ML003767169

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Issuance of the Core Operating Limits Report for Reload 5, Cycle 6, Revision 2
ML003767169
Person / Time
Site: Limerick Constellation icon.png
Issue date: 10/25/2000
From: Hutton J
PECO Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
-RFPFR
Download: ML003767169 (29)
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Nuclear Group Headquarters 200 Exelon Way A Unit of PECO Energy Kennett Square, PA 19348 October 25, 2000 Docket No. 50-353 License No. NPF-85 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D.C. 20555-0001

Subject:

Limerick Generating Station, Unit 2 Issuance of the Core Operating Limits Report for Reload 5, Cycle 6, Revision 2

Dear Sir/Madam:

Enclosed is a copy of the Core Operating Limits Report (COLR) Revision 2 for Limerick Generating Station (LGS) Unit 2, Reload 5, Cycle 6. This COLR provides the cycle-specific parameter limits for: Maximum Average Planar Linear Heat Generation Rate (MAPLHGR);

Minimum Critical Power Ratio (MCPR); ARTS MCPR thermal limit adjustments and multipliers; ARTS MAPLHGR thermal limit multipliers; Rod Block Monitor (RBM) setpoints; MAPLHGR single loop operation (SLO) reduction factor; Linear Heat Generation Rate (LHGR); Turbine Bypass Valve parameters; and Reactor Coolant System Recirculation Flow Upscale Trips. 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 COLR Revision was implemented on October 9, 2000, and is being provided to the NRC in accordance with LGS, Unit 2 Technical Specifications (TS) Section 6.9.1.12.

If you have any questions, please do not hesitate to contact us. Very truly yours, rames A. Hutton irector -Licensing Enclosure cc: (w/encl) H. J. Miller, Administrator, Region 1, USNRC A. L. Burritt, USNRC Senior Resident Inspector, LGS PECO Nuclear, Fuel & Services Division [U L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 1, Rev. 2 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 2 RELOAD 5, CYCLE 6 Prepared By: V/ J. -P. Buc ey Engin r Date: ?/- I Aj Reviewed By: Date: _-_7-7_Approved By: G. F. Ruppert Manager Nuclear Design -BWR Branch Date: -Iqevo PECO Nuclear, Fuel & Services Division I L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 2, Rev. 2 LIST OF EFFECTIVE PAGES Page(s)1-28 Revision 2 PECO Nuclear, Fuel & Services Division PECO-COLR-L2R5 1-L2R5 Core Operating Limits Report Page 3, Rev. 2 INTRODUCTION AND

SUMMARY

This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 2 Cycle 6: "* Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

"* Minimum Critical Power Ratio (MCPR) "* ARTS MCPR thermal limit adjustments and multipliers

"* ARTS MAPLHGR thermal limit multipliers

"* Rod Block Monitor (RBM) setpoints

"* MAPLHGR single loop operation (SLO) reduction factor "* Linear Heat Generation Rate (LHGR) "* Turbine Bypass Valve parameters

  • Reactor Coolant System Recirculation Flow Upscale Trips These values have been determined using NRC-approved methodology, Reference 19, and are established such that all applicable limits of the plant safety analysis are met. This report is submitted in accordance with Technical Specification 6.9.1.9 of Reference
1. Preparation of this report was performed in accordance with PECO Nuclear, Fuel & Services Division Procedure FM-300. The data presented in this report is valid for all points and domains on the operating map, including:

"* Maximum Extended Load Line Limit (MELLL) down to 81% of rated core flow during full power operation

"* Increased Core Flow (ICF) up to 110% of rated core flow "* Feedwater Temperature Reduction (FWTR) up to 105OF during cycle extension operation

"* Feedwater Heater Out of Service (FWHOOS) up to 60OF feedwater temperature reduction at any time during the cycle prior to cycle extension.

Further information on the cycle specific analyses for Limerick 2 Cycle 6 and their associated operating domains is available in Reference

2. Additional information on the inputs used in performing the Limerick 2 Cycle 6 specific analyses are available in References 12 and 21. MAPLHGR LIMITS The limiting MAPLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of average planar exposure is given in Figures 1 through 8. These figures are used when hand calculations are required as specified in Technical Specification 3.2.1. The MAPLHGR limit curves of Figures 1 through 8 were generated from References 3, 4, 5, and 6. For single loop operation, a reduction factor is used which is shown in Table 3 (Reference 13).

PECO Nuclear, Fuel & Services Division PECO-COLR-L2R5 I L2R5 Core Operating Limits Report Page 4, Rev. 2 MCPR LIMITS The MCPR value for use in Technical Specification 3.2.3 for each fuel type is given in Table 1. This table is derived from the Reference 2 analyses and is valid for all Cycle 6 fuel types and operating domains. Information regarding the treatment of these MCPR limits for SLO is also provided.

Bounding MCPR values are also provided for inoperable Recirculation Pump Trip (RPTOOS) or inoperable Steam Bypass System (TBVOOS).

These two options represent the Equipment Out of Service I (Equipment OOS) condition.

Note that in Table 1 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). The cycle exposure which represents "EOR" is given in the latest verified and approved Cycle Management Report. This value can change during the cycle due to changes in operating strategy.

ARTS THERMAL LIMIT ADMINISTRATION ARTS provides for power- and flow-dependent thermal limit adjustments and multipliers which allow for a more reliable administration of the MCPR and MAPLHGR thermal limits. The flow dependent adjustment MCPR(F) is sufficiently generic to apply to I all fuel types and operating domains (Reference 18). However, there are two sets of flow-dependent MAPFAC(F) multipliers for dual-loop and single-loop operation, References 18 and 11, respectively.

In addition, there are also two sets of power dependent MAPLHGR multipliers for with Equipment in Service and with Equipment OOS conditions, References 9 and 7, respectively.

Finally, there are two sets of power-dependent MCPR adjustments and I multipliers for with Equipment in Service and with Equipment OOS conditions, Reference

11. These adjustments and multipliers are shown in Figures 9 through 15. Thermal limit monitoring must be performed with the more limiting MCPR and MAPLHGR limits resulting from the power- and flow-biased calculation.

ROD BLOCK MONITOR SETPOINTS The ARTS RBM provides for power-dependent RBM trips. The trip setpoints/allowable values and applicable RBM signal filter time constant data are shown in Table 2. These values are for use with Technical Specification 3.3.6. The use of the setpoints specified in Table 2 is documented in References 2, 9, 10, and 14.

PECO Nuclear, Fuel & Services Division PECO-COLR-L2R5 L2R5 Core Operating Limits Report Page 5, Rev. 2 LINEAR HEAT GENERATION RATES The maximum LHGR value for each fuel type for use in Technical Specification 3.2.4 is given in Table 4. The LHGR is an exposure dependent value. Due to the proprietary nature of these values only the maximum LHGR for each fuel type is listed in Table 4. The LHGR data is listed in References 3 & 4 (GNF proprietary).

STEAM BYPASS SYSTEM OPERABILITY The operability requirements for the steam bypass system for use in Technical Specifications 3.7.8 and 4.7.8.C are found in I Table 5 (Reference 12). If these requirements cannot be met, the MCPR, MCPR(P) and MAPFAC(P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service (TBVOOS), must be used. RECIRCULATION PUMP TRIP OPERABILITY If the recirculation pump trip is inoperable, then the MCPR, MCPR(P) and MAPFAC(P) limits for Recirculation Pump Trip Out Of Service (RPTOOS), must be used. Further information about the RPTOOS condition is available in Reference

7. RECIRCULATION PUMP MOTOR-GENERATOR (MG) SET SCOOP TUBE STOPS DELETED (see Reference
20) CONTROL ROD BLOCK INSTRUMENTATION REACTOR COOLANT SYSTEM RECIRCULATION FLOW UPSCALE TRIP Technical Specification Limiting Condition for Operation number 3.3.6 requires control rod block instrumentation channels shall be OPERABLE with their trip setpoints consistent with the values shown in the Trip Setpoint column of Technical Specification Table 3.3.6-2. The Reactor Coolant System Recirculation Flow Upscale Trip is a cycle-specific value and as such is found in Table 7 of this COLR. Table 7 lists the Nominal Trip Setpoint and Analytical Value. These setpoints are set high enough to allow full utilization of the enhanced ICF domain up to 110% of rated core flow. Reference 8 provides the current basis for the trip setpoint values used.

PECO Nuclear, Fuel & Services Division PECO-COLR-L2R5 I L2R5 Core Operating Limits Report Page 6, Rev. 2 HIGH EXPOSURE PROGRAM BUNDLES Limerick Unit 2 Cycle 6 is the fourth cycle of irradiation for four Limerick Unit 1 Reload 4 GEl1 fuel bundles. These bundles previously resided in Limerick Unit 1 Cycles 5, 6 and 7. They have spent one year in the Limerick fuel pool and have been inspected prior to being inserted into this cycle. These bundles are part of a joint GE-PECON Lead Test Assembly (LTA) program. This LTA program was implemented in order to obtain fuel bundle data at high exposures (beyond the current GEl1 licensed limit of 70 GWd/MT Peak Pellet Exposure, Reference 17). A PECON IOCFR50.59 Review has been performed for the use of these bundles in a fourth cycle. No Unreviewed Safety Questions were identified.

New MAPLHGR and DESLIM limits, respectively used for calculating MAPRAT and MFLPD, have been determined by the fuel vendor and are shown in Figure 6 and Table 4. See References 2, 3, 15 and 16 for more information on these bundles.

SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (SLMCPR) The Safety Limit Minimum Critical Power Ration (SLMCPR) for Limerick 2 Cycle 6 is 1.12 for Dual Loop Operation and 1.14 for Single Loop Operation.

These values are documented in Reference

2. REFERENCES
1. "Technical Specifications and Bases for Limerick Generating Station Unit 2", Docket No. 50-353, License No. NPF-85. 2. "Supplemental Reload Licensing Report for Limerick Generating Station Unit 2 Reload 5 Cycle 6", Global Nuclear Fuel Document No. Jl1-03480SRLR, Revision 2, September 2000. 3. "Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 2 Reload 5 Cycle 6", Global Nuclear Fuel Document No. Jll-03480MAPL, Revision 2, September 2000. 4. "Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 2 Reload 4 Cycle 5", General Electric Company Document No. 24A5383AA, Rev. 0, January 1997. 5. "Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 2 Reload 3 Cycle 4", General Electric Company Document No. 24A5168AA, Rev. 0, January 1995. 6. "Lattice-Dependent MAPLHGR Report for Limerick Generating Station Unit 2 Reload 2 Cycle 3", General Electric Company Document No. 23A7200AA, Rev. 3, July 1994. 7. Letter, G. V. Kumar to K. M. McGinnis, "Limerick ARTS Application with Equipment Out-of-Service(EOOS)", Dec. 10, 1993.

PECO Nuclear, Fuel & Services Division PECO-COLR-L2R5 I L2R5 Core Operating Limits Report Page 7, Rev. 2 8. "Safety Review for Limerick Generating Station Units 1 and 2, 110% Increased Core Flow Operation and Final Feedwater Temperature Reduction", GE Nuclear Energy Document No. NEDC 32224P, Revision 1, October 1994. 9. "Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Limerick Generating Station Units 1 and 2", GE Nuclear Energy Document No. NEDC-32193P, Rev. 2, October 1993. 10. "GE NSSS Setpoints Required to Support Power Rerate", PECON Calculation No. LE-0082, Revision 5, June 19, 1998. 11. Letter, J. A. Baumgartner to J. M. Carmody, "Limerick 2 Cycle 6 ARTS Curves", May 5, 1999. 12. Letter, R. M. Butrovich to J. M. Carmody, "Limerick 2 Cycle 6 Resolved OPL-3", December 11, 1998. 13. "Limerick Generating Station Unit 2 ECCS-LOCA Evaluation for Cycle 6", GE Nuclear Energy Document No. J11-03480-08-01P, February 1999. 14. "Power Rerate Condition Setpoint Calculations for the Philadelphia Electric Company Limerick Generating Station Units 1 & 2", GE Document No. GE-NE-208-20-0993-2, August 1994. 15. Letter, J. A. Baumgartner to K. W. Hunt, "Licensing Evaluation for Core Reconfiguration of Limerick 2 Cycle 6", April 14, 1999. 16. General Electric Report, "1OCFR50.59 Safety Evaluation, Continued Irradiation of Limerick 1 GEl1 Assemblies in Limerick 2 Cycle 6", March 22, 1999. 17. General Electric Report No. NEDE-31917P, "GEll Compliance With Amendment 22 of NEDE-24011-P-A (GESTAR II)", April 1991. 18. "ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station", GENE Document NEDC-32847P, June 1998. 19. "General Electric Standard Application for Reactor Fuel", NEDE 24011-P-A-14, June 2000. 20. Amendment to Facility Operating License for Limerick Generating Station, Unit 2, Amendment No. 104, Docket No. 50-353, License No. NPF-85. 21. Letter, R. M. Butrovitch to K. W. Hunt, "Limerick 2 Cycle 6 Revised FRED Form", November 21, 1998.

PECO Nuclear, Fuel & Services Division j.L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 8, Rev. 2 Figure 1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE 2 (P9CTB412-13GZI, GEl3) (Reference

3) This Figure is Referred to by Technical Specification 3.2.1 13.0 9.0.. ... ..N.7.0 --------0.0 10.0 20.0 30.0 40.0 50.0 Average Planar Exposure (GWd/ST)Avg. Plan Exposure (GWd/ST) 0.0 0.2 1.0 2.0 3.0 4.0 5.0 MAPLHGR (kW/ft) 10.74 10.81 10.91 11.04 11.18 11.32 11.47 11.62 Avg. Plan Exposure (GWd/ST) 7.0 8.0 9.0 10.0 12.5 15.0 17.5 MAPLHGR (kW/ft) 11.77 11.93 12.10 12.22 12.36 12.40 12.34 12.20 Avg. Plan Exposure (GWd/ST) 25.0 30.0 35.0 40.0 45.0 50.0 55.0 57.99 6.24 4.) A '3 60.0 MAPLHGR (kW/ft) 11.89 11.49 10.87 10.24 9.59 8.91 7.36 I..........

..........6.0 20.0 6.0 PECO Nuclear, Fuel & Services Division SL2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 9, Rev. 2 Figure 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPES 3, 6 & 19 (P8CIB219-4GZ, GE6) (Reference 3)This Figure is Referred to by Technical Specification 3.2.1 13.0 12..5 f -......................................................................................

.. ...................

12.0 11.5 11.0 +. ..10.+ ...10.0'0.0 5.0 10.0 Average 15.0 20.0 25.0 30.0 Planar Exposure (GWd/ST)Avg. Plan Exposure (GWd/ST) 0.2 1.0 MAPLHGR (kw/ft) 11.90 11.90 12.00 Avg. Plan Exposure (GWd/ST) 10.0 15.0 MAPLHGR (kW/ft) 11.90 11.90 2040 11.80 Avg. Plan Exposure (GWd/ST) 25.0 30.0 0 a. <4 MAPLHGR (kW/ft) 11.60 11.20 I.................... ........... .......... ................. .................... ......... .......... .......... ......S. ..... ........... ...........5.0 PECO Nuclear, Fuel & Services Division L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 10, Rev. 2 Figure 3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPES 4 & 7 (P8CIB176-4GZ, GE6) (Reference

3) This Figure is Referred to by Technical Specification 3.2.1 10.0 , 0.0 S.0 10.0 15.0 20.0 25.0 Aveerage Planar Exposure (GWd/ST)Avg. Plan Exposure (GWd/ST) 0.2 1.0 5.0 MAPLHGR (kW/ft) 11.80 11.90 Avg. Plan Exposure (GWd/ST) 10.0 15.0 MAPLHGR (kW/ft) 12.00 12.00 20.0 11.90 Avg. Plan Exposure (GWd/ST) 25.0 30.0 4: 30.0 MAPLHGR (kW/ft) 11.70 10.80 12.00 PECO Nuclear, Fuel & Services Division L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 11, Rev. 2 Figure 4 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE 5 (P9CTB412-13GZ2, GEl3) (Reference

3) This Figure is Referred to by Technical Specification 3.2.1 13.0 12.0 11.0 10.0 ..19.0-8.0 -7.0 -20.0 Average Planar 30.0 40.0 Exposure (GWd/ST)Avg. Plan Exposure (GWd/ST) 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 MAPLHGR (kW/ft) 10.74 10.81 10.91 11.04 11.18 11.32 11.47 11.62 Avg. Plan Exposure (GWd/ST) 7.0 8.0 9.0 10.0 12.5 15.0 17.5 20.0 MAPLHGR (kW/ft) 11.77 11.93 12.10 12.22 12.36 12.40 12.34 12.21 Avg. Plan Exposure (GWd/ST) 25.0 30.0 35.0 40.0 45.0 50.0 55.0 57.99 8;_0 0.0 10.0 00.0 60.0 MAPLHGR (kW/ft) 11.89 11.49 10.87 10.24 9.59 8.91 7.36 6.24 I... ........... ........ ............................ ... ........... .................. ............................. ... ............................. ................SO.O PECO Nuclear, Fuel & Services Division PECO-COLR-L2R5 I L2R5 Core Operating Limits Report Page 12, Rev. 2. Figure 5 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE 11 (P9CUB354-12GZ2, GEl1) (Reference

3) This Figure is Referred to by Technical Specification 3.2.1 14.0 2.....................................................................

12.0 10s.0 ..........

........ ....... .... ........ ...............................

.. ...... ................... -! S6 o.....0 4 -... ......... ......................... ...... 4.0 ...... ... ...............

... ....... .........

...........

.........

.. .........

..... .........

... 2.0 -...............................................

0.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 Average Planar Exposure (GWd/ST) Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) 0.0 11.05 7.0 11.98 25.0 10.98 0.2 11.09 8.0 12.13 30.0 10.58 1.0 11.19 9.0 12.30 35.0 10.15 2.0 11.31 10.0 12.42 40.0 9.77 3.0 11.44 12.5 12.38 45.0 9.44 4.0 11.56 15.0 12.10 50.0 9.13 5.0 11.70 17.5 11.79 55.0 8.83 6.0 11.84 20.0 11.49 57.74 8.55 PECO Nuclear, Fuel & Services Division I L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 13, Rev. 2 Figure 6 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE 13 (P9CUB331-9G5.0, GEll-High Exposure Program) (Reference

3) This Figure is Referred to by Technical Specification 3.2.1 13.0 12.0 11.0 10.0-J a. 4E 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 Average Planar Exposure (GWd/ST)Avg. Plan Exposure (GWd/ST) 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 7.0 MAPLHGR (kW/ft) 9.39 9.43 9.50 9.59 9.65 9.71 9.77 9.84 9.90 Avg. Plan Exposure (GWd/ST) 8.0 9.0 10.0 12.5 15.0 17.5 20.0 25.0 30.0 MAPLHGR (kW/ft) 9.97 10.04 10.12 10.22 10.13 10.04 9.94 9.77 9.59 Avg. Plan Exposure (GWd/ST) 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 72.82 MAPLHGR (kW/ft) 9.41 9.20 8.93 8.55 8.02 7.55 7.12 6.74 6.54 I PECO Nuclear, Fuel & Services Division j-L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 14, Rev. 2 Figure 7 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE 15 (P9CUB399-14GZ, GEl1) (Reference

3) This Figure is Referred to by Technical Specification 3.2.1 14.0 6 .0 . 4.0 ! ... 2.0 .....0.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 Average Planar Exposure (GWd/ST)Avg. Plan Exposure (GWd/ST) 0.0 0.2 1.0 2.0 3.0 4.0 5.0 6.0 MAPLHGR (kW/ft) 10.57 10.63 10.76 10.95 11.10 11.24 11.38 Avg. Plan Exposure (GWd/ST) 7.0 8.0 9.0 10.0 12.5 15.0 17.5 MAPLHGR (kW/ft) 11.67 11.82 11.95 12.09 12.13 11.97 11.68 Avg. Plan Exposure (GWd/ST) 25.0 30.0 35.0 40.0 45.0 50.0 55.0 20.0 11.37 MAPLHGR (kW/ft) 10.87 10.56 10.24 9.92 9.58 9.14 8.69.. ........I 12.0. .- .. ... .... ... ... .... .... 8 .,. ..........., ...... .. ...... ........................... .. ........ ...........30.0 40.0 57.08 8.50 11.53 PECO Nuclear, Fuel & Services Division L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 15, Rev. 2 Figure 8 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE 18 (P9CTB416-15GZ, GE13) (Reference

3) This Figure is Referred to by Technical Specification 3.2.1 13.0 12.0 --/11.0-aJ I 9,. 8.0 -7.0 -0.0 60.0 10.0 20.0 30.0 40.0 s0.0 Average Planar Exposure (GWd/ST)Avg. P1 an Exposure (GWd/ST) 0.0 0.2 1.0 2.0 3.0 4.0 5.0 MAPLHGR (kW/ft) 10.54 10.60 10.73 10.90 11.09 11.30 11.47 11.61 Avg. Plan Exposure (GWd/ST) 7.0 8.0 9.0 10.0 12.5 15.0 17.5 MAPLHGR (kW/ft) 11.76 11.91 12.04 12.16 12.30 12.39 12.35 Avg. Plan Exposure (GWd/ST) 25.0 30.0 35.0 40.0 45.0 50.0 55.0 20.0 12.22 MAPLHGR (kW/ft) 11.90 11.50 10.88 10.25 9.60 8.92 7.38 I 58.05 6.24 6.0 PECO Nuclear, Fuel & Services Division I L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 16, Rev. 2 FIGURE 9 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS AND FWTR OPERATING DOMAINS (Reference
9) This Figure is Referred to by Technical Specification 3.2.1 0.63 600% Flow IMAPLHGR(P)

= MAPFAC(P)

= Standard MAPLHGR Limits For 25% > P: No Thermal Limits Monitoring Required No Limits Specified For 25% <= P < 30%: MAPFAC(P)

= 0.55 + 0.004(P -30%) For <= 60% Core Flow MAPFAC(P)

= 0.50 + 0.004(P -30%) For > 60% Core Flow For 30% <= P : 20 30 40 50 60 70 80 90 MAPFAC(P)

= 1.0+ 0.005224(P

-100%)Power (% Rated)1.0 0.9-0.8 1 0.7 I 0.6 1 U. a.0.5 +0.4 +0.3 +0.2 0.1 0.0 0 10 100 I 90 70 so 40 so 60 PECO Nuclear, Fuel & Services Division I L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 17, Rev. 2 FIGURE 10 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)

THIS FIGURE IS VALID FOR THE RPTOOS OR TBVOOS OPERATING DOMAINS (Reference

7) This Figure is Referred to by Technical Specification 3.2.1 1.0 0.9 40 SO Power (% Rated)60<=- 60% Flow 0.MAPLHGR(P)

MAPFAC(P)

-MAPLHGRstd 0.53 IMAPLHGRstd

= Standard MAPLI-iGR Uimits 0.48 For 25% > P: No Thermal Umits Monitoring Required 0.40 No Umits Specified 0.35 For 25% <= P < 30%9: MAPFAC(P)

= 0.53 + 0.01 (P -30%) > 60% Row For <= 60% Core Flow MAPFAC(P)

= 0.40 + 0.01(P -30%) For > 60% Core Row For 30% <= P: MAPFAC(P)

= 0.84+ 0.004143(P

-100%)0.8 0.7 0. 0.5 0.6 S0.5 0.3 0.2 0.1 0.0 0 10 20 30 I 90 100 70 so PECO Nuclear, Fuel & Services Division I L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 18, Rev. 2 FIGURE 11 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)

THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS EXCLUDING SINGLE LOOP OPERATION (Reference

18) This Figure is Referred to by Technical Specification 3.2.1 40 50 60 70 90 90 100 Core Flow (% Rated)1.1 1.0 +0.9 +U.i 0.8 E a.7 0.6 1 0.5 0.4 30 MAPLHGR(F)

= MAPFAC(F)

= The Minimum of EITHER 1.0 OR {0.0268 x (WT-70)/10

+ 0.9732) For Two Loop Operation, 5 70% WT MAPFAC(F)

= {0.6682 x (WT/100) + 0.5055} WT = % Rated Core Flow n 100 so 90 PECO Nuclear, Fuel & Services Division .L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 19, Rev. 2 FIGURE 12 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)

THIS FIGURE IS VALID FOR SINGLE LOOP OPERATION (Reference

11) This Figure is Referred to by Technical Specification 3.2.1 40 50 60 70 Core Flow (% Rated)80 90 100 The above multiplier is capped at the SLO Reduction factor provided in Table 3.1.1 1.0+0.9 f 0.8 L 0.7 0.6 O.S 0.4 Note: 30 MAPLHGR(F)

= MAPFAC(F)

-MAPLHGRstd For Single Loop Operation, MAPFAC(F)

= The Minimum of EITHER 0.79 OR {0.6682 x (WT/100) + 0.50551 WT = % Rated Core Flow 110 I 4 100 PECO Nuclear, Fuel & Services Division L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 20, Rev. 2 TABLE 1 OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR) Use in conjunction with Figures 13, 14 and 15. (Reference 2)0 0 0 This table is valid for two-loop operation.

Add 0.02 to the OLMCPR when in Single Loop Operation.

This table is valid for all Cycle 6 fuel types. This table is referred to by Technical Specification 3.2.3.Notes: 1. When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.

TBV In Service TBV Out of RPT Out of and Service Service RPT In Service Opt. B Opt. A Opt. B Opt. A Opt. B Opt. A (Tau=0) (Tau=1) (Tau=0) (Tau=1) (Tau=0) (Tau=1) BOC TO EOR -1.31 1.32 1.35 1.35 1.40 2000 MWd/ST EOR 2000 1.32 1.35 1.38 1.41 1.40 1.48 MWd/ST to EOC PECO Nuclear, Fuel & Services Division I L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 21, Rev. 2 FIGURE 13 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS AND FWTR OPERATING DOMAINS (Reference

11) This Figure is Referred to by Technical Specification 3.2.3 283 R>60Fow 241 OPERATING UMI\T MCPR(P) =.Kp" OPERATING UIvIT MCPR(100)

IFOR P <25%: NO THERMvAL UMIT MONITORING NO LIMITS SPECIFIED FOR 25% /< P < PeyAS: (P~rfflAs

= 301) = [ Kyp + 0.032(300/a

-P)] / OLMCPR(100)

K= 2.25 FOR < 60%/6 CORE FLOW = 267 FOR > 60%/o CORE FLOW FOR 300/6< P < 45%: Kp = 1.28 + 0.0134(45%-

P) FOR45%0< P < 60%: Kp = 1.15 + 0.00867(60/a-P) FOR 6r%< P: Kp = 1.00+ 0.00375(100%

-P)20 30 40 50 Power R% Rated)60 70 80 90 100 2.8+2.6 2.4+o V 0. 2.0 A _ 1.8 1.6 1.4 1.2 J..u 0 10 1-n f J 1.0 PECO Nuclear, Fuel & Services Division PECO-COLR-L2R5 I L2R5 Core Operating Limits Report Page 22, Rev. 2 FIGURE 14 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS VALID FOR THE RPTOOS OR TBVOOS OPERATING DOMAINS (Reference

11) This Figure is Referred to by Technical Specification 3.2.3 3.8 3.61\ P R TN I I C R1 0 3.1 > 60% Flow OPERATING LIMIT MCPR(P) = Kp,* OPERATING LIMIT MCPR(100) 3.43FOR P < 25%0: NO THERMAL LIMIT MONITORING REQUIRED 3.3 NO LIMITS SPECIFIED FOR 25% < P < PBypASS: (PByPASS = 309/6) 3.0 Kp =Kyp + 0.062(30%-

P)] 1OLMCPR(100)

.<60% Flow 3.30 FOR > 60% CORE FLOW a,. .41 FOR3O%_<P<45%:

K= 1.28+0.0134(45%-P)

S2 FOR 45%< P < 60%: Kp = 1.15 + 0.00867(60%

-P) FOR 60%6< P: Kp =1.00 + 0.00375(100%

-P) 1.8 1.4" 1.0 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

PECO Nuclear, Fuel & Services Division PECO-COLR-L2R5 L2R5 Core Operating Limits Report Page 23, Rev. 2 FIGURE 15 FLOW DEPENDENT MCPR LIMITS MCPR(F) THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS (Reference

18) This Figure is Referred to by Technical Specification 3.2.3 2.00 For Two Loop Operation, SLMCPR :_ 1.12, a 40% W-r MCPR(F) = The Maximum of EITHER 1.25 OR (-0.5784 x (WT/100) + 1.7073) 1.0 !For Two Loop Operation, SLMCPR : 1.12, < 40% WT MCPR(F) = (-0.5784 x (WT/100) + 1.7073) x 1 e 0.0032 x (40 -WT)) ..0 jiW r = % Rated Core Flow 1.0 1.50 1.40 1.30 1.20 1.10 30 40 so 60 70 s0 90 100 110 Core Flow (% Rated)

PECO Nuclear, Fuel & Services Division t L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 24, Rev. 2 TABLE 2 ROD BLOCK MONITOR SETPOINTS (References 2, 9, 10 and 14)This Information is Referred to by Technical Specification 3.3.6Nominal Trip Setpoint Allowable Value LTSP 117.1% 118.3% ITSP 112.3% 113.5% HTSP 107.3% 108.5% DTSP 92% 89%These setpoints are based on a MCPR limit of 1.31 (SLMCPR=1.12) and are consistent with a RBM filter time constant between 0.1 seconds and 0.55 seconds.

LTSP -Low trip setpoint ITSP -Intermediate trip setpoint HTSP -High trip setpoint DTSP -Downscale trip setpoint PECO Nuclear, Fuel & Services Division PECO-COLR-L2R5 I L2R5 Core Operating Limits Report Page 25, Rev. 2 TABLE 3 MAPLHGR SINGLE LOOP OPERATION (SLO) REDUCTION FACTOR (Reference

13) This Information is Referred to by Technical Specification 3.2.1 SLO reduction factor = 0.79 for all Cycle 6 fuel types.

PECO Nuclear, Fuel & Services Division I L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 26, Rev. 2 TABLE 4 LINEAR HEAT GENERATION RATE LIMITS This Information is Referred to by Technical Specification 3.2.4 FUEL TYPE MAXIMUM VALUE GE6 GE21 GE13 GE11 (High Exposure LUA)13.4 kW/ft 14.4 kW/ft 14.4 kW/ft 11.5 kW/ft NOTE: The LHGR is an exposure dependent value. Due to the proprietary nature of these values only the maximum LHGR for each fuel type is listed in Table 4. The LHGR data is listed in References 3 and 4 (GNF proprietary).

PECO Nuclear, Fuel & Services Division I-L2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 27, Rev. 2 TABLE 5 TURBINE BYPASS VALVE PARAMETERS (Reference

12) This Information is Referred to by Technical Specifications 3.7.8 and 4.7.8.C TURBINE BYPASS SYSTEM RESPONSE TIME Maximum delay time before start of bypass valve opening following generation of the turbine bypass valve flow signal 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)0.10 sec 0.30 sec Number of valves = 7 MINIMUM REQUIRED BYPASS VALVES TO MAINTAIN SYSTEM OPERABILITY PECO Nuclear, Fuel & Services Division IjL2R5 Core Operating Limits Report PECO-COLR-L2R5 Page 28, Rev. 2 TABLE 6 Recirculation Pump Motor-Generator (MG) Set Scoop Tube Stops DELETED (see Reference
20) TABLE 7 Control Rod Block Instrumentation Reactor Coolant System Recirculation Flow Upscale Trip (Reference
8) This Information is Referred to by Technical Specification 3.3.6 Nominal Trip Setpoint 113.4% Allowable Value 115.6%
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