ML042680368

Lssuance of the Core Operating Limits Report for Reload 15, Cycle 16, Revision 0

ML042680368
Person / Time
Site:	Peach Bottom
Issue date:	09/23/2004
From:	Gallagher M Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML042680368 (29)

Text

Exelon Nuclear www.exeloncorp.com Nuclear 2 0 0 Exelon Way Kennett Square, PA 19348 TS 5.6.5.d September 23,2004 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 Subject :

lssuanceof the Core Operating Limits Report for Reload 15, Cycle 16, Revision 0

Dear Si r/Madam :

Enclosed is a copy of the Core Operating Limits Report (COLR) for Peach Bottom Atomic Power Station (PBAPS), Unit 2, Reload 15, Cycle 16, Revision 0. Revision0 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 Exelon Generation Company, LLC Enclosure

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report EXELON-COLR-P2C16 Page 1, Rev. 0 CORE OPERATING LIMITS PEACH BOlTOM ATOMIC POWER RELOAD 1 YCLE REV1 S I0 N Prepared By:

Date: ?A$Y Engineer

?I17 1 0 %

Date:

Nf &

Reviewed By:

William P. Gassmann Engineer Approved By:

Randy T. Tropasso Director, BWR Design Branch

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report 1-28 EXELON-COLR-PZC16 Page 2, Rev. 0 evision 0

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report EXELON-COLR-P2C16 Page 3, Rev. 0 This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 2 Cycle 16 (Reload 15):

a Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) a Single Loop Operation (SLO) MAPLHGR multipliers o

Operating Limit Minimum Critical Power Ratio (OLMCPR) a ARTS MCPR thermal limit adjustments and multipliers a

Single Loop Operation (SLO) MCPR adjustment a

Linear Heat Generation Rate (LHGR) 0 ARTS LHGR thermal limit multipliers o

Single Loop Operation (SLO) LHGR multipliers a

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

Turbine Bypass Valve Parameters EOC Recirculation Pump Trip (EOC-RPT) Parameters 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:

a 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 rated thermal power (3514 MWt) operation a

Increased Core Flow (ICF), up to 11 0% of rated core flow 0

End-of-Cycle Power Coastdown to a minimum power level of 40%

a Feedwater Heaters Out of Service (FWHOOS) to 55" 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 90" F temperature reduction maintaining 5 100% load line (Reference 1)

Asymmetric Feedwater Temperature Operation (AFTO) - Appendix A 0

0 The Allowable Values, documented in Reference (l), 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 AFTO. A separate description of AFT0 limits and their associated ARTS figures are located in Appendix A.

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report EXELON-COLR-P2C16 Page 4, Rev. 0 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 (ARTWMELLLA) for Peach Bottom Unit 2 Cycle 16.

The MAPLHGR limits (kW/ft) obtained from the emergency core cooling system analysis are provided in Figure 1. 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 (4) and (5) and the process computer databank. The SLO MAPLHGR multiplier (0.73) is applied as shown in Table 4. This value is based on the 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 (4). AFTO parameters are addressed in Appendix A.

AR HFAT GFNFRqIl(lhljaaUES 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 References (5) and (17). The bases for the LHGR values are documented in Reference (3). The ARTS-based LHGR power-dependent multipliers (LHGRFAC(P)) are provided in Figures 2 and 3. Figure 2 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 3 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 4 and 5 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 5. The power-and flow-dependent LHGR multipliers were obtained from References (l), (6), (7) and (9).

AFTO parameters are addressed in Appendix A.

J!EmuMm 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 retoad analyses in Reference (4). For Single Loop Operation with Turbine Bypass Valve and Recirculation Pump Trip in-service (Option B) from BOC to OR-2300, the OLMCPR is increased to 1.38 to comply with the results of the Single Loop Operation Recirculation Pump Seizure Analysis described in Reference (1 3). This OLMCPR increase is necessary to prevent violating the Reference (1 3) 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 6) and 1.0 (Tau Option A).

Exelon Nuclear - Nuclear Fuek P2C16 Core Operating Limits Report EXELON-COLR-P2C 16 Page 5, Rev. 0 Separate OLMCPR values are presented herein (Table 1) for the following domains:

0 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 0 TBVs In-Service (seven or more in-service) and RPT Out-of-Service, maximum NVTR of 90 OF The OLMCPR values are documented in Reference (4) for all of the fuel designs.

The ARTS-based power-dependent MCPR limits, OLMCPR(P), for use in Technical Specification 3.2.2 are provided in Figures 6 and 7. Figure 6 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 7 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 8. Figure 8 is valid for all operating conditions with symmetric feedwater temperature operation. OLMCPR(P, F) curves were obtained from References (l),

(6),

(7) and (9). AFT0 parameters are addressed in Appendix A.

DVFRA' ' GaYFRIVlblGMCPR AhUllJiGR ' MUIS 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 2 through 15, 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 (4). Rated LHGR values are obtained from the bundle-specific thermal-mechanical analysis. Supporting documentation for the ARTS-based limits is provided in References (l), (4), (7), (8) and (9).

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 (6) with supporting documentation in References (4) and (1 0).

S F A M RYPL\\SSSYSTFM OPERABli 1-w 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 Bwass Valves Out-of-Service (TBVOOS) must be used (Table 1 with Fiaures 3 and 7 or Figures 1 0 and 14).

The minimum number of bvpass valves to maintain svstem operabilitv is seven as per Reference (1 1) and Table 5. Table 5 also includes other Turbine Bypass Valve parameters.

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report EXELON-COLR-P2C16 Page 6, Rev. 0 If the EOC-RPT is inoperable, then the OLMCPR (Table l), LHGRFAC(P) (Figure 3), and OLMCPR(P) (Figure 7) values for EOC Recirculation Pump Trip Out-of-Setvice (RPTOOS), must be used. Appendix A contains LHGRFAC(P) and OLMCPR(P) for RPTOOS with AFT0 conditions.

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 comply with the surveillance requirements in Reference (1 2) and applicable site procedures for TCV Fast Closure Trip (i.e.

Generator Load Drop) and TSV Fast Closure Trip (i.e. Turbine Trip).

A total EOC-RPT system response time acceptance criterion 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.

FNT TRVOQSBEIIP RPT-Cycle 16 is not licensed for TBVOOS and RPTOOS to occur concurrently. Therefore, concurrent TBVOOS and RPTOOS is an unanalyzed condition.

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report EXELON-COLR-PZC 16 Page 7, Rev. 0 1, Peach Bottom Atomic Power Station Evaluation for Extended Final Feedwater Temperature Reduction of 90 F, NEDC-32707PI 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-24011 -P-A-14, June 2000; and NEDE-24011 -P-A-1 4-US, June 2000

4. Supplemental Reload Licensing Report for Peach Bottom 2, Reload 15 Cycle 16, Global Nuclear Fuel Document No. 0000-0025-6977-SRLRI Rev. 0, August 2004

5. Fuel Bundle Information Report for Peach Bottom 2, Reload 15 Cycle 16, Global Nuclear Fuel Document No. 0000-0025-6977-FBI R, Revision 0, August 2004

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-32847PI 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 1 1. Peach Bottom 2 Cycle 16 OPL-3, Global Nuclear Fuels eDRF #OOOO-0024-7901, Suresh Gupta, August 12,2004

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

13. GE14 Fuel Design Cycle-Independent Analyses for Peach Bottom Atomic Power Station Units 2

& 3, GENE Ll2-00880-00-01 P, September 2000 7 4. 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, Asymmetric 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. 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 -01 190 Power Uprate Request for Appendix K Measurement Uncertainty Recapture, May 24,2002

Exelon Nuclear - Nuclear Fuels PZC16 Core Operating Limits Report 4.00 2.00 0.00 FIGURE 1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGEPLANAREXPOSURE FOR ALL FUEL TYPES I

I I

i

~

14.00 12.00 10.00 F

E zi..- 8.00 d

p:

Q 3 6.00 e

U EXELON-COLR-PZC16 Page 8, Rev. 0 Avg Plan Exposure MAPLHGR (GWd/STI Lkwlftz 0.0 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00

Exelon Nuclear - Nuclear Fuels EXELON-COLR-P2C16 P2C16 Core Operating Limits Report Page 9, Rev. 0 FIGURE 2 POW E R-DEPENDENT LHGR MU LTI PLI ER, LHG RFAC( P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPEClFlCATlO VALID FOR 7 OR MORE TBVs IN-SERVICE, RPT IN-SERVICE AND MAX 90' F FWTR 1.1 1.o 0.9 0.8 0.7 n

is a

Q 5 0.6 f

n i?

CI s

f 0.5 LL 0.4 0.3 0.2 (1 00,l.oo (85,1.000)

. /

LHGR(p) = LHGFiFAqp) LHGeStd)

For P< 25%: No lherml L i s Monioring Required No lirrits specified For 25% 5 P<

P(Bypass):

(4Bypass) = 30Y0 for WAPS Units 2 & 3)

LffiRFAC(p) = 0.60 + 0.00320 * (P30)

For Flow LHGRFAqp) = 0.568 + 0.00720 (P30) For RMN > 60%

For 30% 5 Pc 65%: LHGFFAqp) = 0.960 + 0.006 (Pa)

For 65% 5 P c 85%:

LffiFFAqp) = 1.OM) + 0.002 (Pa) 5 60%

For 85% c I?

LffiWAqp) = 1.OM) 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (%Rated)

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report FIGURE 3 POWER-DEPENDENT LHGR MULTIPLIER, LHGRFAC(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 O F NVTR 1.1 1.o 0.9 0.8 0.7 n

ti

zf a 5.- 8 0.6 n

8 E

n c

0 0.4 0.3 0.2 (95,l

.OOO)

Flow

.460)

I

> 60% Flow I

I LHGR(p) = LHGRFAC(P)

• LHGR(6td)

Fa P< 25%: No lllemlal Limits Mdmng Requred No limits spedhed F a 25% c P c P(ByPaSS):

(~(~yp8ss)

= 30% for PBAPS Units 2 L 3)

LHGRFAC(p) = 0.572 + 0.013w * (P-30) F a Fkm c 60%

LHGRFAC(p) = 0.480 + 0.00780 * (P-30) For Fkm =- 60%

For 30% 5 P c 85%.

For 85% 5 P 95%:

LHGRFAC(p) = 0.930 + 0.W418 (P-85)

LHGRFAC(p) I I.ooO + 0.0070 (p-95)

F a 95% 5 P LHGRFAC(P) = I.ooO 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (h Rated)

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report 1.o 0.9 0.8 0.7 0.6 n

5 0.5 0.4 0.3 0.2 0.1 0.0 EXELON-COLR-P2C16 Page I 1, Rev. 0 FIGURE 4 FLOW-DEPENDENT LHGR MULTIPLIER, LHGRFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 VALID FOR TWO LOOP RECIRC FL LHGR(F) = LHGRFAC(F)

• LHGR(Std)

For Two Loop Operation, > 70% WT LHGRFAC(F) = The Minimum of EITHER 1.O OR (0.0268 x (WT - 70)/10 + 0.9732)

For Two Loop Operation, I 70% WT LHGRFAC(F) = I0.6682 x (W~/100)+

0.5055)

WT= ?Ao Rated Core Flow I

I 1

1 1

1 1

1 1

1 1

1 70 20 30 40 50 60 70 80 90 100 110 CORE FLOW (%

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report ELON-COLR-P2C16 Page 12, Rev. 0 FIGURE 5 FLOW-DEPENDENT LHGR MULTIPLIER, LHGRFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 A VALID FOR SINGLE LOOP RECIRC FLOW 1.1 1.1 LHGR(F) = LHGRFAC(F)

• LHGR(std)

LHGR(std) = Standard LHGR Limits 1

LHGRFAC(F) = (Af

• WT / 100 + Bf), OR

= 0.73; whichever is lower 0.9 WT = % Rated Core Flow Af = 0.6682, Bf = 0.5055 0

0.8 Y

K a '

0.7 0.6 0.572 0.5 0.4 10 20 30 40 50 60 70 80 90 100 110 Core Flow ("! Rated) 10 20 30 40 50 60 70 80 90 100 110 Core Flow ("! Rated)

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report TBV in Service and RPT in Service EXELON-COLR-P2C16 Page 13, Rev. 0 T 00s TBV out of Service (3 or more TBVQOS)

OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (

Applicable to all fuel types Use in conjunction with Figures 6, 7, and 8 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 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 1 3).

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

(Reference 1 3)

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report IGURE EXELON-COLR-P2Cl 6 Page 14, Rev. 0 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 M 4.0 3.0 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.8 1.6 1.4 1.2 1.o (25, 2.70) 60%

!5, 2.45)

(30, 2.50)

(30, 2.36)

\\

c 60% flow 30,1340)

Operating Limit MCPR (4 = Kp

• Operating Limit MCFR (1 00)

For Pe 25%: No Therml Limits Monitoring Required No limts specified For 25% 5 Pc VBypass):

(P(Bypass) = 30% for FBAPS h i t s 2 & 3)

OLMcpR(p) =2.36+0.018"(30-p)

For FIOW 5 60%

OLMCPR(p) = 2.50 + 0.04 * (30-4 For Row > 60%

For30% zPc65%: K(P)=1.131 +0.00597(65-p)

For 65% 5 I?

K(p) = 1.000 + 0.00375 (1 00- p) 7 (65,l.I 31) 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (%Rated)

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report EXELON-COLR-PZC16 Page 15, Rev. 0 FIGURE 7 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.

VALID FOR 3 OR MORE TBVOOS OR RPTOOS AND MAX 90 OF R

4.0 3.8 3.6 3.4 3.2 3.0 2.8 g

F)

V n 8 2.6 n

z 8 2.4

.c 2.2 h

Q 3 8 2.0 E

8 n

Q !i 1.8 8

1.6 1.4 1.2 1.a Q (25,3.68)

\\ i k-.

560% Row (30, 2.70)

Operating Linit tvWR (P) = Kp

• Operating Limit tvWR (1 00)

For Pc 25%: No Thermal L i M Monitoring Required No linits specified For 25% 5 Pc p(Bypass):

(p(Bypass) =30%for F%APSLhits2&3)

OLMcpR(p) = 2.70 + 0.098 * (30-P) For Flow 5 60%

OLtvWR(p) = 3.1 9 + 0.098 (30-P) For Row > 60%

For3PA (P<65%:

K(P)=1.131 +0.00597(65-P)

For 65% 5 I?

K(p) = 1.OOO +O.O0375 (100-P)

(30,1340)

(65.1.131) 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-P2C16 P2C16 Core Operating Limits Report Page 16, Rev.

FIGURE FLOW-DEPENDENT MCPR LIMITS, OLMCPR(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2 VALID FOR ALL CONDITIONS 2.00 1.90 1.80 1.70 g 1.60 1.50 1.40 1.30 1.20 i. i a MCPR(F) = The Maximum of EITHER 1.25 OR { -0.5784 x (WT/1 OO)+ 1.7073)

WT= % Rated Core Flow 1.25

1.

loo 110 30 40 50 60 70 80 90 0

10 20 Core Flow ("! Rated)

Exelon Nuclear - Nuclear Fuels EXELON-COLR-P2C16 P2C16 Core Operating Limits Report Page 17, Rev. 0 ROD BLOCK MONITOR ANALYTICAL LIMITS, ALLOWABLE VALUES, AND MCPR LIMITS THIS TABLE IS REFERRED TO BY TECHNICAL SPECIFICATIO~ 3.

Appficabifity:

BOC to EOC I

~

FUNCTION High Power Range - Upscale (High TriD SetDoint) hop (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 2 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 2 90% RTP) below which the RBM i s required to be OPERABLE (References (4) and (6) and TS Table 3.3.2.1-1).

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report EXELON-COLR-P2C16 Page 18, Rev. 0 DESIGN LINEAR HEAT GENERATION RATE (LHGR) LIM~TS' GE14 ElELnE GE14 13.4 kW/ft SINGLE LOOP MAPLHGR MULTIPLI~R

.73 The LHGR limits provided above are the beginning of life (maximum) values. The LHGR limits as a function of peak pellet exposure are provided in References (5) and (17).

1

Exelon Nuclear - Nuclear Fuels P2C 16 Core Operating Limits Report TURBINE BYPASS VALVE P A ~ E T E R S F R Y P W Y S T F M RF-SF T

U EXELON-COLR-P2Cl 6 Page 19, Rev. 0 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 the above delay time) 0.30 sec.

Minimum required number of bypass valves to maintain system operability 7

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report 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 heatedstring 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 LHGR ARTS curves and MAPLHGR to ensure that sufficient thermal margin exists during anticipated operational occurrences while in AFTO.

The ARTS-based LHGR power-dependent multipliers (LHGRFAC(P)) for asymmetric feedwater temperature operation are provided in Appendix A, Figures 9 and 10. Figure 9 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 55' F between the two feedwater sparger lines. Figure 10 is valid for three or more (of nine) TBVs Out-of-Service (00s) or RPTOOS, maximum 90 OF FWTR, 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 1 1 and 12 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 12. LHGRFAC(F) is clamped at 0.679 starting at 33.6% of rated core flow for single recirculation loop and asymmetric feedwater temperature operation. The power-and flow-dependent LHGR multipliers were obtained from References (l), (4), (6) and (7) and were adjusted with a 7%

penalty as per Reference (1 4).

~

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 13 and 14. Figure 13 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 55' F between the two feedwater sparger lines. Figure 14 is valid for three or more (of nine) TBVs Out-of-Service (00s) or RPTOOS, maximum 90 OF FWTR, 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, Figure 15. Figure 15 is valid for all operating conditions with AFTO. The power-and flow-dependent OLMCPR curves were obtained from References (l), (4), (6) and (7) and were adjusted with a 4% penalty as per Reference (14).

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report EXELON-COLR-PZCI 6 Page 21, Rev. 0 A 7% penalty is applied to all MAPLHGR limits for all conditions under asymmetric feedwater temperature operation (AFTO) as per Reference (1 4). The penalty is being applied as a 0.930 multiplier for all conditions, except single-loop operation (SLO), in Table 6. For single-loop operation, the AFTO multiplier is also applied to the MAPLHGR limits. The SLO multiplier (0.73) from Reference (4) is multiplied by the AFTO multiplier (0.93) in Table 6. Therefore, the SLO MAPLHGR multiplier is clamped at 0.679 as shown in Table 7 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)

GE14 0.93 AFT0 SINGLE LOOP MAPLHGR ~ULTIPLIER GE14

Exelon Nuclear - Nuclear Fuels EXELON-COLR-P2C16 P2C16 Core Operating Limits Report Page 22, Rev. 0 FlGUaEs POW E R-D E P EN DENT LH G R MU LTI PLI E R, LHG R FAC( 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 OF FWTR, WITH MAX 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 1.1 1.o 0.9 0.8 0.7 h

P

u. z a

8 3 0.6 P

c 0.5

& s n

0 0.4 0.3 0.2

560% Fbw J

4 (30,0.558) i

>'6O%FIoW For Pc 25%: No Thermal L i d s Monitoring Required No lirrits specified For 25% 5 Pc pI8ypass):

(pIE3ypass) = 30Y0 for WAPS W i 2 & 3)

LHGRFAC(p) = 0.558 + 0.00300 x (P30)

For Fbw 5 60%

LHGRFAC(p) = 0.528 + 0.00660 x (P30)

For Fbw > 60%

For 30% 5 P c 65%:

For 65% 5 P < 85%:

LHGRFAC(p)

= 0.893 + 0.0056 x (P65)

LHGRFAC(p) = 0.930 + 0.0019 x (P85)

For 85% 5 P. LffiRFAC(p) = 0.930 I

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

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report EXELON-COLR-P2C16 Page 23, Rev. 0 POW ER-DEPENDENT LHGR MULTIPLIER, LHG RFAC( P)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1,3.3.4.

VALID FOR 3 OR MORE TBVOOS OR RPTOOS, MAX 90 OF FWTR, WITH MAX 55 OF TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 1.l 1.o 0.9 0.8

- 0.7 U

U U

c7 3 0.6 P

iT 9 -

P c '

0.5 9

n. :

0.4 0.3 0.2 (95,0.930)

(30,O.

<60%Row For P< 25%: No Thermal Lirrits Monitoring Raquired No lirrits specified For 25% 5 P< qBypass):

(RBypass) = 30% for FBAPS M i 2 & 3)

LHGRFAqp) = 0.532 + 0.01200 x (P30)

For Row 5 60%

LHGRFAqp) = 0.428 + 0.00720 x (P30) For Row > 60%

For 30% 5 P c 85%:

LHGRFAqp) = 0.865 + 0.00389 x (P85)

For 85% 5 P < 95%:

LHGRFAqp) = 0.930 + 0.00650 x (P95)

For 95% 5 P: LffiRFAC(p) = 0.930 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-P2C16 P2C16 Core Operating Limits Report Page 24, Rev. 0 FLOW-DEPENDENT LHGR ~ U L T I P L I E ~,

LHGRFAC(F)

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 VALID FOR 2 LOOP RECIRC FLOW WITH MAX 55 O F TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 1.o 0.9 0.8 0.7 0.6 n

k.

0.5 0.4 0.3 0.2 0.1 0.0 0.9:

.905 LHGR(F) = LHGRFAC(F) x LHGR(std) 3.532 For TWO LOOP Operation, > 70% WT LHGRFAC(F) = The Minimum of EITHER 0.930 OR {0.0250 x (WT -70)/10 +.9050)

For TWO LOOP Operation, 5 70% WT LHGRFAC(F) = (0.6217 x (W~/100)+ 0.4701)

WF % Rated Core Flow I

I I

1 1

1 1

1 1

I 1

1 1

1 1

10 20 30 40 50 60 70 80 90 100 110 CORE FLOW ('Yo RATED)

EXELON-COLR-P2C16 age 25, Rev. 0 Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report FLOW-DEPENDENT LHGR MULTIPLIER, LHGRFA THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1 AN

.1 VALID FOR SINGLE LOOP RECIRC FLOW WITH MAX 55 OF TEMPERATURE DIFFERENTIAL 1.o 0.9 0.8 0.7 0.6 n

k 0.5 0.4 0.3 0.2 0.1 0.0 BETWEEN FEEDWATER SPARGER LINES (AFTO) 0.679 0.67!

LHGR(F) = LHGRFAC(F)

• LHGR(std)

LHGR(std) = Standard LHGR Limits LHGRFAC(F) = MIN(0.679, Af*WT/lOO + Bf);

where, WT = % Rated Core Flow Af = 0.6217, Bf = 0.4701 1

10 20 30 40 50 60 70 80 90 100 110

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report EXELON-COLR-P2C16 Page 26, Rev. 0 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) 3.0 2.8 2.6 2.4 (3

V n.

B iz 3

O 2.0 w.. n P 2.2

0. 0 1.8 1.6 h

p 1.4 Y

v f -

n 3 1.2 I

f L

n.

c 0

1.0

> 60% Flo OpBv\\TNG LMm WpR1P) = Kp

• OPERATING LMm MCpR(100)

> 60% Flo OpBv\\TNG LMm WpR1P) = Kp

• OPERATING LMm MCpR(100) 2.45 FOR PQ5% : No THERMAL LlMK h4ONmORM RECIUIRED No LIMITS s m m FOR25%5P<30%:

oLMcpR(p) = 2.45 + 0.02 (30% - F') FOR FLOW 5 60%

= 2.60 + 0.042 * (30% - F') FOR FLOW > 60%

FOR 30% 5P<65% :

FOR 65% 5 P :

Kp = 1.176 +0.00623 * ( 65% - F')

Kp = 1.040 + 0.00389 ( 100% - F')

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

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report XELON-COLR-P2C16 Page 27, Rev. 0 P 0 WE R-D E P E N DENT M C P R LI M IT, 0 LM C P R( P), AND MU LTI P LI E RS THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.2, 3.3.4.2, and 3.7.

VALID FOR 3 OR MORE TBVOOS OR RPTOOS, MAX 90 OF FWTR, WITH MAXIMUM 55 O F TEMPERATURE DIFFERENTIAL BETWEEN FEEDWATER SPARGER LINES (AFTO) 4.0 3.8 3.6 3.4 3.2 3.0 2.8 m

V P

n P

P 2.4 0

iz 0 2.2 f

2.0 1.0 1.6 P

?5 L

0, B 1.c i5 OPERATING LIMIT MCPR(P) = Kp ' OPERATING LMIT MCpR(100)

FOR P<25% : NO THERMAL LMIT MONITORING REOUIRED NO LMrrS SPECIFIED FOR 25% 5 P.z 30%:

OLMCPR(P)=2.81 +0.102'(3O%-P) K)RROWc60%

= 3.32 + 0.102 * (30% - P) FOR FLOW > 60%

FOR30% c P < 65% :

FOR 65%

P :

Kp = 1.176 + 0.00623 * ( 65% - P)

Kp = 1.040 + 0.00389 * ( 100% - P) 40 50 60 70 00 90 100 Power (?h Rated) 0 10 20 30

Exelon Nuclear - Nuclear Fuels P2C16 Core Operating Limits Report EXELON-COLR-P2C16 Page 28, Rev. 0 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 O F TEMPERATURE DIFFERENTIAL B E ~ E E N FEEDWATER SPARGER LINES (AFf'O) 2.00 1.90 1.80 1.70 G: 1.60 iE n

0 s

a 1.50 1.40 1.30 1.20 MCPR(F) = The Maximum of EITHER 1.30 OR { -0.6016 x (WT/lOO)+ 1.7756)

WF % Rated Core Flow 1.300 1.a0 1

1.10 100 110 0

10 20 30 40 50 60 70 80 90 Core Flow ('?? Rated)