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 Nuclear - Nuclear Fuels

'P2C1 5 Core Operating Limits Report EXELON-COLR-P2C1 5 Page 1, Rev. 0 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 2 RELOAD 14, CYCLE 15 REVISION 0 Prepared By: -

ate: vD a

,/

Matthew M. Heverly Engineer Reviewed By:

Date:

0-2z-0--

James J. Tusar Engineer Approved By:

/

Randy T. Tropasso Manager, BWR Design Branch Date: 8/a-(0 2..

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

Revision 0

1 -32

Fxelon Nuclear - Nuclear Fuels EXELON-COLR-P2C1 5 P2C1 5 Core Operating Limits Report Page 3, Rev. 0 INTRODuCTION AND RUMMARV This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power 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

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

"* Linear Heat Generation Rate (LHGR)

"* Turbine Bypass Valve Parameters

"° EOC Recirculation Pump Trip (EOC-RPT) Parameters 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 the means for calculating the Operating Limit MCPR and MAPLHGR thermal limits for the following conditions:

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

81% of rated core flow during rated thermal power (3458 MWt) operation 0

For Appendix K power uprate (References 11 and 18) - 82.9% of rated core flow during rated thermal power (3514 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 at any time during the cycle

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

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

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

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

Preparation of this report was performed in accordance with Exelon Nuclear procedures. This report is submitted in accordance with Technical Specification 5.6.5 of Reference (2) and contains all thermal limit parameters related to the implementation of the ARTS Improvement Program and Maximum Extended Load Line Limit Analyses (ARTS/MELLLA) for Peach Bottom Unit 2 Cycle 15.

MAPLHrR -IMITS The bounding MAPLHGR limits (kW/ft) for each fuel type are provided in Figures 1 through 6. The bounding MAPLHGR limits are the lowest kW/ft limits of the fuel lattices (excluding natural uranium) which comprise a given fuel type as a function of average planar exposure. The MAPLHGR figures are used when hand calculations are required. All MAPLHGR values for each fuel type as a function of axial location and average planar exposure shall be less than or equal to the applicable MAPLHGR limits for the respective fuel and lattice types to be in compliance with Technical Specification 3.2.1. These MAPLHGR limits are specified in References (4), (5) and (17) and the process computer databank. The ARTS-based MAPLHGR power-dependent multipliers (MAPFAC(P)) are provided in Figures 7 and 8. Figure 7 is valid for seven or more (of nine) Turbine Bypass Valves (TBVs) In-Service and Recirculation Pump Trip (RPT) In-Service with a maximum temperature reduction of 9T0 F for FWTR operation. Figure 8 is valid for three or more (of nine) TBVs Out-of-Service (OOS) or RPTOOS with a maximum FWTR of 900 F. The flow-dependent multipliers (MAPFAC(F)) are provided in Figures 9 and 10 as a function of the number of recirculation loops in operation only. The SLO MAPLHGR multiplier (0.73) is applied through MAPFAC(F) as shown in Figure 10. This value is based on the GE14 fuel product line. MAPFAC(F) is clamped at 0.73 starting at 33.6% of rated core flow to ensure peak clad temperatures are maintained within the limits of the cycle-specific LOCA analysis for single recirculation loop operation. The power-and flow dependent MAPLHGR multipliers were obtained from References (1), (6), (7) and (9). AFTO parameters are addressed in Appendix A.

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

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

"* TBVs Out-of-Service (three or more out-of-service) and RPT In-Service, maximum FWTR of 90 OF

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

Exelon Nuclear - Nuclear Fuels 5EXELON-COLR-P 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 3.2.2 are provided in Figures 11 and 12. Figure 11 is valid for seven or more (of nine) Turbine 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 MCPR limits, OLMCPR(F), are provided in Figure 13. Figure 13 is valid for all operating conditions with symmetric feedwater temperature operation. OLMCPR(P, F) curves were obtained from References (1), (6), (7) and (9). AFTO parameters are addressed in Appendix A.

OVERALL GOVERNING MCPR AND MAPLHr.R LIMITS ARTS provides for power-and flow-dependent thermal limit adjustments and multipliers that allow for 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 OLMCPR(F) from Figures 7 through 20, inclusive. The most limiting MCPR and the most limiting MAPLHGR [maximum of OLMCPR(P) and OLMCPR(F) and minimum of MAPLHGR(P) and MAPLHGR(F)] for a given (P,F) condition will be the governing limits. The OLMCPR for each fuel 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 core cooling system analyses. Supporting documentation for the ARTS-based limits is provided in 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 Specification 3.3.2.1 are provided in Table 2 per Reference (6) with supporting documentation in 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 3.2.3 are provided in Table 3. The LHGR values as a function of fuel exposure are provided in References (5) and (17). The bases for the LHGR values are documented in Reference (3).

STEAM BYPASS SYSTEM OPERARILITY The operabilitv requirements for the steam bvpass system are poverned bv Technical Specification 3.7.6. If the requirements cannot be met, the appropriate power dependent limits for Turbine Bvpass Valves Out-of-Service (TBVOOS) must be used (Table 1 with Fiaures 8 and 12 or Fiaures 15 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 "P2C1 5 Core Operating Limits Report Page 6, Rev. 0 rOC RFCIRCULATION PUMP TRIP (.OC-RPT) OPFRARILITY 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.

The measured EOC-RPT Response Time as referenced in Technical Specifications Section 3.3.4.2 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 )

A total RPT response time of 0.175 seconds is assumed in the safety analysis for both trips and is 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 Nuclear - Nuclear Fuels EXELON-COLR-P2Ci 5 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
5. "Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Unit 2 Reload 14 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
8. Letter, G. V. Kumar to A. M. Olson, "PECO Rerate Project, ARTS Thermal Limits", June 27, 1995
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
11. Email from C. P. Collins to J. J. Tusar, "Resolved OPL-3 for Peach Bottom 2 Cycle 15," April 29, 2002 (Including Attached Resolved OPL-3 form)
12. PECO Calculation PE-0173, "Determination of Total Time Required to Initiate the Trip Signal to the EOC-RPT Circuit Breaker," Revision 1
13. "GE14 Fuel Design Cycle-Independent Analyses for Peach Bottom Atomic Power Station Units 2

& 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.
17. "Lattice Dependent MAPLHGR Report for Peach Bottom Atomic Power Station Unit 2 Reload 13 Cycle 14", Global Nuclear Fuel Document No. J1 1-03716MAPL, Revision 2, January 2001
18. Letter, Michael P. Gallagher to U. S. Nuclear Regulatory Commission, "Peach Bottom Atomic Power Station Units 2 & 3, Facility Operating License Nos. DPR-44 and DPR-56, NRC Docket Nos 50-277 and 50-278, License Amendment Request 01-01190 "Power Uprate Request for Appendix K Measurement Uncertainty Recapture," May 24,2002

.Exelon Nuclear - Nuclear Fuels 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 12.00 10.00 !

i cc I,

8.001 6.00 1 A At%

EXELON-COLR-P2C1 5 Page 8, Rev. 0 THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 2.00 0.00 E::

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

Exelon Nuclear - Nuclear Fuels P2C15 Core Operating Limits Report EXELON-COLR-P2C 15 Page 9, Rev. 0 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 "r

-4 8.00 6.00 4.00 2.00 0.004 0.0 10.0 20.0 30.0 40.0 50.0 Average Planar Exposure, GWdWST MAPLHGR JkWJWk 10.38 10.42 10.48 10.57 10.67 10.77 10.88 11.00 11.16 Avg Plan Exposure (rWdIlAI) 8.0 9.0 10.0 12.5 15.0 17.5 20.0 24.38 25.0 MAPLHGR (kW/ft) 11.34 11.54 11.73 11.96 12.12 12.12 12.00 11.79 11.76 Avg Plan Exposure (GWdISI) 30.0 32.66 35.0 40.0 45.0 50.0 55.0 56.7 56.99 MAPLHGR (kW"f1 11.35 11.04 10.76 10.16 9.51 8.83 7.03 6.38 6.28 60.0 Avg Plan Exposure (GwWfSI) 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 7.0

Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2C15 Page 10, Rev. 0 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 0.0 10.0 20.0 60.0 30.0 Average Planar Exposure, GWdIST MAPLHGR (kW/fk) 9.52 9.59 9.70 9.86 10.02 10.14 10.26 10.38 10.50 Avg Plan Exposure (GWdLSI-)

8.0 9.0 10.0 11.0 12.0 13.0 14.0 15.0 17.0 MAPLHGR 10.63 10.76 10.89 11.02 11.04 11.05 11.06 11.06 11.04 Avg Plan Exposure 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 57.68 MAPLHGR (kW/fi) 10.92 10.54 10.08 9.55 9.03 8.50 7.96 6.28 4.92 12 10 8

E r

0.

Avg Plan Exposure (GVM~d1SI.

0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 7.0

Exelon Nuclear - Nuclear Fuels 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 EXELON-COLR-P2C1 5 Page 11, Rev. 0 1200-1 1

  • THS FUEJ IS FFFRM:TO BY M"__.

T

-N CAL SPIEMRCA'1'ION 32.1 floo 4.00 10,0 2a0 3ao

40.

Average PlaW Exposure GWI*ST 5WO 7ao MAPLHGR (kWtft) 9.84 9.90 9.99 10.08 10.18 10.29 10.39 10.50 10.61 Avg Plan Exposure (Gwd*ll*SI 8.0 9.0 10.0 11.0 12.0 13.0 14.0 15.0 17.0 MAPLHGR 10.72 10.84 10.95 11.07 11.10 11.10 11.10 11.08 11.04 Avg Plan Exposure (GwdLSIý 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 57.78 MAPLHGR (kWltM 10.90 10.54 10.08 9.55 9.03 8.50 7.96 6.32 4.92 E

C,

1

0.

4 Q000 aC0 4

.4

  • 1 Avg Plan Exposure (niwdLS'r 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 7.0

,"~UU

Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2CI5 Page 12, Rev. 0 FIGURE 5 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE 0.0 10.0 20.0 30.0 40.0 50.0 Average Planar Exposure, GWd/ST FUEL TYPE GE1 4-PI ODNAB416-1 5GZ-1 DOT-1 50-T MAPLHGR (kW/ft) 9.67 9.77 9.88 9.97 10.06 10.16 10.26 10.36 10.47 Avg Plan Exposure 8.0 9.0 10.0 11.0 12.0 13.0 14.0 15.0 17.0 MAPLHGR 10.58 10.69 10.81 10.92 10.91 10.88 10.85 10.82 10.74 Avg Plan Exposure 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 56.28 MAPLHGR 10.55 10.16 9.73 9.29 8.83 8.33 7.79 5.50 4.86 12 10 E

3 C,

-J

0.

4 60.0 Avg Plan Exposure (G&wdlSr 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 7.0

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

_1 8

e-j CL

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

-Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2CI 5 Page 14, Rev. 0 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 K

MA~t~HG(650.6)=MFACpMPU1sd F4~~r PJ~O/:No~hemlus mvolrngRqie

< 60% lRow (25,0.58,4, (30,0.600)

V (30,0.568)

(25>00F32w 600%Flow 20 25 30 35 40 45 50 55 NW orrs specified For 25% < P< P(Bypass):

(P(Bypass) = 30*%f or PBAPS Unds 2 & 3)

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

MAPFAC(p) = 0.568 + 0.00720 - (P-30) For Flow > 60%

For 30% < P < 65%:

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

For 65% <P< 85%:

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

For 85% <P MAPFAC(p)=1.000 60 65 70 75 80 85 90 95 100 Power (% Rated) 1.0 0.9 0.8-

a.

U LL

0.

1

U, -a IU, a

0.

0.7 0.6 0.5.

0.4

03.

A 15

  • xelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2C1 5 Page 15, Rev. 0 FIGURE 8 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 AND MAX 90 OF FWTR (95,1.000)

(100.1.

(85,0.930)

(30,0.700)

MAPLHGR(p) = MAPFAC(P) -MAPLHGR(std)

ForP 5%:No m...iit

  • ororn

,-iequlru

/i 60%/= Flow (30,0.572)

(25,06107)

(30,0.460)

(25,0 21 60% Flow No limits specified For 25% et P < P(Bypass):

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

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

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

For 30%/ P <85%:

MAPFAC(p) = 0930 + 000418 (P-85)

For 85%

P < 95%/6:

MAPFAC(p) = 1.000 + 0.0070 (P-95)

For 95% 4 P:

MAPFAC(p) = 1.000

)00) 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

I1.

1.0 0.9 0.8-0.7 S0.6 0.5 0 I.

0.4 0.3-0.2 4

4

Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2C1 5 Page 16, Rev. 0 FIGURE 9 FLOW-DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 VALID FOR TWO LOOP RECIRC FLOW 10 20 1.1 1.0 0.9 0.8 It.

0.

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

.Exelon Nuclear - Nuclear Fuels P2Cl 5 Core Operating Limits Report EXELON-COLR-P2C1 5 Page 17, Rev. 0 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 1i+

0.9 t 0.8 +

C 0

II a.

0.7 +

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

MAPLHGR(F) = MAPFAC(F) - MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Limits MAPFAC(F) = (Af

  • WT/ 100 + Bf), OR

= 0.73; whichever is lower WT = % Rated Core Flow Af = 0.6682, Bf = 0.5055 0.73 110

Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2CI 5 Page 18, Rev. 0 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 1C=

0 Option A 1r= 1 Option B

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

Two Loop BOC to EOR -2000 1.33 1.36 1.37 1.40 1.38 1.49 Operation MWd/ST EOR - 2000 MWd/ST to 1.37 1.40 1.41 1.44 1.42 1.59 EOC Single Loop BOC to EOR -2000 1.38(3) 1.38 1.39 1.42 1.40 1.51 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 Nuclear - Nuclear Fuels EXELON-COLR-P2CI 5 "P2C1 5 Core Operating Limits Report Page 19, Rev. 0 FIGURE 11 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 AND MAX 90 OF FWTR 4.0' 3.8 Operating Umrt MCPR (P) = Kp

  • Operating Unit MCPR (100) 3.6 For P< 25%: No Thermal Umits Monitoring Requred No limits specifWe 3.4 For 25% c P < P(Bypass):

(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 S2.6 252.50)

(30 2.55) 2.4 (30,2.40) 0 2.2

-.c 60% Flow 2.0 1.8 "X 1.6 2

C.

(30,1.340),

-1.4

".5 (65,1.131)

S1.2

1 1

1.0 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

  • Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2CI 5 Page 20, Rev. 0 FIGURE 12 POWER-DEPENDENT MCPR LIMIT, OLMCPR(p), AND MULTIPLIERS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2, 3.3.4.2 and 3.7.6 VALID FOR 3 OR MORE TBVOOS OR RPTOOS AND MAX 90 OF FWTR 0-0 0

0

c.

0

0.
0.

S 4.0 3.8 3.6 3.4

25. 3.R5) 32
  • 3.0 2.8 2.6 2.4 2.2 2.0 1.8 1.6 1.4 1.2 1.0 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Operating Umit MCPR (P). Kp

  • Operating Limit MCPR (100)

For P< 25%" No Thermal Limits Monitoring Required No limits specified For 25% c P < P(Bypass)"

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

OLMCPR(P) = 2.75 + 0.10 D (30-P) For Flow 4 60%

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

For3O%

P-P<65%" K(P)-1.131 ÷000597(65-P)

For 65% c P: K(p) = 1.000 + 0.00375 (100- P)

>60% Flow (30, 2.75)

S60%/. Flow

(30.1.340)

(65,1.131)

(100,1.0)L

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

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

Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2C1 5 Page 22, Rev. 0 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 (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).

ANALYTICAL ALLOWABLE MCPR FUNCTION

.LIMITI."

VALUE"'*

LIMIT Low Power Range - Upscale

<5123.0%

__121.2%

< 1.70(2)

(Low Trip Setpoint)

< 1.40 (3' Intermediate Power Range - Upscale

<5118.0%

_<116.2%

< 1.70 (2)

(Intermediate Trip Setpoint)

< 1.40 (3)

High Power Range - Upscale

_< 113.2%

<111.4%

< 1.70 (2)

(High Trip Setpoint)

< 1.40 (

Inop N/A N/A

< 1.70 (2)

< 1.40 (3)

.Exelon Nuclear - Nuclear Fuels P2CI 5 Core Operating Limits Report EXELON-COLR-P2CI 5 Page 23, Rev. 0 TABLEN A

DESIGN LINEAR HEAT GENERATION RATE (LHGR) LIMITS U.L.L_.TYE GEl3 GE14 LU.GULAII 14.4 kW/ft 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 Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2C 15 Page 24, Rev. 0 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

ýExelon Nuclear - Nuclear Fuels EXELON-COLR-P2C1 5 P2C15 Core Operating Limits Report Page 25, Rev. 0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION 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 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.

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

As a result of analyses documented in Reference (14), a 4% penalty has been applied to the MCPR ARTS curves and a 7% penalty has been applied to the MAPLHGR ARTS curves to ensure that sufficient thermal margin exists during anticipated operational occurrences while in AFTO.

MAPI Hr.R I IMITR The ARTS-based MAPLHGR power-dependent multipliers (MAPFAC(P)) for asymmetric feedwater temperature operation are provided in Appendix A, Figures 14 and 15. Figure 14 is valid for seven or more (of nine) Turbine Bypass Valves (TBVs) In-Service and Recirculation Pump Trip (RPT) In Service, maximum 90 OF FWTR, with a maximum temperature differential of W5O F between the two feedwater sparger lines. Figure 15 is valid for three or more (of nine) TBVs Out-of-Service (OOS) or RPTOOS, maximum 90 OF FWTR, with a maximum temperature differential of 550 F between the two feedwater sparger lines. The flow-dependent multipliers (MAPFAC(F)) for AFTO are provided in Appendix A, Figures 16 and 17 as a function of the number of recirculation loops in operation only.

The SLO MAPLHGR multiplier (0.73) is applied, with a 7% penalty, through MAPFAC(F) as shown in Figure 17. MAPFAC(F) is clamped at 0.679 starting at 33.6% of rated core flow to ensure peak clad temperatures are maintained within the limits of the cycle-specific LOCA analysis for single recirculation loop and asymmetric feedwater temperature operation. The power-and flow-dependent MAPLHGR multipliers were obtained from References (1), (4), (6) and (7) and were adjusted with a 7% penalty as per Reference (14).

MCPR..MITS The ARTS-based power-dependent MCPR limits, OLMCPR(P), for use in Technical Specification 3.2.2 during asymmetric feedwater temperature operation are provided in Appendix A, Figures 18 and 19. Figure 18 is valid for seven or more (of nine) Turbine Bypass Valves (TBVs) In-Service and Recirculation Pump Trip (RPT) In-Service, maximum 90 OF FWTR, with a maximum temperature differential of 550 F between the two feedwater sparger lines. Figure 19 is valid for three or more (of nine) TBVs Out-of-Service (OOS) or RPTOOS, maximum 90 OF FWTR, with a maximum temperature differential of 550 F between the two feedwater sparger lines. The flow-dependent MCPR limits, OLMCPR(F), for AFTO are provided in Appendix A, Figure 20. Figure 20 is valid for all operating conditions with AFTO. The power-and flow-dependent OLMCPR curves were obtained from References (1), (4), (6) and (7) and were adjusted with a 4% penalty as per Reference (14).

  • Exelon Nuclear - Nuclear Fuels P2CI 5 Core Operating Limits Report EXELON-COLR-P2CI5 Page 26, Rev. 0 FIGURE 14 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, MAX 90 °F FWTR, WITH MAX 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 1.1 1.0 0.9 0.8 0.7

0.

CL 0.6 0.5*

0.4 0.3 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

(85,0.930)

(100,0 930)

'APLHGR(p)

MAPFAC(P)

MAPUGR(std)

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

For 25% < P < P(Bypass).

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

MAPFAC(p) - 0.558 + 0 00300° (P-30) For Flow

< 60%

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

For 30%

< P < 65%:

MAPFAC(p) = 0 893 + 0.0056 (P-65)

For 65%

<P <85%:

MAPFAC(p) =0930 + 00019 (P-85)

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

> 60% Flow 02

,Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2C1 5 Page 27, Rev. 0 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 0.9 0.8.

U

0.
1.

cE 0

0.

0.71 0.6 0.5-0.4 0.3

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

(95,0.930)

(85,o.865) Z (30,0 651)

MMAPLHGR(p) = MAPFAC(p)

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

_s P < P(Bypass):

(30,0.532)

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

MAPFAC(p) = 0 532 + 0.01200 (P-30) For Flow

< 60%

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

(25,0,172)

(.7 (30,0428)

For 300

< P < 85%" MAPFAC(p) = 0.865 + 0.00389 (P-85)

Sj For 85%

< P < 95%:

MAPFAC(p) = 0.930 + 0.00650 (P-95)

(25,0 *92).

For 95%

< P:

MAPFAC(p) = 0.930

> 60r/6 Flow 0.2

Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2C1 5 Page 28, Rev. 0 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) 0.2+

0.1 t'A 4'

  • I 0.930 0.93C 0.0 MAPLHGR(F) = MAPFAC(F)
  • MAPLHGR(std) 0.532 For Two Loop Operation, > 70% WT I

I I

I I

I 10 20 30 40 50 60 70 80 90 100 CORE FLOW (% RATED) 110 1.0 0.9 0.8 0.7 0.6 IL L< 0.5 at.

0.4 0.3 MAPFAC(F) = The Minimum of EITHER 0.930 OR {0.0250 x (WT - 70)/10 + 0.90501 For Two Loop Operation, < 70% WT MAPFAC(F) = {0.6217 x (WT/100)+ 0.4701)

WT= % Rated Core Flow

.Exelon Nuclear - Nuclear Fuels P2C15 Core Operating Limits Report EXELON-COLR-P2C1 5 Page 29, Rev. 0 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 0.6 +

"< 0.5 0,I 0.4 +

0.3-0.2t 0.1

-nI 0.679 0.657 0O.532 0.679 0.0 10 20 30 40 50 60 70 CORE FLOW (% RATED) 80 90 100 MAPLHGR(F) = MAPFAC(F)

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

where, WT = % Rated Core Flow Af = 0.6217, Bf = 0.4701 110 I

Exelon Nuclear - Nuclear Fuels P2CI 5 Core Operating Limits Report EXELON-COLR-P2CI 5 Page 30, Rev. 0 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

2.8 t

> 60% Flow Y42.65 2.60:

2.50 4 60% Flow 1

.39 OPERATING UMIT MCPR(P)

Kp

  • OPERATING LIMIT MCPR(100)

FOR P<25%: NO THERMAL LIMITS MONITORING REQUIRED NO LIMITS SPECIFIED FOR 25% e. P < 30%:

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

FOR 30% ýa P <65%:

Kp= 1.176 + 0 00623 * (65% -P)

FOR 65% e. P:

Kp= 1.040 + 0.00389 * ( 100% - P)

.4 I

I 0

10 20 30 40 50 60 Power (% Rated) 70 80 90 100 0

v 0

0.

0 2.6 t 2.2-2.0 t 1.8 t 1.6j 0 I-1.4 t 1.2f 1.0 00 I

I T

Exelon Nuclear - Nuclear Fuels P2C1 5 Core Operating Limits Report EXELON-COLR-P2CI 5 Page 31, Rev. 0 FIGURE 19 POWER-DEPENDENT MCPR LIMIT, OLMCPR(p), AND MULTIPLIERS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2,3.3.4.2, and 3.7.6 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 3.6 3.4-

_"40 0

V 0

3.0 "2.8 C)

.J 2.6 0

2.4 2.2 2.0 1.8 1.6

" 1.4 1.2 10A 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated) operating Umit MCPR (P) = Kp *Operating Umit MCPR (100)

For P< 25%: No Thermal Umits Monitonng Required No limits specified (25, 3 P8)

(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%

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

For 30% :S P < 65%:

K(P) = 1.176 + 0.00623 (65 - P)

(30, 2.86)

For 65% <_ P: K(p) 1.04 + 0 00389 (100- P)

(30.1.394)

T (65,1.176)

S(100,1.04) 10v

SExelon Nuclear - Nuclear Fuels P2C15 Core Operating Limits Report EXELON-COLR-P2CI 5 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) 1.901 1.80 1.701 1.601 1.50 1.401 1.30-1.20-1.776 1.595 1.300 1.300

.4' I

0 10 20 30 40 so 60 Core Flow (% Rated) s-Nndb\\cor*pb2\\P2C15_COLR_rO.doc 70 80 90 100 110 2.00 For Two Loop Operation, SLMCPR a 1.12 MCPR(F) = The Maximum of EITHER 1.30 OR ( -0.6016 x (WT/100)+ 1.7756)

WT= % Rated Core Flow U

0 5

I,1v 4

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