ML030840577
| ML030840577 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/14/2003 |
| From: | Gallagher M Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EXELON-COLR-L2R7, Rev 0 | |
| Download: ML030840577 (26) | |
Text
Exelkns Exelon Nuclear 200 Exelon Way Telephone 610 765 5520 wwwexeloncorp com Nuclear KSA 3-E TS 6.9.1.12 Kennett Square, PA 19348 March 14, 2003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Limerick Generating Station, Unit 2 Facility Operating License No. NPF-85 NRC Docket No- 50-353
Subject:
Issuance of the Core Operating Limits Report for Reload 7, Cycle 8, Revision 0
Dear Sir/Madam:
Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station, Unit 2, Reload 7, Cycle 8, Revision 0. Revision 0 of this report incorporates the revised cycle specific parameters resulting from the new core configuration implemented during the LGS, Unit 2 (2R07) refueling outage.
This COLR is being submitted 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, 2v-Michael P. Gallagher Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC Enclosure cc: H. J. Miller, Administrator, Region I, USNRC A. L. Burritt, USNRC Senior Resident Inspector, LGS S. P. Wall, Project Manager, USNRC
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 1, Rev. 0 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 2 RELOAD 7, CYCLE 8 f9C.Ce4ý Prepared By: Date:-. ~,v Engineer Reviewed By: Date: FM 0620 Independent Reviewer Approved By:
R. T. T~opasso Date: a/o (9/3 Manager Nuclear Design - BWR Branch
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 2, Rev. 0 LIST OF EFFECTIVE PAGES Page (s) Revision 1-25 0
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 3, Rev. 0 INTRODUCTION AND
SUMMARY
This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 2 Cycle 8:
- Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
- Minimum Critical Power Ratio (MCPR)
- Rod Block Monitor (RBM) setpoints
- 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 9, and are established such that all applicable limits of the plant safety analysis are met.
This report is prepared in accordance with Technical Specification 6.9.1.9 of Reference 1. Preparation of this report was performed in accordance with Exelon Nuclear, Nuclear Fuels Procedure NF-AB-120.
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 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 8 and their associated operating domains is available in Reference 2.
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 6. 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 6 were generated from References 2, 12, and 13.
For single loop operation, a reduction factor is used which is shown in Table 3 (Reference 2).
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 4, Rev. 0 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 8 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 (Equipment OOS) conditions.
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 all fuel types and operating domains (References 2, 8, and 11).
However, there are two sets of flow-dependent MAPFAC(F) multipliers for dual-loop and single-loop operation, References 2 and 8. In addition, there are also two sets of power-dependent MAPLHGR multipliers for, use with Equipment in Service and with Equipment OOS conditions, Reference 5. Finally, there are two sets of power dependent MCPR adjustments and multipliers for use with Equipment in Service and with Equipment OOS conditions, References 2 and 5.
These adjustments and multipliers are shown in Figures 7 through 13. 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 and 10.
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 limit 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
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 5, Rev. 0 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 Table 5 (Reference 6). 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 limits for Recirculation Pump Trip Out Of Service (RPTOOS) must be used. The MCPR(P) and MAPFAC(P) curves are independent of recirculation pump trip operability (Reference 5).
CONTROL ROD BLOCK INSTRUMENTATION REACTOR COOLANT SYSTEM RECIRCULATION FLOW UPSCALE TRIP Technical Specification Limiting Condition for Operation number 3.3.6 requires that 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 6 of this COLR. Table 6 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 10 provides the current basis for the trip setpoint values used.
SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (SLMCPR)
The Safety Limit Minimum Critical Power Ratio (SLMCPR) for Limerick 2 Cycle 8 is 1.07 for Dual Loop Operation and 1.09 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 7 Cycle 8", Global Nuclear Fuel Document No. 0000-0006-6569SRLR, Revision 0, January 2003.
- 3. "Fuel Bundle Information Report for Limerick 2 Reload 7 Cycle 8", Global Nuclear Fuel Document No. 0000-000606569FBIR, Revision 0, January 2003.
- 4. "GEl4 Compliance with Amendment 22 of NEDE-24011-P-A (GESTAR II)", NEDC-32868P, Revision 0, December 1998.
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 6, Rev. 0
- 5. "GEl4 Fuel Design Cycle-Independent Analyses for Limerick Generating Station Units 1 and 2", GE-NE-L12-00884-00-01P, March 2001.
- 6. Verified OPL-3 document for Limerick 2 Reload 7 Cycle 8 transmitted by email from Tammy G. Orr, GNF, to Christopher K.
Hoffman, Exelon Nuclear, dated September 30, 2002.
- 7. "Limerick Generating Station Units 1 and 2 ECCS-LOCA Evaluation for GE14", GE Nuclear Energy Document No. GE-NE-Jll-03793-09 01P, February 2001.
- 8. "ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station", GENE Document NEDC-32847P, June 1998.
- 9. -'General Electric Standard Application for Reactor Fuel",
NEDE-24011-P-A-14, June 2000 and U.S. Supplement NEDE-24011-P-A 14-US, June 2000.
- 10. "'Power Range Neutron Monitor System Setpoint Calculation",
Global Nuclear Fuel Calculation LE-0107, Rev. 2(GNF), March 2000.
- 11. Letter, C.P. Collins to K. Donovan, "Removal of MCPR(f) Low Flow Correction in NEDC-32847P", February 4, 2002.
- 12. "Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 2 Reload 6 Cycle 7", Global Nuclear Fuel Document No. J11-03793MAPL, Revision 0, March 2001.
- 13. "Limerick 2 Cycle 8 Fresh Fuel MAPLHGR" email from A. Enica, GNF to S. Getz, Exelon, dated January 28, 2003.
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 7, Rev. 0 Figure 1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE: GE13-P9CTB4l2-l3GZ1-100T-146-T6 (GE13)
(References 2 and 12)
This Figure is Referred to by Technical Specification 3.2.1 F
6.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 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 10.74 7.0 11.77 25.0 11.89 0.2 10.81 8.0 11.93 30.0 11.49 1.0 10.91 9.0 12.10 35.0 10.87 2.0 11.04 10.0 12.22 40.0 10.24 3.0 11.18 12.5 12.36 45.0 9.59 4.0 11.32 15.0 12.40 50.0 8.91 5.0 11.47 17.5 12.34 55.0 7.36 6.0 11.62 20.0 12.20 57.99 6.24
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 8, Rev. 0 Figure 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE: GEl3-P9CTB412-13GZ2-100T-146-T6 (GE13)
(References 2 and 12)
This Figure is Referred to by Technical Specification 3.2.1 4
J
'4 20.0 30.0 40.0 50.0 70.0 Average Planar Exposure (*d/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 10.74 7.0 11.77 25.0 11.89 0.2 10.81 8.0 11.93 30.0 11.49 1.0 10.91 9.0 12.10 35.0 10.87 2.0 11.04 10.0 12.22 40.0 10.24 3.0 11.18 12.5 12.36 45.0 9.59 4.0 11.32 15.0 12.40 50.0 8.91 5.0 11.47 17.5 12.34 55.0 7.36 6.0 11.62 20.0 12.21 57.99 6.24
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 9, Rev. 0 Figure 3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE: GE14-PIOCNAB403-16GZ-1O0T-150-T6-3957 (GE14C)
(References 2, 3, and 12)
This Figure is Referred to by Technical Specification 3.2.1 4)
A 20.0 30.0 40.0 60.0 Average Planar Exposure ((md/ST)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWdIST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) 0.0 9.52 7.0 10.58 25.0 10.08 0.2 9.61 8.0 10.73 30.0 9.66 1.0 9.73 9.0 10.81 35.0 "9.23 2.0 9.82 10.0 10.89 40.0 8.78 3.0 9.95 12.0 10.97 45.0 8.30 4.0 10.10 15.0 10.82 50.0 7.78 5.0 10.27 17.0 10.70 55.0 5.52 6.0 10.43 20.0 10.50 56.33 4.86
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 10, Rev. 0 Figure 4 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE: GE14-PIOCNAB403-16GZ-100T-150-T6-3956 (GEI4C)
(References 2, 3, and 12)
This Figure is Referred to by Technical Specification 3.2.1 12.0 11.0 10.0 4, 9.0
'4 8.0 7.0 6.0 5.0 4.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 Average Planar Exposure (*d/ST)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/ST) (kW/ft) (GWdIST) (kW/ft) (GWd/ST) (kW/ft) 0.0 9.55 8.0 10.73 35.0 9.23 0.2 9.64 9.0 10.81 40.0 8.78 1.0 9.73 10.0 10.89 45.0 8.30 2.0 9.82 12.0 10.97 50.0 7.78 3.0 9.95 15.0 10.82 55.0 5.52 4.0 10.10 17.0 10.70 56.33 4.86 5.0 10.27 20.0 10.50 6.0 10.43 25.0 10.08 7.0 10.58 30.0 9.66
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 11, Rev. 0 Figure 5 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE: GEl4-PIOCNAB417-15GZ-1OOT-150-T-2592 (GE14C)
(References 2 and 13)
This Figure is Referred to by Technical Specification 3.2.1 4.2
'.4 A
4.0 r "r 0.0 10.0 20.0 30.0 40.0 50.0 60.0 Average Planar Exposure (G~dfST)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWdIST) (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft) 0.0 10.00 8.0 10.91 35.0 9.39 0.2 10.01 9.0 10.99 40.0 8.91 1.0 10.03 10.0 11.07 45.0 8.40 2.0 10.11 12.0 11.17 50.0 7.87 3.0 10.22 15.0 11.04 55.0 5.89 4.0 10.34 17.0 10.95 57.06 4.86 5.0 10.49 20.0 10.76 6.0 10.64 25.0 10.34 7.0 10.81 30.0 9.87
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 12, Rev. 0 Figure 6 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE: GEl4-PlOCNAB417-14GZ-lOOT-150-T-2591 (GEl4C)
(References 2 and 13)
This Figure is Referred to by Technical Specification 3.2.1
'4 A
4.0 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 10.02 8.0 10.77 35.0 9.39 0.2 10.07 9.0 10.87 40.0 8.91 1.0 10.15 10.0 10.98 45.0 8.40 2.0 10.24 12.0 11.13 50.0 7.86 3.0 10.34 15.0 11.01 55.0 5.84 4.0 10.46 17.0 10.91 56.96 4.86 5.0 10.54 20.0 10.74 6.0 10.60 25.0 10.34 7.0 10.68 30.0 9.87
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 13, Rev. 0 FIGURE 7 POWER DEPENDENT I MAPLHGR MULTIPLIER MAPFAC(P)
THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS AND FWTR OPERATING DOMAINS (RPT IN SERVICE OR RPTOOS)
(Reference 5)
This Figure is Referred to by Technical Specification 3.2.1 1.0 t 0.8f 06343 MAPLHGR(P) MAPFAC(P) MAPLHGRstd 0.6 t < 60% Flow MAPLHGRstd = Standard MAPLHGR Limits I *0.4 For 25% > P : No Thermal Umits Monitonng Required 0485 0490 No Limits Specified 0.434 0473 For25% < P<30%: MAPFAC(P)= 0.490+ 00010(P-30%)
0 .4 t / For< 60% Core Flow a'
> 60% Flow MAPFAC(P) = 0.473 + 0.0078(P - 30%)
For > 60% Core Flow For 30% < P: MAPFAC(P) = 1.0+ 0 005224(P - 100%)
0 .2+
0.0 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 14, Rev. 0 FIGURE 8 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)
THIS FIGURE IS VALID FOR THE TBVOOS OPERATING DOMAIN (Reference 5)
This Figure is Referred to by Technical Specification 3.2.1 1.01 0.8f 064 MAPLHGR(P) = MAPFAC(P)
- MAPLHGRstd 0.6 1- <c60% Flow 0490 MAPLHGRstd - Standard MAPLHGR Umits 0
0463, 04For 25% > P : No Thermal Umits Monitoring Required 0 463 .. No Limits Specified 0.4 : 0.386 For 25%x P < 30%: MAPFAC(P) = 0 490 + 0 0054(P - 30%)
0.352 For < 60% Core Flow
> 60% Flow MAPFAC(P) = 0.386 + 0.0068(P - 30%)
For > 60% Core Flow 0.2 f For 30% < P: MAPFAC(P) = 1.0+ 0 005224(P - 100%)
Si I I I I I 0.0 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 15, Rev. 0 FIGURE 9 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)
THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS EXCLUDING SINGLE LOOP OPERATION (References 2 and 8)
This Figure is Referred to by Technical Specification 3.2.1 1.1 1.0-0 .9 +
V.
IAAPLHGR(F) = MAPFAC(F)
- MAPLHGRstd "ow0.7
=
For Tmo Loop Operation, > 70% WT MAPFAC(F) = The Mirinimn of EITHER 1.0 OR {0 0268 x (Wr-70Yl0 + 0 9732) 0.6 For TMo Loop Operation, <70% Wr MAPFAC(F) = (0 6682 x (WT/100)+ 0 5055) 0.5 + WT = % Rated Core Flow 0.4 I I I I 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 16, Rev. 0 FIGURE 10 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)
THIS FIGURE IS VALID FOR SINGLE LOOP OPERATION (References 2 and 8)
This Figure is Referred to by Technical Specification 3.2.1 1.1 1.0 1 0.9 t U
0.8 t Er C, 0.7 5
MAPLHGR(F) - MAPFAC(F)
- MAPLHGRstd 0.6 t For Single Loop Operation.
MAPFAC(F) = The Minimum of EITHER 0 79 OR {0 6682 x (WN100) + 0 50551 0.5 t WT= % Rated Core Flow I I I I I I I 0.4 30 40 50 60 70 80 90 100 o10 Core Flow (% Rated)
Note: The above multiplier is capped at the SLO Reduction factor provided in Table 3.
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 17, Rev. 0 TABLE 1 OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR)
Use in conjunction with Figures 11, 12 and 13.
(References 2 and 5)
S This table is valid for all Cycle 8 fuel types.
S This table is referred to by Technical Specification 3.2.3.
TBV In Service and TBV out of Service RPT Out of Service RPT In Service OPT. B
(,Z=0) (1) OPT. (1)
(.1=1) A =0 (B)
(OPT. = )( A)
(OPT. = )( B)
(OPT. = )( A)
(OPT.
Two Loop BOC 1.33 1.36 1.37 1.40 1.40 1.51 Operation to EOR 2000 MWd/ST Two Loop oprton EOR 200 2000 1.37 1.40 1.42 1.45 1.46 1.63 operation MWd/ST to EOC Single BOC 1.44(2) 1.44(2) 1.44(2) 1.44(2) 1.44(2) 1.53 Loop to Operation EOR 2000 MWd/ST Single EOR - 1.44(2) 1.44(2) 1.44 1.47 1.48 1.65 Loop 2000 Operation MWd/ST to EOC Notes:
- 1. When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.
Recirculation Pump Seizure Analysis.
EXELON Nuclear, Nuclear Fuels EXELON- COLR-L2R7 L2R7 Core Operating Limits Report Page 18, Rev. 0 FIGURE 11 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS AND FWTR OPERATING DOMAINS (RPT IN SERVICE OR RPTOOS)
(References 2 and 5)
This Figure is Referred to by Technical Specification 3.2.3 4.0 3.8 OPERATING LIMIT MCPR(P) - K,- OPERATING UMITMCPR(100) 3.6 FOR P<25%: NO THERMAL LIMITIMONITORING REQUIRED 339 NO LIMITS SPECFED 3.4 ;> vW NOW FOR 25% < P < PBypss : (Psyp*ss = 30%)
3.2 OLMCPR(P) = [ 2 44 + 0 044(30% - P)]
3.0 2.93 FOR < 60% CORE FLOW j 2.8 2.66 < 60% Flow OLMCPR(P) = [2.93 + 0.094(30% - P)]
FOR > 60% CORE FLOW 2.6 0 \-` 2.44 FOR 30%< P < 45%: Kp = 1.28 + 0 0134(45% - P) 2.4 2:
FOR 45%< P < 60%: Kp=1.15+0.00867(60%-P) 2.2 a
2.0 FOR 60%< P: Kp = 1.00+ 0.00375(100% - P)
U U
1.8 1.6 1.4 1.2 1.0 I I I I I I I 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 19, Rev. 0 FIGURE 12 POWER DEPENDENT MCPR LIMIT ADJUSTMENTS AND MULTIPLIERS THIS FIGURE IS VALID FOR THE TBVOOS OPERATING DOMAIN (References 2 and 5)
This Figure is Referred to by Technical Specification 3.2.3 5.0 4.6 4.54 OPERATING LIMIT MCPR(P) = Kp* OPERATING LIMIT MCPR(100)
>60% Flow A,. FOR P < 25%: NO THERMAL LIMIT MONITORING REQUIRED 4.2 NO LIMITS SPECIFIED FOR 25%: <P< Pyp~ss: (Pa'pss = 30%)
3.83.77 OLMCPR(P) = [2.63 + 0.090(30% - P)]
3.8 FOR < 60% CORE FLOW OLMCPR(P) = [3.77 + 0.156(30% - P)]
307 < 60% Flow FOR > 60% CORE FLOW 2 3.0 FOR 30% < P < 45%: Kp - 1.28 + 0 0134(45% - P)
" 2.6 263 FOR 45% < P < 60%: Kp = 1.15 + 0.00867(60% - P)
FOR 60% < P: Kp 1.00 + 0.00375(100% - P)
= 2.2 1.8 1.4 1.0 +I I ÷ +I 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 20, Rev. 0 FIGURE 13 FLOW DEPENDENT MCPR LIMITS MCPR(F)
THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS (References 2, 8, and 11)
This Figure is Referred to by Technical Specification 3.2.3 2.00 For Two Loop Operation, 1.90 1 MCPR(F) = The Maximum of EITHER 1.25 OR {-0*5526 x (WT/100) + 16311) 1.80 f WT = % Rated Core Flow 1.70 f C 1.60 1.50 1.40 1.30 1.20-In*1,/
- 1. di.
30 40 50 60 70 80 90 100 110 Core Flow (% Rated)
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 21, Rev. 0 TABLE 2 ROD BLOCK MONITOR SETPOINTS (References 2 and 10)
This Information is Referred to by Technical Specification 3.3.6 Nominal Trip Allowable Value Setpoint LTSP 121.5% 121.5%
ITSP 116.5% 116.5%
HTSP 111.0% 111.7%
DTSP 92.0% 89.0%
These setpoints are based on a MCPR from Reference 10, limited by an OLMCPR of 1.33 (SLMCPR=1.07), 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
EXELON-COLR-L2R7 Fuels EXELON Nuclear, Nuclear EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 22, Rev. 0 TABLE 3 MAPLHGR SINGLE LOOP OPERATION (SLO) REDUCTION FACTOR (Reference 2)
This Information is Referred to by Technical Specification 3.2.1 SLO reduction factor = 0.79 for the Cycle 8 core.
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 23, Rev. 0 TABLE 4 LINEAR HEAT GENERATION RATE LIMITS This Information is Referred to by Technical Specification 3.2.4 FUEL TYPE MAXIMUM VALUE GEl3 14.4 kW/ft GE14 13.4 kW/ft NOTE: The LHGR limit 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 Reference 3 (GNF proprietary).
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 24, Rev. 0 TABLE 5 TURBINE BYPASS VALVE PARAMETERS (Reference 6)
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 0.11 sec of bypass valve opening following generation of the turbine bypass valve flow signal Maximum time after generation 0.31 sec of a turbine bypass valve flow signal for bypass valve position to reach 80% of full flow (includes the above delay time)
MINIMUM REQUIRED BYPASS VALVES TO MAINTAIN SYSTEM OPERABILITY Number of valves = 7
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L2R7 L2R7 Core Operating Limits Report Page 25, Rev. 0 TABLE 6 Control Rod Block Instrumentation Reactor Coolant System Recirculation Flow Upscale Trip (Reference 10)
This Information is Referred to by Technical Specification 3.3.6 Nominal Trip Setpoint < 113.4%
Allowable Value < 115.6%