt) operation 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) to 550 F temperature reduction Final Feedwater Temperature Reduction (FFWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) to 90' F temperature reduction (40 and 5h stage FFWTR)
Asymmetric Feedwater Temperature Operation (AFTO)
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 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.
Also note that the following description of MAPLHGR, LHGR and MCPR limits pertain to NON - AFTO conditions. A separate description of AFTO limits and their associated ARTS tables are located in Section 10.
Preparation of this report was performed in accordance with Exelon Nuclear procedures. This report is provided to the NRC in accordance with Technical Specification 5.6.5 of Reference 1 and contains all thermal limit parameters related to the implementation of the ARTS Improvement Program and Maximum Extended Load Line Limit Analysis (ARTS/MELLLA) for Peach Bottom Unit 2 Cycle 21.
The "BASE" thermal limit values shown in tables are for normal two loop operation with at least seven turbine bypass valves in service and the reactor recirculation pump trip system in service.
Exelon Nuclear - Nuclear Fuels P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 6 of 21 3.0 MAPLHGR LIMITS 3.1 Technical Specification Section 3.2.1, 3.3.4.2, 3.4.1 and 3.7.6 3.2 Description The MAPLHGR limits (kW/fl) 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. The MAPLHGR tables are used when hand calculations are required. 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.
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 TABLE 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2)
SLO Multiplier 10.73
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 9 P2C21 Core Operating Limits Report Page 7 of 21 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 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, 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).
Separate OLMCPR values are presented in Table 4-1 for the following conditions:
- TBVs In-Service (per section 7.0), RPT In-Service (per section 8.0), and maximum FFWTR of 90 *F (a.k.a. "BASE")
" TBVs Out-of-Service (per section 7.0), RPT In-Service (per section 8.0), and maximum FFWTR of 90 'F
" TBVs In-Service (per section 7.0), RPT Out-of-Service (per section 8.0), and maximum FFWTR 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 of 90 'F for FFWTR 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 10.
Exelon Nuclear - Nuclear Fuels P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 8 of 21 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (Reference 2)
SCRAM Cycle Exposure Time
< EOR - 4409
> EOR - 4409 EOOS Combination Option0 1 )
MWd/ST MWd/ST B
1.38(2) 1.38(3)
BASE A
1.38(7 1.46 B
1.42 1.42 BASE SLO(4)
A 1.42 1.50 B
1.38(5) 1.39 TBVOOS A
1.39 1.48 B
A 1.43 1.52 B
1.38(6) 1.43 RPTOOS A
1.53 1.60 B
1.42 1.47 RPTOOS SLO(4)
A 1.57 1.64 (1)
When Tau does not equal 0 or 1, use linear interpolation.
(2) Analyzed DLO Option B OLMCPR is 1.29 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.
(3) Analyzed DLO Option B OLMCPR is 1.38 per Reference 2, value is maintained to obtain an OPRM amplitude setpoint of 1.11.
(4) For single-loop operation, the MCPR operating limit is 0.04 greater than the analyzed limiting two loop value. However a minimum value of 1.42 is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).
(5) Analyzed DLO Option B OLMCPR is 1.30 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.
(6) Analyzed DLO Option B OLMCPR is 1.36 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.
(7)
Analyzed DLO Option A OLMCPR is 1.37 per Reference 2, value is adjusted to obtain an OPRM amplitude setpoint of 1.11.
Exelon Nuclear - Nuclear Fuels P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 9 of 21 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 23 1 <26.7 [_26.7 1 40 1 55 65 1 85 100 of rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp
< 60 2.56 2.56 2.49 Base 1.352 1.352 1.317 1.131 1.082 1.000
> 60 2.86 2.86 2.71
< 60 2.60 2.60 2.53 Base SLO 1.352 1.352 1.317 1.131 1.082 1.000
> 60 2.90 2.90 2.75
< 60 2.56 2.56 2.49 RPTOOS 1.352 1.352 1.317 1.131 1.082 1.000
> 60 2.86 2.86 2.71
< 60 2.60 2.60 2.53 RPTOOS SLO 1.352 1.352 1.317 1.131 1.082 1.000
> 60 2.90 2.90 2.75
< 60 3.48 3.48 3.11 TBVOOS 1.659 1.479 1.373 1.155 1.082 1.000
> 60 3.97 3.97 3.62
< 60 3.52 3.52 3.15 TBVOOS SLO 1.659 1.479 1.373 1.155 1.082 1.000
> 60 4.01 4.01 3.66 TABLE 4-3 Flow Dependent MCPR Limits MCPR(F)
(Symmetric Feedwater Heating)
(Reference 2)
Core Flow MCPR(F)
(% rated)
Limit 0.0 1.701 30.0 1.530 79.0 1.250 110.0 1.250 TABLE 4-4' SLO Flow Dependent MCPR Limits MCPR(F)
(Symmetric Feedwater Heating)
(Reference 2)
Core Flow MCPR(F)
(% rated)
Limit 0.0 1.741 30.0 1.570 79.0 1.290 110.0 1.290 1
For single-loop operation, the MCPR operating limit is 0.04 greater than the analyzed limiting two loop value (with the exception of the OPRM based OLMCPR which remains the same).
Exelon Nuclear - Nuclear Fuels P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 10 of 21 5.0 LINEAR HEAT GENERATION RATE 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 of 900 F for FFWTR operation. 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 0.73 and is 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.
TABLE 5-1 Linear Heat Generation Rate Limits - U02 rods (References 4 and 11)
Fuel Type LHGR Limit GNF2 See Appendix B of Reference 4 TABLE 5-2 Linear Heat Generation Rate Limits - Gad rods (References 4 and 11)
Fuel Type LHGR Limit GNF2 See Appendix B of Reference 4
Exelon Nuclear - Nuclear Fuels P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 11 of 21 TABLE 5-3 Power Dependent LHGR Multiplier LHGRFAC(P)
(Symmetric Feedwater Heating)
(Reference 2)
Core Thermal Power (% of rated)
EOOS Combination M of rated) 0 23
<26.7 1>_26.7 40 1 55 65 1 85 1 100 LHGRFAC(P) Multiplier
< 60 0.508 0.508 0.522 Base 0.748 0.756 0.771 0.817 0.959 1.000
> 60 0.508 0.508 0.522
< 60 0.508 0.508 0.522 Base SLO 0.748 0.756 0.771 0.817 0.959 1.000
> 60 0.508 0.508 0.522 RPTOOS 0.748 0.756 0.771 0.817 0.959 1.000
> 60 0.508 0.508 0.522
< 60 0.508 0.508 0.522 RPTOOS SLO 0.748 0.756 0.771 0.817 0.959 1.000
> 60 0.508 0.508 0.522
< 60 0.397 0.397 0.442 TBVOOS 0.635 0.655 0.714 0.817 0.930 1.000
>60 0.410 0.410 0.417
< 60 0.397 0.397 0.442 TBVOOS SLO 0.635 0.655 0.714 0.817 0.930 1.000
> 60 0.410 0.410 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 P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 12 of 21 6.0 ROD BLOCK MONITOR SETPOINTS 6.1 Technical Specification Section 3.3.2.1 6.2 Description The RBM power-biased Analytical Limits, Allowable Values and MCPR Limits are provided in Table 6-1 with supporting documentation in References 2 and 9.
TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 9)
Power Level Analytical Limit')
Allowable Value(1)
121.2%
< 1.70 (2)
< 1.40 (3)
ITSP 118.0%
116.2%
< 1.70(2)
< 1.40 3 HTSP 113.2%
111.4%
< 1.70(2)
< 1.40 (2)
INOP N/A N/A
< 1.70 (2)
< 1.40(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 9).
(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).
....~ 94..0,j Vi' ~.1'.tn
- 1.
- 44.Q7p ~&cJI#
Exelon Nuclear - Nuclear Fuels P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 13 of 21 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 Valves Out-of-Service (TBVOOS) must be used. Additionally, the OLMCPR for TBVOOS 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 14.
TABLE 7-1 Turbine Bypass System Response Time (Reference 14)
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% of full flow (includes the 0.30 sec above delay time)
(1)
First movement of any TSV or any TCV or generation of the turbine bypass valve flow signal (whichever occurs first)
TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability (Reference 14)
Reactor Power No. of Valves in Service P Ž_ 23%
7
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 9 P2C21 Core Operating Limits Report Page 14 of 21 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.
A total RPT response time of 0.175 seconds is assumed in the safety analysis and is defined as 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. Reference 7 provides the basis for the RPT response time.
Exelon Nuclear - Nuclear Fuels P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 15 of 21 9.0 STABILITY PROTECTION OSCILLATION POWER RANGE MONITOR (OPRM) 9.1 Technical Specification Section 3.3.1.1, Table 3.3.1.1-1 Function 2.f 9.2 Description The CYCLE 21 OPRM Period Based Detection Algorithm (PBDA) Trip Settings are provided in Table 9-1 and 9-2. These values are based on the cycle specific analysis documented in Reference 2. The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system, Reference 13.
The OPRM Growth Rate Algorithm (GRA) and Amplitude Based Algorithm (ABA) trip settings for dual loop and single loop can be found in the Power Range Neutron Monitoring Configuration Control Documents (SPID's) G-080-VC-234 through 237 (Unit-2).
TABLE 9-1 OPRM PBDA Trip Settings (Valid for All Conditions)
(Reference 2)
PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting 1.11 14 TABLE 9-2 OPRM PBDA Trip Settings - SLO(1)
(Valid For SLO Conditions Only)
(Reference 2)
PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting 1.17 17 (1) The standard two loop operation OPRM Trip Settings specified in Table 9-1 must be implemented prior to restarting the idle pump when exiting the SLO condition.
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 9 P2C21 Core Operating Limits Report Page 16 of 21 10.0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION (AFTO)
Asymmetric feedwater heating (resulting from removing a heater string, or individual feedwater heaters, from operation) 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 P2C21 COLR Rev. 9 is the first COLR to no longer require implementation of SLO AFTO penalty files. The station no longer requires SLO AFTO files or penalties due to a 3D MONICORE upgrade required for EPU operation. Asymmetric feedwater temperature operation (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 10-1 will be implemented when the threshold asymmetry temperature (temperature above which a penalty is required) is exceeded. This will minimize the number of AFTO thermal limit tables in the COLR and core monitoring system.
TABLE 10-1 AFTO Thermal Limit Penalties (Asymmetric Feedwater Heating)
(Reference 10)
_MFLCPR MFLPD/MAPRAT 40F < FWT DELTA _ 55F 3%
4%
30F < FWT DELTA5 _40F 2%
3%
20F < FWT DELTA_ 30F 2%
2%
OF < FWT DELTA!< 20F No Penalty No Penalty LHGR LIMITS The ARTS-based LHGR power-dependent multipliers for AFTO operation are provided in Table 10-2. The flow-dependent multipliers for AFTO in DLO are provided in Table 10-3.
The power-and flow-dependent LHGR multipliers were obtained from Reference 2 and were adjusted with the appropriate penalties displayed in Table 10-1 as per Reference 10. 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 Table 10-1 are applied to the thermal limits. Additionally, no LHGR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.
Exelon Nuclear - Nuclear Fuels P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 17 of 21 TABLE 10-2 AFro Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTA < 55F (Asymmetric Feedwater Heating)
(References 2 and 10)
Core Thermal Power (% of rated)
EOOSCominaionCore Flow _____________________________
EOOSCombination/
of rated) 0 23
<26.7 1_26.7 1 40 1 55 65 1 85 195 1100 LHGRFAC(P) Multiplier Base
- 60 0.488 0.488 0.501 0.718 0.726 0.740 0.784 0.921 0.947 0.960
> 60 0.488 0.488 0.501
< 60 0.488 0.488 0.50 1 RPTOOS 0.718 0.726 0.740 0.784 0.921 0.947 0.960
> 60 0.488 0.488 0.501
< 60 0.381 0.381 0.424 TBVOOS 0.610 0.629 0.685 0.784 0.893 0.938 0.960
> 60 0.394 0.394 0.400
_II I
TABLE 10-3 AFrO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTA _ 55F (Asymmetric Feedwater Heating)
(References 2 and 10)
Core Flow (% of rated)
EOOS Combination 0
30 33.60 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.486 0.678 0.701 0.934 0.960 0.960
Exelon Nuclear - Nuclear Fuels P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 18 of 21 MCPR LIMITS, 2:.
The OLMCPRs during asymmetric feedwater temperature operation with a feedwater temperature difference greater than 20 'F are provided in Table 10-4. The ARTS-based power-dependent MCPR limits for use during AFTO conditions are provided in Table 10-5. The flow-dependent MCPR limits for AFTO are provided in Table 10-6. The power and flow-dependent OLMCPR curves were obtained from Reference 2 and were adjusted with a 3% penalty for feedwater temperature difference greater than 20 *F as displayed in Table 10-1 as per Reference 10. No MCPR penalties are required for asymmetric temperature differentials less than or equal to 20 *F. Additionally, no MCPR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.
TABLE 10-4 AFTO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTA _ 55F (Asymmetric Feedwater Heating)
(References 2 and 10)
SCRAM Cycle Exposure Time
< EOR - 4409
> EOR - 4409 EOOS Combination Option°1 )
MWd/ST MWd/ST B
1.42 1.42 BASE A
1.42 1.50 B
1.42 1.43 TBVOOS A
1.43 1.52 B
1.42 1.47 RPTOOS A
1.58 1.65 TABLE 10-5 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 20F < FWT DELTA < 55F (Asymmetric Feedwater Heating)
(References 2 and 10)
Core Core Thermal Power (% of rated)
EOOS Combination Fow (%
0 2
<26..7 6.7 140 55 65 85 100 of rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp
< 60 2.64 2.64 2.56 Base 1.352 1.352 1.317 1.131 1.082 1.000
> 60 2.95 2.95 2.79
< 60 2.64 2.64 2.56 RPTOOS 1.352 1.352 1.317 1.131 1.082 1.000
> 60 2.95 2.95 2.79
< 60 3.58 3.58 3.20 TBVOOS 1.659 1.479 1.373 1.155 1.082 1.000
> 60 4.09 4.09 3.73 (1) When Tau does not equal 0 or 1, use linear interpolation.
Exelon Nuclear - Nuclear Fuels P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 19 of 21 TABLE 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 20F < FWT DELTA < 55F (BOC to EOC)(Asymmetric Feedwater Heating)
(References 2 and 10)
Flow MCPR(F)
(% rated)
Limit 0.0 1.752 30.0 1.576 79.0 1.288 110.0 1.288 MAPLHGR LIMITS An appropriate penalty must be applied to MAPLHGR limits under asymmetric feedwater temperature operation (AFTO) for varying temperature differentials as displayed in Table 10-1 as per Reference 10.
No MAPLHGR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.
TABLE 10-7 AFrO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)
(References 2 and 10)
AFTO Reduction Factor 20F < FWT DELTA <55F 1 0.960
Exelon Nudear-Nuclear Fuels P2C21 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 9 Page 20 of 21 11.0 MODES OF OPERATION TABLE 11-1 Modes of Operation (Reference 2)
Supported Operating EOOS Options' Region 2 Base, Option A or B Yes Base SLO, Option A or B Yes TBVOOS, Option A or B Yes TBVOOS SLO, Option A or B Yes RPTOOS, Option A or B Yes RPTOOS SLO, Option A or B Yes TBVOOS and RPTOOS, Option A or B No TBVOOS and RPTOOS SLO, Option A or B No TABLE 11-2 Additional Equipment Out Of Service Modes of Operation EOOS PLUOOS (controlled via station procedures)
PROOS (controlled via station procedures)
TCV/TSVOOS (controlled via station procedures)
MSIVOOS (controlled via station procedures)
AFTO LFWH (controlled via station procedures) 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", NEDE-24011-P-A-20, December 2013 and U.S.
Supplement NEDE-2401 1-P-A-20-US, December 2013.
- 2. "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Unit 2 and 3", NEDC-32162P, Revision 2, March 1995.
- 3.
"Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications", NEDO-32465-A, Revision 0, August 1996.
1 Modes of operation with thermal limit sets in the COLR 2 Operating Region refers to operation on the Power to Flow map with or without FFWTR or AFTO
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 2 Rev. 9 P2C21 Core Operating Limits Report Page 21 of 21
13.0 REFERENCES
- 1. "Technical Specifications for Peach Bottom Atomic Power Station Unit 2", Docket No. 50-277, Appendix A to License No. DPR-44.
- 2. Global Nuclear Fuel Document "Supplemental Reload Licensing Report for Peach Bottom Unit 2, Reload 20, Cycle 21 Extended Power Uprate (EPU)", GNF Document No. 001N2149.3-SRLR, Revision 3, July 2014.
- 3. Global Nuclear Fuel Document "General Electric Standard Application for Reactor Fuel", NEDE-2401 l-P-A-20, December 2013 and U.S. Supplement NEDE-2401 I-P-A-20-US, December 2013.
- 4. Global Nuclear Fuel Document NEDC-33270P Rev. 5, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR H)," May 2013.
- 5.
General Electric Hitachi Document 001N2494 R1, "Peach Bottom EPU Evaluation of Feedwater Temperature vs.
Reactor Power for Feedwater Temperature Conditions of Nominal Rated, FWHOOS (Nominal -55°F) and FFWTR (Nominal -90°F)", July 2014.
- 6. Not Used
- 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.
General Electric Hitachi Document GEH-0000-0107-7348, "GNF2 Fuel Design Cycle-Independent Analyses For Exelon Peach Bottom Atomic Power Station Units 2 and 3", Revision 3, March 2012.
- 9.
PECO Calculation PE-025 1, Revision 1E, "PRNMS Setpoint Calculation" dated 8/25/11.
- 10. General Electric Hitachi Document 001N6733-R1, "Final Evaluation Report Exelon Nuclear Generating Company LLC, Peach Bottom Units 2 & 3, MELLLA+, Asymmetric Feedwater Temperature Operation for EPU/MELLLA+", Revision 1, September 2014. This document is searchable in Exelon EDMS under document number "PEAM-EPU-68 Rev. 1."
- 11. Global Nuclear Fuel Document 001N6160.1-FBIR, "Fuel Bundle Information Report for Peach Bottom Unit 2 Reload 20 Cycle 21 Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Analysis Plus (MELLLA+) and Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Analysis (MELLLA)",
Revision 1, July 2014.
- 12. Not Used
- 13. General Electric Document NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications", August 1996.
- 14. Exelon TODI ENSAF ID# ES1400004, Rev. 1, "Final Resolved OPL-3 Parameters for Peach Bottom Unit 2 Cycle 21 - EPU/IMELLLA+", May 9, 2014.