ML022830178

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Issuance of Core Operating Limits Report for Reload 14, Cycle 15, Revision 0
ML022830178
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 10/01/2002
From: Gallagher M
Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TS 5.6.5.d
Download: ML022830178 (33)
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Text

Exekrns.

Exelon Nuclear wwwexeloncorpcom Nuclear 20o Exelon Way Kennett Square, PA 19348 TS 5.6.5.d October 1, 2002 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Peach Bottom Atomic Power Station, Unit 2 Facility Operating License No. DPR- 44 NRC Docket No. 50-277

Subject:

Issuance of the Core Operating Limits Report for Reload 14, Cycle 15, Revision 0

Dear Sir/Madam:

Enclosed is a copy of the Core Operating Limits Report (COLR) for P~each Bottom Atomic Power Station (PBAPS), Unit 2, Reload 14, Cycle 15, Revision 0. Revision 0 of this report incorporates the revised cycle specific parameters resulting from the new core configuration implemented during the PBAPS, Unit 2 outage.

This COLR is being submitted to the NRC in accordance with PBAPS, Unit 2 Technical Specifications (TS) Section 5.6.5.d.

If you have any questions, please do not hesitate to contact us.

Very truly yours, Michael P. Gallagher Director, Licensing and Regulatory Affairs Mid-Atlantic Regional Operating Group Enclosure cc: H. J. Miller, Administrator, Region I, USNRC (w/enc)

A. C. McMurtray, USNRC Senior Resident Inspector, PBAPS (w/enc)

EXELON-COLR-P2C1 5 Exelon Nuclear - Nuclear Fuels Page 1, Rev. 0

'P2C1 5 Core Operating Limits Report CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 2 RELOAD 14, CYCLE 15 REVISION 0 Prepared By: - aate: vD ,/

Matthew M. Heverly Engineer Reviewed By: Date: 0-2z-0--

James J. Tusar Engineer Approved By: Date: 8/a-(0 2..

/

Randy T. Tropasso Manager, BWR Design Branch

EXELON-COLR-P2C1 5 Exelon Nuclear - Nuclear Fuels Page 2, Rev. 0 P2C1 5 Core Operating Limits Report LIST OF EFFECTIVE PAGES Page(s) Revision 1 -32 0

EXELON-COLR-P2C1 5 Fxelon Nuclear - Nuclear Fuels Page 3, Rev. 0 P2C1 5 Core Operating Limits Report INTRODuCTION AND RUMMARV limits for Peach Bottom Atomic Power This report provides the following cycle-specific parameter Station Unit 2 Cycle 15 (Reload 14):

"* Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

"* ARTS MAPLHGR thermal limit multipliers

"* 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 and MCPR Limits

"* Rod Block Monitor (RBM) Analytical Limits, Allowable Values

"* Linear Heat Generation Rate (LHGR)

"* Turbine Bypass Valve Parameters

"° EOC Recirculation Pump Trip (EOC-RPT) Parameters methodology and are established such These values have been determined using NRC-approved met.

that all applicable limits of the plant safety analysis are Limit MCPR and MAPLHGR thermal This report provides the means for calculating the Operating limits for the following conditions:

Maximum Extended

"* All points in the operating region of the power/flow map including Load Line Umit (MELLL) down to:

MWt) operation

  • 81% of rated core flow during rated thermal power (3458 82.9% of rated core flow 0 For Appendix K power uprate (References 11 and 18) -

during rated thermal power (3514 MWt) operation

"* Increased Core Flow (ICF), up to 110% of rated core flow 40%

"* End-of-Cycle Power Coastdown to a minimum power level of reduction at any time

"* Feedwater Heaters Out of Service (FWHOOS) to 550 F temperature during the cycle End-of-Rated (EOR) and

"* Final Feedwater Temperature Reduction (FWTR) between line End-of-Cycle (EOC) to 900 F temperature reduction maintaining 5 100% load (Reference 1)

A

"* Asymmetric Feedwater Temperature Operation (AFTO) - Appendix feedwater temperature as a function of The Allowable Values, documented in Reference (1), for in the appropriate Peach Bottom thermal power for both FWHOOS and FWTR are specified procedures.

which operation at "rated conditions" is no Note that the term "EOR" refers to the cycle exposure at begins) based on the EOR point as longer possible (i.e., the cycle exposure at which cycle extension Report.

documented in the current revision of the Cycle Management

EXELON-COLR-P2C1 5 Exelon Nuclear - Nuclear Fuels Page 4, Rev. 0 P2C1 5 Core Operating Limits Report and MCPR lirfiits jertain to NON - AFTO. A Also note that the following descripti6n of MAPLHGR ARTS figures are located in Appendix A.

separate description of AFTO limits and their associated with Exelon Nuclear procedures. This report Preparation of this report was performed in accordance 5.6.5 of Reference (2) and contains all is submitted in accordance with Technical Specification of the ARTS Improvement Program and thermal limit parameters related to the implementation for Peach Bottom Unit 2 Cycle 15.

Maximum Extended Load Line Limit Analyses (ARTS/MELLLA)

MAPLHrR -IMITS type are provided in Figures 1 through 6. The The bounding MAPLHGR limits (kW/ft) for each fuel limits of the fuel lattices (excluding natural uranium) bounding MAPLHGR limits are the lowest kW/ft planar exposure. The MAPLHGR figures which comprise a given fuel type as a function of average MAPLHGR values for each fuel type as a function are used when hand calculations are required. All be less than or equal to the applicable of axial location and average planar exposure shall types to be in compliance with Technical MAPLHGR limits for the respective fuel and lattice specified in References (4), (5) and (17) and the Specification 3.2.1. These MAPLHGR limits are MAPLHGR power-dependent multipliers process computer databank. The ARTS-based Figure 7 is valid for seven or more (of nine) Turbine (MAPFAC(P)) are provided in Figures 7 and 8. a maximum Bypass Valves (TBVs) In-Service and Recirculation Pump Trip (RPT) In-Service with 0 Figure 8 is valid for three or more (of nine) TBVs temperature reduction of 9T F for FWTR operation.

FWTR of 900 F. The flow-dependent multipliers Out-of-Service (OOS) or RPTOOS with a maximum in as a function of the number of recirculation loops (MAPFAC(F)) are provided in Figures 9 and 10 as shown in is applied through MAPFAC(F) operation only. The SLO MAPLHGR multiplier (0.73) fuel product line. MAPFAC(F) is clamped at 0.73 Figure 10. This value is based on the GE14 clad temperatures are maintained within the limits starting at 33.6% of rated core flow to ensure peak loop operation. The power- and flow of the cycle-specific LOCA analysis for single recirculation References (1), (6), (7) and (9). AFTO dependent MAPLHGR multipliers were obtained from parameters are addressed in Appendix A.

MrPBJ ULMS Technical Specification 3.2.2 for each fuel type is The Operating Limit MCPR (OLMCPR) for use in in by the cycle-specific fuel reload analyses provided in Table 1. These values are determined Bypass Valve and Recirculation Pump Trip Reference (4). For Single Loop Operation with Turbine comply with the OLMCPR is increased to 1.38 to in-service (Option B) from BOC to EOR-2000, the Pump Seizure Analysis described in Reference results of the Single Loop Operation Recirculation violating the Reference (13) SLO SLMCPR (13). This OLMCPR increase is necessary to prevent flows. For all other operating domains, considering the appropriate ARTS multiplier for single pump in SLO (due to the 0.02 safety limit MCPR the OLMCPR is increased by 0.02 when operating documented in Section 2.1.1.2 of Reference (2).

increase for SLO). The Safety Limit MCPRs are per Technical Specification 3.1.4, "Control Rod Control rod scram time verification is required as to notch position 36 throughout the Scram Times". Tau, a measure of scram time performance time test results. The calculation of Tau shall be cycle, is determined based on the cumulative scram interpolation shall be used to calculate the performed in accordance with site procedures. Linear B) and 1.0 (Tau Option A).

OLMCPR value if Tau is between 0.0 (Tau Option (Table 1) for the following domains:

Separate OLMCPR values are presented herein In-Service, maximum FWTR of 90 OF

"*TBVs In-Service (seven or more in-service) and RPT and RPT In-Service, maximum FWTR of 90 OF

"*TBVs Out-of-Service (three or more out-of-service)

Out-of-Service, maximum FWTR of 90 OF

"*TBVs In-Service (seven or more in-service) and RPT

5EXELON-COLR-P Exelon Nuclear - Nuclear Fuels P2CI 5 Core Operating Limits Report Page 5, Rev. 0 The OLMCPR values are documented in Reference (4) for the GE13 and GE14 fuel designs.

The ARTS-based power-dependent MCPR limits, OLMCPR(P), for use in Technical Specification Turbine 3.2.2 are provided in Figures 11 and 12. Figure 11 is valid for seven or more (of nine)

Bypass Valves (TBVs) In-Service and Recirculation Pump Trip (RPT) In-Service and a maximum temperature reduction of 90 OF for FWTR operation. Figure 12 is valid for three or more (of nine)

TBVs Out-of-Service (OOS) or RPTOOS with a maximum FWTR of 90 OF. The flow-dependent conditions MCPR limits, OLMCPR(F), are provided in Figure 13. Figure 13 is valid for all operating OLMCPR(P, F) curves were obtained from with symmetric feedwater temperature operation.

References (1), (6), (7) and (9). AFTO parameters are addressed in Appendix A.

OVERALL GOVERNING MCPR AND MAPLHr.R LIMITS that allow for ARTS provides for power- and flow-dependent thermal limit adjustments and multipliers a more reliable administration of the MCPR and MAPLHGR thermal limits. At any given power/flow (P/F) state, all four limits are to be determined: MAPFAC(P), MAPFAC(F), OLMCPR(P), and limiting OLMCPR(F) from Figures 7 through 20, inclusive. The most limiting MCPR and the most MAPLHGR [maximum of OLMCPR(P) and OLMCPR(F) and minimum of MAPLHGR(P) and fuel MAPLHGR(F)] for a given (P,F) condition will be the governing limits. The OLMCPR for each type is determined by the cycle-specific fuel reload analyses in Reference (4). Rated MAPLHGR values are a composite of results obtained from bundle-specific thermal-mechanical and emergency in core cooling system analyses. Supporting documentation for the ARTS-based limits is provided References (1), (4), (7), (8) and (9).

ROD RLOCK MONITOR R-TPOINTS The RBM power-biased Analytical Limits, Allowable Values and MCPR Limits for use in Technical in Specification 3.3.2.1 are provided in Table 2 per Reference (6) with supporting documentation References (4) and (10).

I INEAR Hi, AT G;ENFRATION RATER The beginning of life (maximum) LHGR values for each fuel type for use in Technical Specification provided in 3.2.3 are provided in Table 3. The LHGR values as a function of fuel exposure are in Reference (3).

References (5) and (17). The bases for the LHGR values are documented STEAM BYPASS SYSTEM OPERARILITY Specification The operabilitv requirements for the steam bvpass system are poverned bv Technical dependent limits for Turbine Bvpass 3.7.6. If the requirements cannot be met, the appropriate power 12 or Fiaures 15 and Valves Out-of-Service (TBVOOS) must be used (Table 1 with Fiaures 8 and 19). The minimum number of bvyass valves to maintain system operabilitv is seven as per Reference (11) and Table 4. Table 4 also includes other Turbine Bvpass Valve parameters.

Exelon Nuclear - Nuclear Fuels EXELON-COLR-P2Cl 5 "P2C15 Core Operating Limits Report Page 6, Rev. 0 RFCIRCULATION PUMP TRIP (.OC-RPT) OPFRARILITY rOC If the EOC-RPT is inoperable, then the OLMCPR (Table 1), MAPFAC(P) (Figure 8), and OLMCPR(P) (Figure 12) values for EOC Recirculation Pump Trip Out-of-Service (RPTOOS), must be used. Appendix A contains MAPFAC(P) and OLMCPR(P) for RPTOOS and AFTO.

3.3.4.2 The measured EOC-RPT Response Time as referenced in Technical Specifications Section and as defined in Technical Specifications Section 1.1 shall be:

< 0.145 seconds for TCV Fast Closure Trip (i.e. Generator Load Rejection)

< 0.155 seconds for TSV Fast Closure Trip ( i.e. Turbine Trip )

is A total RPT response time of 0.175 seconds is assumed in the safety analysis for both trips and defined as the time from the turbine valves (TCV or TSV) start to close until complete arc suppression of the EOC-RPT circuit breakers. Reference (12) provides the basis for the RPT response time.

CONCURRFNTTRVOOQ AND RPTOOQ Cycle 15 is not licensed for TBVOOS and RPTOOS to occur concurrently. Therefore, concurrent TBVOOS and RPTOOS is an unanalyzed condition.

EXELON-COLR-P2Ci 5 Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report Page 7, Rev. 0

.EF.F.RNES

1. "Peach Bottom Atomic Power Station Evaluation for Extended Final Feedwater Temperature Reduction of 900 F', NEDC-32707P, Supplement 1, May 20,1998
2. "Technical Specifications for Peach Bottom Atomic Power Station Unit 2", Docket No. 50-277, Appendix A to License No. DPR-44
3. "General Electric Standard Application for Reactor Fuel', NEDE-2401 1-P-A-1 4, June 2000; and NEDE-2401 1-P-A-1 4-US, June 2000
4. "Supplemental Reload Licensing Report for Peach Bottom 2, Reload 14 Cycle 15", Global Nuclear Fuel Document No. 0000-0002-7262-SRLR, Rev. 0, August 2002 14
5. "Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Unit 2 Reload Cycle 15", Global Nuclear Fuel Document No. 0000-0002-7262-MAPL, Revision 0, August 2002
6. "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
7. "ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station", NEDC-32847P, June 1998 1995
8. Letter, G. V. Kumar to A. M. Olson, "PECO Rerate Project, ARTS Thermal Limits", June 27,
9. "Peach Bottom Atomic Power Station Units 2 & 3 Plant and Cycle-Independent ARTS Thermal Limits Analyses", NEDC-32162P, Supplement 1, Revision 0, August 2001
10. PECO Energy Calculation PE-0251, "Power Range Neutron Monitoring System Setpoint Calculations Peach Bottom Atomic Power Station Units 2 & 3," Revision 1 April 29,
11. Email from C. P. Collins to J. J. Tusar, "Resolved OPL-3 for Peach Bottom 2 Cycle 15,"

2002 (Including Attached Resolved OPL-3 form) to

12. PECO Calculation PE-0173, "Determination of Total Time Required to Initiate the Trip Signal the EOC-RPT Circuit Breaker," Revision 1 Units 2
13. "GE14 Fuel Design Cycle-Independent Analyses for Peach Bottom Atomic Power Station

& 3," GENE Li 2-00880-00-01 P, September 2000

14. "Safety Review for Peach Bottom Atomic Power Station Units 2 and 3 Asymmetric Feedwater Temperature Operation", NEDC - 32691 P, Revision 0, May 1997
15. ECR 02-00478, "Assymetric Feedwater Operation Implementation"
16. Letter, F. T. Bolger to C. P. Collins, "Removal of MCPR(F) Low Flow Correction in NEDC 32847P," February 4, 2002.

2 Reload 13

17. "Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Unit Cycle 14", Global Nuclear Fuel Document No. J1 1-03716MAPL, Revision 2, January 2001 Atomic
18. Letter, Michael P. Gallagher to U. S. Nuclear Regulatory Commission, "Peach Bottom Nos. DPR-44 and DPR-56, NRC Docket Power Station Units 2 & 3, Facility Operating License Uprate Request for Nos 50-277 and 50-278, License Amendment Request 01-01190 "Power Appendix K Measurement Uncertainty Recapture," May 24,2002

.Exelon Nuclear - Nuclear Fuels EXELON-COLR-P2C1 5 Page 8, Rev. 0 P2C15 Core Operating Limits Report FIGURE 1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE GEl 3-P9DTB406-12GZ-1 00T-1 46-T 14.00 THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 12.00 10.00 ! i 8.001 cc I, 6.00 1 A At%

2.00 0.00 E::

40.0 50.0 60.0 70.0 0.0 10.0 20.0 30.0 Average Planar Exposure, GWd/ST Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (kwItu) (GWd/SI) (kWttt (GWdILSI) (kWht) (GMWISIT) 11.83 30.0 11.41 0.0 10.67 8.0 11.92 32.66 11.09 0.2 10.72 9.0 12.01 35.0 10.81 1.0 10.82 10.0 12.08 40.0 10.20 2.0 10.96 12.5 12.15 45.0 9.57 3.0 11.11 15.0 12.20 50.0 8.89 4.0 11.27 17.5 55.0 7.25 11.43 20.0 12.12 5.0 56.7 6.61 11.60 24.38 11.86 6.0 57.58 6.28 11.72 25.0 11.82 7.0

EXELON-COLR-P2C 15 Exelon Nuclear - Nuclear Fuels Page 9, Rev. 0 P2C15 Core Operating Limits Report FIGURE 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE GE1 3-P9DTB409-13GZ-1 DOT-1 46-T 14.00 12.00 10.00 8.00 "r 6.00

-4 4.00 2.00 0.004 20.0 30.0 40.0 50.0 60.0 0.0 10.0 Average Planar Exposure, GWdWST Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (rWdIlAI) (kW/ft) (GWdISI) (kW"f1 (GwWfSI) JkWJWk 11.34 30.0 11.35 0.0 10.38 8.0 11.54 32.66 11.04 0.2 10.42 9.0 11.73 35.0 10.76 1.0 10.48 10.0 11.96 40.0 10.16 2.0 10.57 12.5 12.12 45.0 9.51 3.0 10.67 15.0 12.12 50.0 8.83 4.0 10.77 17.5 12.00 55.0 7.03 5.0 10.88 20.0 11.79 56.7 6.38 6.0 11.00 24.38 11.76 56.99 6.28 7.0 11.16 25.0

EXELON-COLR-P2C15 Page 10, Rev. 0 Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report FIGURE 3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE GE1 4-P1 ODNAB397-15GZ-1 OT-1 50-T 12 10 8

E r

0.

60.0 20.0 30.0 0.0 10.0 Average Planar Exposure, GWdIST Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR (kW/fi)

Exposure MAPLHGR (GVM~d1SI. (kW/fk) (GWdLSI-)

20.0 10.92 9.52 8.0 10.63 0.0 10.54 10.76 25.0 9.59 9.0 0.2 10.08 10.89 30.0 9.70 10.0 1.0 9.55 11.02 35.0 9.86 11.0 2.0 9.03 11.04 40.0 10.02 12.0 3.0 8.50 11.05 45.0 10.14 13.0 4.0 7.96 11.06 50.0 10.26 14.0 5.0 6.28 11.06 55.0 10.38 15.0 6.0 4.92 11.04 57.68 10.50 17.0 7.0

EXELON-COLR-P2C1 5 Exelon Nuclear - Nuclear Fuels Page 11, Rev. 0 P2C1 5 Core Operating Limits Report FIGURE 4 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE GE1 4-P1 ODNAB396-14GZ-1 00T-1 50-T 1200- 1 1

  • "-" *THS FUEJ ISFFFRM:TO BY M"__. T -NCAL SPIEMRCA'1'ION 32.1 E

floo C,

1 0.

4 4.00

,"~UU Q000 _______ 4 .4 *1 7ao aC0 10,0 2a0 3ao 40. 5WO Average PlaW Exposure GWI*ST Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (niwdLS'r (kWtft) (Gwd*ll*SI (GwdLSIý (kWltM 9.84 8.0 10.72 20.0 10.90 0.0 9.0 10.84 25.0 10.54 0.2 9.90 10.0 10.95 30.0 10.08 1.0 9.99 11.0 11.07 35.0 9.55 2.0 10.08 12.0 11.10 40.0 9.03 3.0 10.18 13.0 11.10 45.0 8.50 4.0 10.29 14.0 11.10 50.0 7.96 5.0 10.39 15.0 11.08 55.0 6.32 6.0 10.50 17.0 11.04 57.78 4.92 7.0 10.61

EXELON-COLR-P2CI5 Exelon Nuclear - Nuclear Fuels Page 12, Rev. 0 P2C1 5 Core Operating Limits Report FIGURE 5 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE 12 10 E

3 C,

-J 0.

4 20.0 30.0 40.0 50.0 60.0 0.0 10.0 Average Planar Exposure, GWd/ST FUEL TYPE GE1 4-PI ODNAB416-1 5GZ-1 DOT-1 50-T Avg Plan Avg Plan Avg Plan MAPLHGR Exposure MAPLHGR Exposure MAPLHGR Exposure (G&wdlSr (kW/ft) 8.0 10.58 20.0 10.55 0.0 9.67 9.0 10.69 25.0 10.16 0.2 9.77 10.0 10.81 30.0 9.73 1.0 9.88 11.0 10.92 35.0 9.29 2.0 9.97 12.0 10.91 40.0 8.83 3.0 10.06 13.0 10.88 45.0 8.33 4.0 10.16 14.0 10.85 50.0 7.79 5.0 10.26 15.0 10.82 55.0 5.50 6.0 10.36 17.0 10.74 56.28 4.86 7.0 10.47

Exelon Nuclear - Nuclear Fuels EXELON-COLR-P2C1 5 Page 13, Rev. 0 P2C1 5 Core Operating Limits Report FIGURE 6 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE GE14-P1ODNAB416-16GZ-100T-150-T 12 10 8

e-j

_1 CL

  • =4 30.0 40.0 50.0 60.0 0.0 10.0 20.0 Average Planar Exposure, GWdfST Avg Plan Avg Plan Avg Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (kW/lfi) 9.49 8.0 10.51 20.0 10.49 0.0 9.55 9.0 10.60 25.0 10.16 0.2 9.66 10.0 10.68 30.0 9.74 1.0 9.81 11.0 10.76 35.0 9.30 2.0 9.97 12.0 10.73 40.0 8.84 3.0 10.12 13.0 10.69 45.0 8.35 4.0 10.24 14.0 10.65 50.0 7.82 5.0 15.0 10.62 55.0 5.53 6.0 10.35 10.43 17.0 10.58 56.28 4.89 7.0

EXELON-COLR-P2CI 5

-Exelon Nuclear - Nuclear Fuels P2C1 5 Core Page 14, Rev. 0 Operating Limits Report FIGURE 7 POWER-DEPENDENT MAPLHGR MULTIPLIER, MAPFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 VALID FOR 7 OR MORE TBVs IN-SERVICE, RPT IN-SERVICE AND MAX 90° F FWTR 1.1 (85,1.000) (100,1.WQ 1.0 0.9 K MA~t~HG(650.6)=MFACpMPU1sd 0.8-F4~~r PJ~O/:No~hemlus mvolrngRqie NWorrs specified a.

U 0.7 For 25% < P< P(Bypass):

LL < 60% lRow (P(Bypass) = 30*%f or PBAPS Unds 2 &3)

0. MAPFAC(p) = 0.60 + 0.00320 * (P-30) For Flow < 60%

1 U, (25,0.58,4, (30,0.600) MAPFAC(p) = 0.568 + 0.00720 - (P-30) For Flow > 60%

-a 0.6 I

U, V (30,0.568)

For 30% < P < 65%:

For 65% <P< 85%:

MAPFAC(p) = 0.960 + 0.006 (P-65)

MAPFAC(p) =1.000 + 0.002 (P-85) a

0. 0.5. (25>00F32w For 85%

600%Flow 0.4 03.

A 15 60 65 70 75 80 85 90 95 100 20 25 30 35 40 45 50 55 Power (% Rated)

EXELON-COLR-P2C1 5

  • xelon Nuclear - Nuclear Fuels Page 15, Rev. 0 P2C1 5 Core Operating Limits Report FIGURE 8 POWER-DEPENDENT MAPLHGR MULTIPLIER, MAPFAC(P) and 3.7.6 THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1, 3.3.4.2 VALID FOR 3 OR MORE TBVOOS OR RPTOOS AND MAX 90 OF FWTR 4 4 I1.

(95,1.000) 1.0 (100.1. )00)

(85,0.930) 0.9 0.8-0.7 (30,0.700) MAPLHGR(p) = MAPFAC(P) -MAPLHGR(std)

ForP 5%:No .. m...iit

.... *ororn

,-iequlru No limits specified S0.6 /i 60%/= Flow For 25% et P < P(Bypass):

(P(Bypass) = 30% for PBAPS Units 2 & 3)

(30,0.572)

MAPFAC(p) = 0 572 + 0 01300 * (P-30) For Flow 4 60(r/

MAPFAC(p).=.0 460 + 0.00780 * (P-30) For Flow > 601/%

0.5 (25,06107) (30,0.460) 0 MAPFAC(p) = 0930 + 000418 (P-85)

I. For 30%/ P <85%:

For 85% P < 95%/6: MAPFAC(p) = 1.000 + 0.0070 (P-95) 0.4 (25,0 21 .

For 95% 4 P: MAPFAC(p) = 1.000

  • > 60% Flow 0.3-0.2 35 40 45 50 55 60 65 70 75 80 85 90 95 100 20 25 30 Power (% Rated)

Exelon Nuclear - Nuclear Fuels Page 16, Rev. 05 EXELON-COLR-P2C1 P2C1 5 Core Operating Limits Report FIGURE 9 FLOW-DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F) 3.2.1 THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION VALID FOR TWO LOOP RECIRC FLOW 1.1 1.0 0.9 0.8 It.

0.

20.7 0.6 0.5 0.4 50 60 70 80 90 100 110 10 20 30 40 CORE FLOW (% RATED)

EXELON-COLR-P2C1 5

.Exelon Nuclear - Nuclear Fuels Page 17, Rev. 0 P2Cl 5 Core Operating Limits Report FIGURE 10 FLOW-DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 AND 3.4.1 VALID FOR SINGLE LOOP RECIRC FLOW 1.1 MAPLHGR(F) = MAPFAC(F) - MAPLHGRstd 1i+ MAPLHGRstd = Standard MAPLHGR Limits MAPFAC(F) = (Af

  • WT/ 100 + Bf), OR

= 0.73; whichever is lower 0.9 t WT = % Rated Core Flow Af = 0.6682, Bf = 0.5055 0.8 +

C II 0

0.73 a.

0.7 +

0.6" 0.572 0.5 1 0.4 30 40 50 60 70 80 90 100 110 10 20 Core Flow (%Rated)

EXELON-COLR-P2CI 5 Exelon Nuclear - Nuclear Fuels Page 18, Rev. 0 P2C1 5 Core Operating Limits Report IABaLE OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR)

Applicable to all fuel types Use in conjunction with Figures 11, 12, 13, 18, 19, and 20 For OLMCPR when in Single Loop Operation, See Note (2).

These Tables are referred to by Technical Specification 3.2.2, 3.4.1 and 3.7.6 TBV in Service and TBV out of Service RPT OOS RPT in Service (3 or more TBVOOS)

Option B Option A Option B Option A Option B Option A 0 1 ',= 0 1T=0 1r= 1 1C= 1r=

BOC to EOR -2000 1.33 1.36 1.37 1.40 1.38 1.49 Two Loop Operation MWd/ST EOR - 2000 MWd/ST to 1.37 1.40 1.41 1.44 1.42 1.59 EOC BOC to EOR -2000 1.38(3) 1.38 1.39 1.42 1.40 1.51 Single Loop Operation MWd/ST EOR - 2000 MWd/ST to 1.39 1.42 1.43 1.46 1.44 1.61 EOC NOTES:

1) When Tau does not equal 0 or 1, use linear interpolation.
2) For single-loop operation, the MCPR operating limit is 0.02 greater than the two loop value except when the Two Loop Operation MCPR operating limit is less than 1.36 (consistent with Reference 13).
3) OLMCPR limit set by the Single Loop Operation (SLO) - Recirculation Pump Seizure Analysis.

(Reference 13)

EXELON-COLR-P2CI 5 Exelon Nuclear - Nuclear Fuels Page 19, Rev. 0 "P2C1 5 Core Operating Limits Report FIGURE 11 POWER-DEPENDENT MCPR LIMIT, OLMCPR(p), AND MULTIPLIERS 3.2.2 THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION AND MAX 90 OF FWTR VALID FOR 7 OR MORE TBVs IN-SERVICE, RPT IN-SERVICE 4.0' 3.8 Operating Umrt MCPR (P) = Kp *Operating Unit MCPR (100)

For P< 25%: No Thermal Umits Monitoring Requred 3.6 No limits specifWe For 25% c P < P(Bypass):

3.4 (P(Bypass) = 30% for PBAPS Units 2 &3) 3.2 OLMCPR(p) = 2.40 + 0.02* (30-P) For Flow -c 60%

OLMCPR(p) = 2.55 + 0.04 * (30-P) For Flow > 60%

3.0 For30% -P<65%: K(P)=1.131 +0.00597(65-P) 00 > 60% Row For65% £P: K(p)=1.000+0.00375(1O0-P)

S2.8- N5 ý

0. (2525.2 252.50) (30 2.55) S2.6

. 2.4 (30,2.40) 0 2.2 -.c 60% Flow 2.0 1.8 "X 1.6 2

C.

-1.4  : (30,1.340),

".5

  • (65,1.131) 1
1 S1.2 1.0 55 60 65 70 75 80 85 90 95 100 20 25 30 35 40 45 50 Power (% Rated)

EXELON-COLR-P2CI 5

  • Exelon Nuclear - Nuclear Fuels Page 20, Rev. 0 P2C1 5 Core Operating Limits Report FIGURE 12 POWER-DEPENDENT MCPR LIMIT, OLMCPR(p), AND MULTIPLIERS and 3.7.6 THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2, 3.3.4.2 VALID FOR 3 OR MORE TBVOOS OR RPTOOS AND MAX 90 OF FWTR 4.0 3.8 Operating Umit MCPR (P) . Kp
  • Operating Limit MCPR (100)

>60% Flow 3.6 For P< 25%" No Thermal Limits Monitoring Required No limits specified 3.4 For 25% c P < P(Bypass)"

25. 3.R5) (P(Bypass) - 30% for PBAPS Units 2 & 3) 32
  • OLMCPR(P) = 2.75 + 0.10D (30-P) For Flow 4 60%

OLMCPR(p) = 3.25 + 0.10 * (30-P) For Flow > 60%

0 3.0 0-0 For3O% P-P<65%" K(P)-1.131 ÷000597(65-P)

For 65% c P: K(p) = 1.000 + 0.00375 (100- P) 2.8 0 (30, 2.75) c.

2.6 2.4 S60%/. Flow 2.2 0

0.

2.0 0.

1.8 S

1.6 1.4  :(30.1 .340)

(65,1.131) 1.2 1.0 (100,1.0)

L 50 55 60 65 70 75 80 85 90 95 100 20 25 30 35 40 45 Power (% Rated)

Exelon Nuclear - Nuclear Fuels EXELON-COLR-P2Cl 5 P2C 5 Core Operating Limits Report Page 21, Rev. 0 FIGURE 13 FLOW-DEPENDENT MCPR LIMITS, OLMCPR(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 VALID FOR ALL CONDITIONS 2.00 For Two Loop Operation, SLMCPR " 1.12 1.90 MCPR(F) = The Maximum of EITHER 1.25 OR { -0.5784 x (WT/10 0 )+ 1.70731 1.80 WT=  % Rated Core Flow 1.70 .7073 1.60 1.534 0 1.50 1.40 1.30 1.25 1.25 1.20 1.10

-2n AA 50 60 70 80 90 100 110 IV . . Cor~e Flow (% R'ated)-

EXELON-COLR-P2C1 5 Exelon Nuclear - Nuclear Fuels Page 22, Rev. 0 P2C1 5 Core Operating Limits Report TABLEL2 ROD BLOCK MONITOR ANALYTICAL LIMITS, ALLOWABLE VALUES, AND MCPR LIMITS THIS TABLE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.3.2.1 Applicability: BOC to EOC ANALYTICAL ALLOWABLE MCPR FUNCTION .LIMITI." VALUE"'* LIMIT Low Power Range - Upscale <5123.0% __121.2% < 1.70(2)

< 1.40 (3' (Low Trip Setpoint)

<5118.0% _<116.2% < 1.70 (2)

Intermediate Power Range - Upscale < 1.40 (3)

(Intermediate Trip Setpoint)

High Power Range - Upscale _< 113.2% <111.4% < 1.70 (2)

< 1.40 (

(High Trip Setpoint)

N/A N/A < 1.70 (2)

Inop < 1.40 (3)

(1) These Trip Level Settings (with RBM filter time constant between 0.1 and 0.55 seconds) are based on a cycle-specific rated RWE MCPR limit of 1.30 which is less than the minimum cycle OLMCPR (References (4), (6) and (10))

(2) This is the MCPR limit (given THERMAL POWER ; 28.4%and < 90% RTP) below which the RBM is required to be OPERABLE (References (4) and (6) and TS Table 3.3.2.1-1).

(3) This is the MCPR limit (given THERMAL POWER > 90% RTP) below which the RBM is required to be OPERABLE (References (4) and (6) and TS Table 3.3.2.1-1).

EXELON-COLR-P2CI 5

.Exelon Nuclear - Nuclear Fuels Page 23, Rev. 0 P2CI 5 Core Operating Limits Report TABLEN A DESIGN LINEAR HEAT GENERATION RATE (LHGR) LIMITS U.L.L_.TYE LU.GULAII GEl3 14.4 kW/ft GE14 13.4 kW/ft 1 The LHGR limits provided above are the beginning of life (maximum) values. The LHGR limits as a function of fuel exposure are provided in References (5) and (17).

EXELON-COLR-P2C 15 Exelon Nuclear - Nuclear Fuels Page 24, Rev. 0 P2C1 5 Core Operating Limits Report TURBINE BYPASS VALVE PARAMETERS TURRINF BYPASS SYRTFM RESPONN*F TIMES Maximum delay time before start of bypass valve opening following generation of the turbine bypass valve flow signal 0.10 sec Maximum time after generation of a turbine bypass valve flow signal for bypass valve position to reach 80% of full flow (includes 0.30 sec.

the above delay time)

Minimum required number of bypass valves to maintain system operability 1 71

EXELON-COLR-P2C1 5

ýExelon Nuclear - Nuclear Fuels Page 25, Rev. 0 P2C15 Core Operating Limits Report ASYMMETRIC FEEDWATER TEMPERATURE OPERATION feedwater Asymmetric feedwater heating (resulting from removing a heater string, or individual lines at Peach heaters, from operation) is the result of the specific configuration of the feedwater strings will result in a temperature Bottom. A reduction in heating either the 'A' or the 'C' heater the reactor vessel.

mismatch between the feedwater flows entering the opposite sides of in a feedwater Asymmetric feedwater temperature operation (AFTO) is defined as operation specified threshold temperature difference. This heater/string configuration which results in a threshold values is incorporated in the threshold is a function of power and flow. The curve of the station procedures that govern AFTO (Reference 15).

been applied to the As a result of analyses documented in Reference (14), a 4% penalty has curves to ensure MCPR ARTS curves and a 7% penalty has been applied to the MAPLHGR ARTS while in AFTO.

that sufficient thermal margin exists during anticipated operational occurrences MAPI Hr.R I IMITR feedwater The ARTS-based MAPLHGR power-dependent multipliers (MAPFAC(P)) for asymmetric 14 is valid for seven temperature operation are provided in Appendix A, Figures 14 and 15. Figure Pump Trip (RPT) In or more (of nine) Turbine Bypass Valves (TBVs) In-Service and Recirculation W5O F between the two Service, maximum 90 OF FWTR, with a maximum temperature differential of (of nine) TBVs Out-of-Service (OOS) or feedwater sparger lines. Figure 15 is valid for three or more differential of 550 F between the two RPTOOS, maximum 90 OF FWTR, with a maximum temperature are provided in feedwater sparger lines. The flow-dependent multipliers (MAPFAC(F)) for AFTO in operation only.

Appendix A, Figures 16 and 17 as a function of the number of recirculation loops a 7% penalty, through MAPFAC(F) as shown in The SLO MAPLHGR multiplier (0.73) is applied, with of rated core flow to ensure peak clad Figure 17. MAPFAC(F) is clamped at 0.679 starting at 33.6%

LOCA analysis for single temperatures are maintained within the limits of the cycle-specific and flow-dependent recirculation loop and asymmetric feedwater temperature operation. The power-were adjusted with a MAPLHGR multipliers were obtained from References (1), (4), (6) and (7) and 7% penalty as per Reference (14).

MCPR..MITS Specification The ARTS-based power-dependent MCPR limits, OLMCPR(P), for use in Technical are provided in Appendix A, Figures 18 3.2.2 during asymmetric feedwater temperature operation Bypass Valves (TBVs) In-Service and and 19. Figure 18 is valid for seven or more (of nine) Turbine temperature Recirculation Pump Trip (RPT) In-Service, maximum 90 OF FWTR, with a maximum for three or more (of differential of 550 F between the two feedwater sparger lines. Figure 19 is valid a maximum nine) TBVs Out-of-Service (OOS) or RPTOOS, maximum 90 OF FWTR, with The flow-dependent temperature differential of 550 F between the two feedwater sparger lines.

20 is valid for all MCPR limits, OLMCPR(F), for AFTO are provided in Appendix A, Figure 20. Figure curves were obtained operating conditions with AFTO. The power- and flow-dependent OLMCPR a 4% penalty as per Reference (14).

from References (1), (4), (6) and (7) and were adjusted with

EXELON-COLR-P2CI5

  • Exelon Nuclear - Nuclear Fuels Page 26, Rev. 0 P2CI 5 Core Operating Limits Report FIGURE 14 POWER-DEPENDENT MAPLHGR MULTIPLIER, MAPFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 MAX 55 OF VALID FOR 7 OR MORE TBVs IN-SERVICE, RPT IN-SERVICE, MAX 90 °F FWTR, WITH TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 1.1 1.0 (85,0.930) (100,0 930) 0.9 0.8 MAPFAC(P) *MAPUGR(std)

'APLHGR(p)

For P< 25%ANo Thermal Umits Monitoring Required 0.7 No limits specified w

0. For 25% < P < P(Bypass).

(P(Bypass) = 30% for PBAPS Units 2 & 3) 0.6 MAPFAC(p) - 0.558 + 0 00300° (P-30) For Flow <60%

MAPFAC(p) = 0 528 + 0.00660 (P-30) For Flow > 60%

CL For 30% <P < 65%: MAPFAC(p) = 0 893 + 0.0056 (P-65) 0.5* <P <85%: MAPFAC(p) =0930 + 00019 (P-85)

,.! For 65%

For 85% < P: MAPFAC(p) = 0 930

> 60% Flow 0.4 0.3 02  !  !

20 40 45 50 55 60 65 70 75 80 85 90 95 100 25 30 35 Power (% Rated)

,Exelon Nuclear - Nuclear Fuels EXELON-COLR-P2C1 5 Page 27, Rev. 0 P2C1 5 Core Operating Limits Report FIGURE 15 POWER-DEPENDENT MAPLHGR MULTIPLIER, MAPFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1, 3.3.4.2, and 3.7.6 VALID FOR 3 OR MORE TBVOOS OR RPTOOS, MAX 90 -F FWTR, WITH MAX 55 -F TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 1.1 1.0 (95,0.930)

,30) 0.9 (85,o.865) Z 0.8.

0.71 (30,0 651)

U MMAPLHGR(p) = MAPFAC(p)

, 60% Flow 0.6 For P< 25%5 No Thermal Umits Monitoring Required No limits specified 0.

For 25% _sP < P(Bypass):

(30,0.532) (P(Bypass) = 30% for PBAPS Units 2 & 3) cE

1. 0.5-MAPFAC(p) = 0 532 + 0.01200 (P-30) For Flow <60%

0 (25,0 * ,172) MAPFAC(p) = 0.428 + 0.00720 * (P-30) For Flow > 60%

0.

(.7 (30,0428) For 300 < P < 85%" MAPFAC(p) = 0.865 + 0.00389 (P-85) 0.4 Sj For 85% <P < 95%: MAPFAC(p) = 0.930 + 0.00650 (P-95)

(25,0 *92) .

> 60r/6 Flow For 95% < P: MAPFAC(p) = 0.930 0.3 0.2 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Exelon Nuclear - Nuclear Fuels EXELON-COLR-P2C1 5 Page 28, Rev. 0 P2C1 5 Core Operating Limits Report FIGURE 16 FLOW-DEPENDENT MAPLHGR MULTIPLIER, MAPFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 VALID FOR 2 LOOP RECIRC FLOW WITH MAX 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 1.0

  • I "" 0.930 0.93C 0.9 0.0 0.8 0.7 0.6 MAPLHGR(F) = MAPFAC(F)

IL 0.532 L< 0.5 For Two Loop Operation, > 70% WT at. MAPFAC(F) = The Minimum of EITHER 0.930 OR {0.0250 x (WT - 70)/10 + 0.90501 For Two Loop Operation, < 70% WT 0.4 MAPFAC(F) = {0.6217 x (WT/100)+ 0.4701)

WT=  % Rated Core Flow 0.3 0.2+

0.1 t'A 4' I I I I I I 10 20 30 40 50 60 70 80 90 100 110 CORE FLOW (% RATED)

.Exelon Nuclear - Nuclear Fuels EXELON-COLR-P2C1 5 Page 29, Rev. 0 P2C15 Core Operating Limits Report FIGURE 17 FLOW-DEPENDENT MAPLHGR MULTIPLIER, MAPFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 AND 3.4.1 VALID FOR SINGLE LOOP RECIRC FLOW WITH MAX 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 1.0-0.9+

0.8 0.7 0.679 0.679

-nI I 0.657 0.6 +

0O.532 0,I 0.5 MAPLHGR(F) = MAPFAC(F)

MAPLHGR(std) = Standard MAPLHGR Limits 0.4 +

MAPFAC(F) = MIN(0.679, Af*WT/100 + Bf);

where, 0.3- WT = % Rated Core Flow Af = 0.6217, Bf = 0.4701 0.2t 0.1 0.0 110 10 20 30 40 50 60 70 80 90 100 CORE FLOW (% RATED)

EXELON-COLR-P2CI 5 Exelon Nuclear - Nuclear Fuels Page 30, Rev. 0 P2CI 5 Core Operating Limits Report FIGURE 18 POWER-DEPENDENT MCPR LIMIT, OLMCPR(p), AND MULTIPLIERS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 VALID FOR 7 OR MORE TBVs IN-SERVICE, RPT IN-SERVICE, MAX 90 OF FWTR, WITH MAX 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 3.01 I

> 60% Flow 2.8 t Y42.65 2.6 t 2.60:

0 v

2.50 0

OPERATING UMIT MCPR(P) Kp

  • OPERATING LIMIT MCPR(100) 0 4 60% Flow FOR P<25%: NO THERMAL LIMITS MONITORING REQUIRED NO LIMITS SPECIFIED 0.

FOR 25% e. P < 30%:

2.2-OLMCPR(P) = 2.50 + 0.02 ° (30% - P) FOR FLOW ..60h OLMCPR(P) = 2.65 + 0.04 * (30% - P) FOR FLOW > 60%

FOR 30% ýaP <65%: Kp= 1.176 + 0 00623 * (65% -P) 2.0 t FOR 65% e. P: Kp= 1.040 + 0.00389 * ( 100% - P) 1.8 t 1.6j

.391 .4 1.4 t 0 1.2f I-00 I ' T I I 1.0 I 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

EXELON-COLR-P2CI 5 Exelon Nuclear - Nuclear Fuels Page 31, Rev. 0 P2C1 5 Core Operating Limits Report FIGURE 19 POWER-DEPENDENT MCPR LIMIT, OLMCPR(p), AND MULTIPLIERS and 3.7.6 THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2,3.3.4.2, VALID FOR 3 OR MORE TBVOOS OR RPTOOS, MAX 90 -F FWTR, WITH MAXIMUM 55 -F TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 3.8 operating Umit MCPR (P) = Kp *Operating Umit MCPR (100) 3.6 For P< 25%: No Thermal Umits Monitonng Required No limits specified (25, 3 P8) 3.4- , (30, 338) For 25% _S P < P(Bypass):

(P(Bypass) = 30% for PBAPS Units 2 & 3)

< 60% FlowOLMCPR(p) = 2.86 010 (30-P) For Flow < 60%

_"40 *

  • OLMCPR(p) = 3.38 + 0.10" (30-P) For Flow > 60%

0 0 3.0 For 30% :S P < 65%: K(P) = 1.176 + 0.00623 (65 - P)

V (30, 2.86) For 65% <_P: K(p) 1.04 + 0 00389 (100- P)

"2.8 C)

.J 2.6 0

2.4 2.2 2.0 1.8

.- 1.6 (30.1.394)

" 1.4 T (65,1.176)

S(100,1.04) 1.2 10A 10v 20 40 45 50 55 60 65 70 75 80 85 90 95 100 25 30 35 Power (% Rated)

SExelon Nuclear - Nuclear Fuels EXELON-COLR-P2CI 5 P2C15 Core Operating Limits Report Page 32, Rev. 0 FIGURE 20 FLOW-DEPENDENT MCPR LIMITS, OLMCPR(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 AND 3.4.1 VALID FOR ALL CONDITIONS WITH MAXIMUM 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 2.00 For Two Loop Operation, SLMCPR a 1.12 1.901 MCPR(F) = The Maximum of EITHER 1.30 OR ( -0.6016 x (WT/100)+ 1.7756)

WT=  % Rated Core Flow 1.80 1.776 1.701 U 1.601 1.595 0

1.50 1.401 1.30- 5 1.300 1.300 1.20-4 .4' & I I,1v 0 10 20 30 40 so 60 70 80 90 100 110 Core Flow (% Rated) s-Nndb\cor*pb2\P2C15_COLR_rO.doc

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