ML051120415

Issuance of the Core Operating Limits Report for Reload 14, Cycle 15, Revision 1

ML051120415
Person / Time
Site:	Peach Bottom
Issue date:	04/21/2005
From:	Cowan P Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML051120415 (32)

Text

Exelon Nuclear www.exelonrorp.com TS 5.6.5.d April 21,2005 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Peach Bottom Atomic Power Station, Unit 3 Facility Operating License No. DPR- 56 NRC Docket No. 50-278

Subject:

Issuance of the Core Operating Limits Report for Reload 14, Cycle 15, Revision 1

Dear SirlMadam:

Enclosed is a copy of the Core Operating Limits Report (COLR) for Peach Bottom Atomic Power Station (PBAPS), Unit 3, Reload 14, Cycle 15, Revision 1. Revision 1 of this report is the result of upgrading the core monitoring system, and incorporation of the Oscillation Power Range Monitoring (OPRM) set points.

This COLR is being submitted to the NRC in accordance with PBAPS, Unit 3 Technical Specifications (TS) Section 5.6.5.d.

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

Very truly yours, Pamela B. Cowan Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC Enclosure cc: S. J. Collins, Administrator, Region I , USNRC (w/Enclosure)

F. L. Bower, USNRC Senior Resident Inspector, PBAPS (w/Enclosure)

G. F. Wunder, Project Manager, USNRC (wlEnclosure)

Exefon Nuclear Nuclear Fuels DOC ID: CQLR Peach Bottom 3 P3C15 Core Operatin$ Limits Report Page 1, Rev. 1 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 3 RELOAD 14$CYCLE I 5 REVISION 1 (This CQLR revision is a re-write)

Prepared By: Date:

4 Reviewed By: Date:

Approved By: Date: 3/?t / 0 S-

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operatins Limits Report Page 2, Rev.

Revision 1

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 3, Rev.

AND SuNIwtPIFly This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 3 Cycle 15 (Reload 14):

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 Turbine Bypass Valve Parameters Rod Block Monitor (RBM) Analytical Limits, Allowable Values and MCPR Limits EOC Recirculation Pump Trip (EOC-RPT) Parameters 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 the means for calculating the Operating Limit MCPR, LHGR, and MAPLHGR thermal limits for the following conditions:

All points in the operating region of the power/flow map including Maximum Extended Load Line Limit (MELLL) down to 82.9% of rated core flow during full 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 55" F temperature reduction Final Feedwater Temperature Reduction (FWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) to 90" F temperature reduction Asymmetric Feedwater Temperature Operation (AFTO) - Appendix A The Allowable Values, documented in Reference (8), 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.

Also note that the following description of MAPLHGR, LHGR and MCPR limits pertain to NQN -

AFTO. A separate description of AFTO limits and their associated ARTS figures are located in Appendix A.

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 4, Rev. 1 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 (1) 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 3 Cycle 15.

The MAPLHGR limits (kW/ft) obtained from the emergency core cooling system analysis are provided in Figures 1 and 2. The MAPLHGR limits comprise a given fuel type as a function of average planar exposure. The MAPLHGR figure is 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 (2) and (16) and the process computer databank. The SLO MAPLHGR multiplier (0.73) is applied as shown in Table 4. This value is based on the limiting GE13 and GE14 fuel product line. The SLO MAPLHGR multiplier is clamped at 0.73 for any core flow to ensure peak clad temperatures are maintained within the limits of the cycle-specific LOCA analysis for single recirculation loop operation. The MAPLHGR SLO multiplier was obtained from Reference (2).

AFTO parameters are addressed in Appendix A.

R HFAT G F N F R A W RATFS 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 peak pellet exposure are provided in Reference (16). The bases for the LHGR values are documented in Reference (16).

The ARTS-based LHGR power-dependent multipliers (LHGRFAC(P)) are provided in Figures 3 and 4. Figure 3 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 90" F for FWTR operation. Figure 4 is valid for three or more (of nine) TBVs Out-of-Service (00s)or RPTOOS with a maximum FWTR of 90" F. The flow-dependent multipliers (LHGRFAC(F)) are provided in Figures 5 and 6 as a function of the number of recirculation loops in operation only.

The SLO LHGR multiplier (0.73) is applied through LHGRFAC(F) as shown in Figure 6. The power- and flow-dependent LHGR multipliers were obtained from References (4, 8, 9, 11 and 20).

AFTO parameters are addressed in Appendix A.

v 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 (2). For Single Loop Operation with Turbine Bypass Valve and Recirculation Pump Trip in-service (Option 6) 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 (15). This OLMCPR increase is necessary to prevent violating the Reference (15) 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 (1).

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 6) and 1.O (Tau Option A).

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 5, Rev.

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 The OLMCPR values are documented in Reference (2) 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 7 and 8. Figure 7 is valid for seven or more (of nine) Turbine Bypass Valves (TBVs) In-Serviceand Recirculation Pump Trip (RPT) In-Serviceand a maximum temperature reduction of 90 OFfor FWTR operation. Figure 8 is valid for three or more (of nine)

TBVs Out-of-Service (00s)or RPTOOS with a maximum FWTR of 90 OF. The flow-dependent MCPR limits, OLMCPR(F), are provided in Figure 9. Figure 9 is valid for all operating conditions with symmetric feedwater temperature operation. OLMCPR(P, F) curves were obtained from References (4, 9 and 11). AFT0 parameters are addressed in Appendix A.

The Oscillation Power Range Monitor (OPRM) Period Based Detection Algorithm (PBDA) Trip Settings are based, in part, on the cycle specific OLMCPR and the ARTS-based power dependent MCPR limits [K(p) multiplier] (see OPRM discussion below).

DVFRAl I GOVF-PR AND I HGRLMUs 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. At any given power/flow (P/F) state, all four limits are to be determined: LHGRFAC(P), LHGRFAC(F), OLMCPR(P), and OLMCPR(F) from Figures 3 through 17, inclusive. The most limiting MCPR and the most limiting LHGR [maximum of OLMCPR(P) and OLMCPR(F) and minimum of LHGRFAC(P) and LHGRFAC(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 (2). Rated LHGR values are obtained from the bundle-specific thermal-mechanical analysis. Supporting documentation for the ARTS-based limits is provided in References (2, 8, 9, 11 and 20).

RI SFTP-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 (4) with supporting documentation in References (2) and (12).

S F A M R Y P M s SYS-tEM nPF-The operabilitv requirements for the steam bvpass svstem are aoverned 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 4 and 8 or Fiaures 11 and 15).

The minimum number of bvpass valves to maintain svstem ooerabilitv is provided per References (2). (5) and (6) and Table 5. Table 5 also includes other Turbine Bvpass Valve parameters.

Due to the GE Nuclear Energy (GENE) issued 10 CFR Part 21 Transfer of Information SCO4-15 Turbine Control System Impact in Transient Analyses and GE-NE-0000-0034-7701-RO, Exelon Power Load Unbalance (PLU) Evaluation, all (9 of 9) Turbine Bypass Valves are required to be operable between 30% and 45% Core Thermal Power until further analysis is performed per IR 269546.

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 6, Rev.

FOG -R F PIIMP TRIP (EW-RPq OPERARll ITY If the EOC-RPT is inoperable, then the OLMCPR (Table I), LHGRFAC(P) (Figure 4), and OLMCPR(P) (Figure 8) values for EOC Recirculation Pump Trip Out-of-Service (RPTOOS), must be used. Appendix A Figures 11 and 15 contain LHGRFAC(P) and OLMCPR(P) for RPTOOS and AFTO.

The measured EOC-RPT Response Times as referenced in Technical Specifications Section 3.3.4.2 and as defined in Technical Specifications Section 1.I are:

5 0.145 seconds for TCV Fast Closure Trip ( i.e. Generator Load Rejection) 5 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 (10) provides the basis for the RPT response time.

NT T R V O W RPTQaSI Cycle 15 is not licensed for TBVOOS and RPTOOS to occur concurrently. Therefore, concurrent TBVOOS and RPTOOS is an unanalyzed condition.

The Cycle 15 OPRM Period Based Detection Algorithm (PBDA) Trip Settings are provided in Table

6. These values are based on the cycle specific analysis documented in Reference 18. The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system (Reference 19). The OPRM Growth Rate Algorithm (GRA) and Amplitude Based Algorithm (ABA) trip settings can be found in the Power Range Neutron Monitoring Configuration Control Documents (SPID's) G-080-VC-174through 177 (Unit-3).

Any change to the OLMCPR value and/or ARTS-based power dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA Trip Settings.

The OPRM PBDA Trip Settings are applicable when the OPRM system is declared operable, and the associated Technical Specifications (TS Table 3.3.1 .I -1, Item 2.f) are implemented.

RI=_FERENCES

1) "Technical Specifications for Peach Bottom Atomic Power Station Unit 3",Docket No. 50-278, Appendix A to License No. DPR-56.

2) "Supplemental Reload Licensing Report for Peach Bottom Atomic Power Station Unit 3, Reload 14, Cycle 15", GNF Document No. 0000-0019-2633-SRLR, Revision 0, August 2003.

3) "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-14, June 2000; and NEDE-2401I-P-A-14-US, June 2000.

4) "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.

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 7, Rev.

5.) Letter from R. M. Butrovich to H. J. Diamond, Peach Bottom-2 Cycle 11 Turbine Bypass Valve Capacity Variation from Design Basis, January 9, 1995.

6) Letter from G. V. Kumar to G. C. Storey, PBAPS Evaluation of Turbine Bypass Surveillance Requirements, January 19, 1995.

7) PECO Energy Calc. PM-0875, GE NSSS Setpoints Required to Support Power Rerate.

8) Peach Bottom Atomic Power Station Evaluation for Extended Final Feedwater Temperature Reduction of 90 F, NEDC-32707P, Supplement 1, May 1998.

9) ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station, NEDC-32847P, June 1998.

10) PECO Calculation PE-0173, Determination of Total Time Required to Initiate the Trip Signal to the EOC-RPT Circuit Breaker.

11) Peach Bottom Atomic Power Station Units 2 and 3 Plant and Cycle independent ARTS Thermal Limits Analysis, NEDC - 32162P, Supplement 1, Revision 0, August 2001.

12) PECO Calculation PE-0251, Revision 1, Power Range Neutron Monitoring System Setpoint Calculations, Peach Bottom Atomic Power Station Units 2 and 3 .

13) Safety Review for Peach Bottom Atomic Power Station Units 2 and 3 Asymmetric Feedwater Temperature Operation, NEDC-32691P, Revision 0, May 1997.

14) ECR 02-00478, Asymmetric Feedwater Operation Implementation

15) GE14 Fuel Design Cycle-Independent Analyses for Peach Bottom Atomic Power Station Units 2 & 3, GENE L12-00880-00-01P, September 2000

16) Fuel Bundle Information Report for Peach Bottom 3 Reload 14 Cycle 15, GNF Document No. 0000-0019-2633-FIBR, Revision 0, August 2003

17) CR 00171805, AFT0 ARTS thermal limit penalties not applied above 100% CTP

18) Peach Bottom 3 Cycle 15 Option Ill Stability Analysis, GENE-0000-0034-3175-R0, January 2005

19) Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, NEDO-32465-A, August 1996.

20) PANACll Offrated Limits Monitoring for Peach Bottom 3 Cycle 15, GENE-0000-0016-5508-RO, February 2005.

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 8, Rev.

FIGURE 1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGEPLANAREXPOSURE GE14 FUEL TYPES 14.00 12.00

! I THIS FIGURE IS REFERRED TO BY TECHNICAL SEClFlCATlON 3.2.1 1

I 10.00 F

2 2-3 8.00 K

(3 3n 6.00 a

I 4.00 2.00 0.00 0.00 10.00 20.00 30.00 40.00 50.00 60.00 70.00 Average Planar Exposure, GWd/ST Avg Plan Exposure MAPLHGR IGWdIST1 Ikwlftz 0.0 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 9 , Rev. 1 FIGURE 2 M ~ I ~ AVERAGE U M PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGEPLANAREXPOSURE GE13 FUEL TYPES 14.00 12.00 TECHNICAL SEClFlCATlON 3.2.1 10.00 F

E E

8.00 17 0:

0 3 6.00 n

a I

4.00 2.00 0.00 0.00 10,oo 20.00 30.00 40.00 50.00 60.00 70.00 Average Planar Exposure, GWcUST Avg Plan Exposure MAPLHGR IGWdIST1 0.0 13.42 24.39 13.42 32.66 12.70 56.70 9.00 63.50 6.40

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 10, Rev.

FIGURE 3 POWER-DEPENDENT LHGR MULTIPLIER, LHGRFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 VALID FOR 7 OR MORE TBVS IN-SERVICE, RPT IN-SERVICE AND MAX 90 OF FWTR (Symmetric Feedwater Heating) 1.1 (85,l .OOO) (100,l .oc 1.o (65,0960) 0.9 0.8 (3

// LHGR(p) = LHGFFAC(p) X LHGR(std) \

For P < 25%: No Thermal Lit-& Monitoring Required No lirrits specified 0.7 For 25% 5 P c: qBypass):

c-r (qBypass) = 30% for PBAPS Units 2 & 3) 8 LHGRFAC(p) = 0.60 + 0.00320 x (P-30) For flow 5 60%

?i LHGRFAC(p) = 0.568 + 0.00720 x (P-30) For flow > 60%

6 0.6 J

/ (30,0568)

For 30% 5 P < 65%: LHGWAC(p) = 0.960 + 0.006 x (P-65)

For 65% 5 P < 85%: LHGRFAC(p) = 1.000 + 0.002 x (P-85) 0.5 For 85% 5 I? LHGFFAC(p) = 1.000

>6O%%w 0.4 0.3 0.2 I , , ,

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

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 11, Rev.

FIGURE 4 POWER-DEPENDENT LHGR MULTIPLIER, LHGRFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3,3.3.4.2 and 3.7.6 VALID FOR 3 OR MORE TBVOOS OR RPTOOS AND MAX 90 O F FWTR (Symmetric Feedwater Heating) 1.1 (95,l.OOO) 1 .o 0.9 0.8 0.7 LHGR(p) = LHGRFAC(p) x LHGR(std)

Y c 60% FIOW h

n For PC 25% No Thermal Limits Monitoring Required zi No limits specified dK 0.6 -

u For 25% f;P c P(8ypass) 4 (P(f3ypass) = 30% for PBAPS Units 2 & 3)

LHGRFAC(p) = 0 572 + 0 01300 x (P-30) For Flow 5 60%

0.5 LHGRFAC(p) = 0 460 + 0 00780 x (P-30) For Flow > 60%

For 30% 5 P < 85% LHGRFAC(p) = 0 930 + 0 00418 x (P-85)

For 85% 5 P c 95% LHGRFAC(p) = 1 000 + 0 0070 x (P-95) 0.4

' > 60% Flow For 95% 5 P LHGRFAC(p) = 1 000 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 DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 12, Rev.

FIGURE 5 FLOW DEPENDENT LHGR MULTIPLIER LHGRFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 VALID FOR TWO LOOP RECIRC FLOW (Symmetric Feedwater Heating)

I I I LHGRstd = Standard LHGR Limits For Two Loop Operation, > 70/0 WT LHGRFAC(F) = {0.0268 X (WT - 70)/10 + 0.9732}, OR

= 1.0; whichew is lower For Two Loop Operation, 5 70/0 WT LHGRFAC(F) = (0.6682 x (Wc/lOO)+ 0.5055)

I I 0.4 i d + I J

I 1

I II l i d 10 20 30 40 50 60 70 80 90 100 110 CORE FLOW (10RATED)

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 13, Rev. 9 FIGURE 6 FLOW DEPENDENT LHGR MULTIPLIER LHGRFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 AND 3.4.1 VALID FOR SINGLE LOOP RECIRC FLOW (Symmetric Feedwater Heating) 1.I 1 'LHGR(F) = LHGRFAC(F) x LHGRstd ILHGRstd = Standard LHGR Limits

/LHGRFAC(F) = (Af x WT/ 100 + Bf), OR 1 = 0.73; whichever is lower 0.9 1'WT= % Rated Core Flow 1Af = 0.6682, Bf = 0.5055 0.8 L

0" 3K 0.73 L3 0.7 0.6 0.572 0.5 0.4 10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 14, Rev.

OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR)

Applicable to all fuel types Use in conjunction with Figures 7, 8, 9, 14, 15, 16, and 17 These Tables are referred t o by Technical Specification 3.2.2, 3.4.1 and 3.7.6 TBV in Service and TBV out of Service RPT 00s RPT in Service (3 or more TBVOOS:

Option B Option A Option B Option A Option B Option A 1; = 0 (') 1;=1 (1) 7-0 11) 1; =: 1 '~

TWOLOOP BOC to EOR -2000 I .32 1.35 I .36 I .39 Operation MWd/ST EOR 2000 MWd/ST to 1.37 1.40 1.42 1.45 1 1 EOC Single Loop Operation ( 2 )

BOC to EOR -2000 MWd/ST 1.38'?' 1.38'3' I

1 -

EOR 2000 MWd/ST to EOC I NOTES:

1) When Tau does not equal 0 or 1, use linear interpolation.

2) For single-Loop operation, the MCPR operating Limit i s 0.02 greater than the two loop value except when the Two Loop Operation MCPR operating limit i s less than 1.36 (consistent with Reference 15).

3) OLMCPR limit set by the Single Loop Operation (SLO) - Recirculation Pump Seizure Analysis.

(Reference 15)

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FIGURE 7 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 VALID FOR TWO LOOP OR SINGLE LOOP RECIRC OPERATION (Symmetric Feedwater Heating) 4.0 3.8 Operating Limit MCPR (P) = Kp x Operating Limit MCPR (loo;\

3.6 For Pe 25%: No Thermal Limits Monitoring Required No limits specified 3.4 For 25% s P c P(Bypass):

(P(Bypass) = 30% for PBAPS Units 2 & 3) 3.2 OLMCPR(p) = 2.40 + 0.02 x (30-P) For Flow 5 60%

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

V 3.0 P For30% cP<65%: K(P)=1.131 +0.00597~(65-P) 8 > 60% Flow For 65% 5 P: K(p) = 1.OOO + 0.00375 x (100- P)

I -

c 60% Flow

,^_ . .^

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

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FIGURE 8 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 VALID FOR TWO LOOP OR SINGLE LOOP RECIRC OPERATION (Symmetric Feedwater Heating) 4.0 3.8 (25, 3.75)

> 60% Flow L e r a t i n g Limit MCPR (P) = Kp x Operating Limit MCPR (100)

\

3.6 For P< 25% No Thermal Limits Monitoring Required

\

3.4 No limits specified (30, 3.25) For 25% 5 P < P(Bypass)

$ 3.2 (P(Bypass) = 30% for PBAPS Units 2 & 3) m nV OLMCPR(p) = 2 75 + 0 10 x (30-P) For Flow 5 60%

L 3.0 OLMCPR(p) = 3 25 + 0 10 x (30-P) For Flow > 60%

P Y

E For 30% 5 P c 65% K(P) = 1 131 + 0 00597 x (65 - P) 2.8 (30, 2.75) 0 For 65% 5 P K(p) = 1 000 + 0 00375 x (100- P) 6E 2.6 2.4 Y

ii:

2.2

-5

.-LL f 2.0 iii b 1.8 ti.

1.6 1.4  : (30,1.340) 1.2 1 .o 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (?? Rated)

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 17, Rev. 1 FIGURE 9 FLOW DEPENDENT MCPR LIMITS, OLMCPR(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 VALID FOR ALL CONDITIONS (Symmetric Feedwater Heating) 2.0(

For Two Loop Operation, SLMCPR -c. 1.12 1.x MCPR(F) = The Maximum of EITHER 1.25 OR { -0.5784 x (WT/~OO)+ 1.7073) 1.8C WT= % Rated Core Flow i .7a n

LL 1.60 U

p!

n U

r:A 1.50 1.40 1.30 1.20 1.10 0 10 20 30 40 50 60 70 80 90 100 110 Core Flow (YORated)

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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 FUNCTION LIMIT() VALUE() LIMIT Low Power Range - Upscale 5 123.0% 5 121.2% < 1.70 (2)

(Low Trip Setpoint) < 1.40 (3)

Intermediate Power Range - Upscale 5 118.0% 5 116.2% < 1.70 (2)

(Intermediate Trip Setpoint) < 1.40 (3) l High Power Range - Upscale 5 I 13.2% 5 111.4% < 1.70 (2)

(High Trip Setpoint) < 1.40 (3) hop N/A NIA < 1.70 (2)

< 1.40 (3)

(I) 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 (see COLR references 2, 4 and 12).

(2) This is the MCPR limit (given THERMAL POWER 2 28.4% and c 90% RTP) below which the RBM is required to be OPERABLE (see COLR references 2 and 4 and TS Table 3.3.2.1-1).

(3) This is the MCPR limit (given THERMAL POWER 2 90% RTP) below which the RBM is required to be OPERABLE (see COLR references 2 and 4 and TS Table 3.3.2.1-1).

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 19, Rev.

JxELEA DESIGN LINEAR HEAT GENERATION RATE(LHGR) LIMITS' GE13 14.4 kW/ft GE14 13.4 kWIft IxRlEA SINGLE LOOP MAPLHGR MULTIPLIER HELJXEE MULTlPLlER GE13 and GE14 0.73 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 Reference (16).

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 20, Rev.

ImLE-5 TURBINE BYPASS VALVE PARAMETERS SYSTFM R F S P W F TI-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 7 I

Due to the GE Nuclear Energy (GENE) issued 10 CFR Part 21 Transfer of Information SCO4-15 Turbine Control System Impact in Transient Analyses and GE-NE-0000-0034-7701-RO, Exelon Power Load Unbalance (PLU) Evaluation, all (9 of 9) Turbine Bypass Valves are required to be operable between 30%

and 45% Core Thermal Power until further analysis is performed per IR 269546.

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 21, Rev.

Oscillation Power Range Monitor (OPRM)

Period Based Detection Algorithm (PBDA) Trip Settings*

Corresponding Maximum n Count Trio Senrna 1.13 15

• The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system. The OPRM Growth Rate Algorithm (GRA) and Amplitude Based Algorithm (ABA) trip settings can be found in the Power Range Neutron Monitoring Configuration Control Documents (SPIDs) G-080-VC-174through 177 (Unit-3).

• The OPRM PBDA Trip Settings are applicable when the OPRM system is declared operable, and the associated Technical Specifications (TS Table 3.3.1 1,Item 2.f) are implemented.

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 22, Rev.

ASYMMETRIC FEEDWATER TEMPERATURE 0PERAT10N 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 heatedstring configuration which results in a specified threshold difference 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 14).

As a result of analyses documented in Reference (13), a 4% penalty has been applied to the MCPR ARTS curves and a 7% penalty has been applied to the LHGR ARTS curves and MAPLHGR to ensure that sufficient thermal margin exists during anticipated operational occurrences while in AFTO.

l9lwuMm The ARTS-based LHGR power-dependent multipliers (LHGRFAC(P)) for asymmetric feedwater temperature operation are provided in Appendix A, Figures 10 and 11. Figure 10 is valid for seven or more (of nine) Turbine Bypass Valves (TBVs) In-Service and Recirculation Pump Trip (RPT) In-Service, maximum 90 OFFWTR, with a maximum temperature differential of 55' F between the two feedwater sparger lines. Figure 11 is valid for three or more (of nine) TBVs Out-of-Service (00s)or RPTOOS, maximum 90 OFFWTR, with a maximum temperature differential of 55' F between the two feedwater sparger lines. The flow-dependent multipliers (LHGRFAC(F)) for AFTO are provided in Appendix A, Figures 12 and 13 as a function of the number of recirculation loops in operation only.

The SLO LHGR multiplier (0.73)is applied, with a 7% penalty, through LHGRFAC(F) as shown in Figure 13. LHGRFAC(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 LHGR multipliers were obtained from References (2, 4, 8 and 9) and were adjusted with a 7%

penalty as per Reference (13).

lbuEuMm 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 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 OFFWTR, with a maximum temperature differential of 55' F between the two feedwater sparger lines. Figure 15 is valid for three or more (of nine) TBVs Out-of-Service (00s)or RPTOOS, maximum 90 OFFWTR, with a maximum temperature differential of 55' F between the two feedwater sparger lines. The flow-dependent MCPR limits, OLMCPR(F), for AFTO are provided in Appendix A, Figures 16 and 17. Figure 16 is valid for all operating conditions with AFTO during the exposure period of BOC to EOR-2000 MWd/ST. Figure 17 is valid for all operating conditions with AFTO during the exposure period of EOR-2000 MWd/ST to EOC. The power- and flow-dependent OLMCPR curves were obtained from References (9) and (1 1) and were adjusted with a 4% penalty as per Reference (13) and (17).

Exelon Nuclear Nuclear Fuels P3C15 Core Operating Limits Report DOC ID: COLR Peach Bottom 3 Page 23, Rev. 1 A 7% penalty is applied to all MAPLHGR limits for all conditions under asymmetric feedwater temperature operation (AFTO) as per Reference (13). The penalty is being applied as a 0.930 multiplier for all conditions, except single-loop operation (SLO), in Table 7. For single-loop operation, the AFTO multiplier is also applied to the MAPLHGR limits. The SLO multiplier (0.73) from Reference (2) is multiplied by the AFTO multiplier (0.93) in Table 7. Therefore, the SLO MAPLHGR multiplier is clamped at 0.679 as shown in Table 8 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.

AFTO MAPLHGR MULTIPLIER (EXCEPT SINGLE LOOP OPERATION)

GE13 and GE14 0.93 TAuEA AFTO SINGLE LOOP MAPLHGR MULTIPLIER lxElJx MULTIPLIER GE13 and GE14 0.679

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 24, Rev.

FIGURE 10 POWER-DEPENDENT LHGR MULTIPLIER, LHGRFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 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) 1.1 1 .o (85,0.930) (100,0.930:

0.9 0.8

/ LHGR(p) = LHGWAC(p) x LHGR(std) 0.7 For P< 25%. No Thermal Limts Monitoring Required No Iirrnts specified For 2 5 O h 5 P < P(Bypass):

h n  :/ (P(f3ypass) = 30% for PBAPS Units 2 & 3) 2U 0.6 6

2 5 , O . p (30,0.558)

LHGRFAC(p) = 0.558 + 0.00300 x (P-30) For flow 5 60%

a LHGRFAqp) = 0.528 + 0.00660 x (P-30) For Flow > 60%

3 0.5 For 30% 5 P < 65%: LHGRFAC(p) = 0.893 + 0.0056 x (P-65)

For 65% 5 P < 85%: LHGRFAC(p) = 0.930 + 0.0019 x (P-85)

For 85% 5 I? LHGRFAQp) = 0.930 0.4 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 DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 25, Rev.

FIGURE 11 POWER-DEPENDENT LHGR MULTIPLIER, LHGRFAC(P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3,3.3.4.2, and 3.7.6 VALID FOR 3 OR MORE TBVOOS OR RPTOOS, MAX 90 O F FWTR, WITH MAX 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 1.1 1.o (95,0.930) 0.9 0.8 0.7 LHGR(p) = LHGRFAqp) x LHGR(std) h n

5 0.6 For P< 25%: No Therrml Limits tvbnitoring Required da No limits specified (3

3 For 25% 5 P < P(Bypass):

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

LHGRFAqp) = 0.532 + 0.01200 x (P-30) For Flow 5 60%

LHGRFAqp) = 0.428 + 0.00720 x (P-30) For flow > 60%

0.4 For 30% 5 P < 85%: LHGRFAqp) = 0.865 + 0.00389 x (P-85)

For 85% 5 P < 95%: LHGRFAqp) = 0.930 + 0.00650 x (P-95) flow 0.3 For 95% 5 P: LHGRFAqp) = 0.930

\ /

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 DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 26, Rev.

FIGURE 12 FLOW-DEPENDENT LHGR MULTIPLIER, LHGRFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 VALID FOR 2 LOOP RECIRC FLOW WITH MAX 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 1.o 0.9 0.8 0.7 0.6 n

L 0

2U 0.5 IFor Two Loop Operation, > 70% W T 1 c3 LHGRFAC(F) = I0.06275x (WT/100)+0.860975) 1[:

-I 0.4 For Two Loop Operation, 2 70% WT LHGRFAC(F) = I0.6217x (WT/IOO)+0.4701)

WT=% Rated Core Flow 0.3 0.2 0.1 0.0 + - 1 1 1 1 1 1

10 20 30 40 50 60 70 80 90 100 110 CORE FLOW (?/o RATED)

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 27, Rev. 1 FIGURE 13 FLOW-DEPENDENT LHGR MULTIPLIER, LHGRFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3 AND 3.4.1 VALID FOR SINGLE LOOP RECIRC FLOW WITH MAX 55 O F TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 1.o 0.9 0.8 0.7 0.679 0.6 0.6 n

8 3& 0.5 (3 LHGR(F) = LHGRFAC(F) x LHGR(std) 3 LHGR(std) = Standard LHGR Limits 0.4 LHGRFAC(F) = MIN(0.679, Af x WT/lOO + Bf);

where, 0.3 W T = % Rated Core Flow Af = 0.621 7, Bf L= 0.4701 0.2 0.1 0.0 10 20 30 40 50 60 70 80 90 100 10 CORE FLOW (% RATED)

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 28, Rev.

FIGURE 14 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)

VALID FOR TWO LOOP OR SINGLE LOOP RECIRC OPERATION 3.0 2.8 2.6

$j V

2.4 OPF31ATING L I W McFR(P) = Kp x OpERATlNG L l W NIcpR(100) 0 c FOR P45% : No THERMAL LIMITS MONITORING REGUIRED No LlNBFS SPECIFIB)

E E

2.2 FOR 25% 5 P < 30%:

-I -

OLMcpR(P) = 2.50+ 0.02X (30% Fj' FOR R O W 560%

0 OLMcpR(P) = 2.65+ 0.04X (30% P)FOR R O W > 60%

~

FOR 30% 5 P < 65% : KP = 1.176 + 0.00623x ( 65% - P) 2.0 h

FOR 65% 5 P: Kp = 1.040 + 0.00389 x ( 100% - P)

B

.--ii 1.8 I c

Q sii 3 1.6 n0 1.4 1.2 1.o 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 29, Rev.

FIGURE 15 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 OF FWTR, WITH MAXIMUM 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO)

VALID FOR TWO LOOP OR SINGLE LOOP RECIRC OPERATION 4.0 3.8 Operating Limit McPR (0 = Kp x Operating Limit McpR (100) \

3.6 For Pc 25%: No Thermal Limits Monitoring Required 3.4 \ No limits specified Cr) aV.

3.2 \

25' 3.38) 9 p (30, 3.38)

Row For 25% 5 P c p(Bypass).

(VBypass) = 30% for PBAPS Units 2 & 3)

OLMcpR(p) = 2.86 + 0.10 x (30-p) For flow 5 60%

OLMcPR(p) 3.38 + 0.10 x (30-p) For Flow > 60%

L 3.0

,o n

$ 2.8

\ (30, 2.86) For 30% ~ P < 6 5 % : K(P) = 1.176+ 0.00623 x (65 - P) 0 For 65% 2 F? K(p) = 1.04 + 0.00389 x (100- P) zi 6 2.6 2.4 n

e 2.2

--5

.-P c

2 2.0 8

a.

b 1.8 1.6

(30,1.394) 1.4 1.2 1.o 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (%Rated)

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 30, Rev.

FIGURE 16 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) [BOC to EOR-2000 MWd/ST]

2.00 1.90 BOC to EOR-2000 MWd/ST For Two Loop Operation, SLMCPR 5 1.12 MCPR(F) = The Maximum of EITHER 1.373 1.80 OR { -0.50987 x (W~/100)+1.7756) 1.70 1.60 E

n 0

5 1.50 1.40 I .30 1.20 1.10 0 10 20 30 40 50 60 70 80 90 100 110 Core Flow (?hRated)

Exelon Nuclear Nuclear Fuels DOC ID: COLR Peach Bottom 3 P3C15 Core Operating Limits Report Page 3 1, Rev.

FIGURE 17 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 M ~ ~ M U 55M OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) [EOR-2000 MWd/ST to EOC]

2.00 I .90 EOR-2000 MWd/ST to EOC For Two Loop Operation, SLMCPR 5 1.12 MCPR(F) = The Maximum of EITHER 1.425 1.80 OR { -0.4443 X (WdlOO)+ 1.7756)

W,=  % Rated Core Flow 1.70 1.60 Y

Q P

0 3

1.50 1.40 1.425 1.425 1.30 1.20 1.10 0 10 20 30 40 50 60 70 80 90 loo 110 Core Flow (% Rated)