ML020860463
| ML020860463 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/15/2002 |
| From: | Gallagher M Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML020860463 (27) | |
Text
ExeIc,, n.m Exelon Nuclear 2oo Exelon Way www.exeloncorp.com Nuclear Kennett Square, PA 19348 TS 6.9.1.12 March 15, 2002 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Limerick Generating Station, Unit 1 Facility Operating License No. NPF-39 NRC Docket No. 50-352
Subject:
Issuance of the Core Operating Limits Report for Reload 9, Cycle 10, Revision 0
Dear Sir/Madam:
Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station, Unit 1, Reload 9, Cycle 10, Revision 0. Revision 0 of this report incorporates the revised cycle specific parameters resulting from the new core configuration implemented during the LGS, Unit 1 (1 R09) refueling outage.
This COLR is being submitted to the NRC in accordance with LGS, Unit 1 Technical Specifications (TS) Section 6.9.1.12.
If you have any questions, please do not hesitate to contact us.
Very truly yours, Michael P. Gallagher Director, Licensing and Regulatory Affairs Mid-Atlantic Regional Operating Group Enclosure cc: H. J. Miller, Administrator, Region I, USNRC A. L. Burritt, USNRC Senior Resident Inspector, LGS C. Gratton, Senior Project Manager, USNRC
EXELON-COLR-LIR9 EXELON Nuclear, Nuclear Fuel Management Page 1, Rev. 0 L1R9 Core Operating Limits Report CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 1 RELOAD 9, CYCLE 10 Prepared By: 2 C.
S. C.
Engineer Date: $*// I0 2 Reviewed By: Date: /* 2 R. LT. Wolf*d,4 Independent Reviewer Approved By: Date: 21/(W8O o R. T. Topasso Manager Nuclear Design - BWR Branch
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 Page 2, Rev. 0 LlR9 Core Operating Limits Report LIST OF EFFECTIVE PAGES Page (s) Revision 1-26 0
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-L1R9 LlR9 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 1 Cycle 10:
- Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
- Minimum Critical Power Ratio (MCPR)
Ssingle Loop Operation (SLO) MCPR adjustment
- 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 I. Preparation of this report was performed in accordance with Exelon Nuclear, Nuclear Fuel Management 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 1 Cycle 10 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 7. 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 7 were generated from Reference 3.
For single loop operation, a reduction factor is used which is shown in Table 3 (Reference 2).
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LlR9 LIR9 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 10 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 8 and 11). However, there are two sets of flow-dependent MAPFAC(F) multipliers for dual loop and single-loop operation, References 2, 5 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 0OS conditions, References 2 and 5.
These adjustments and multipliers are shown in Figures 8 through 14. 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.
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 LIR9 Core Operating Limits Report Page 5, Rev. 0 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 Reference 3 (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 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 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 Ration (SLMCPR) for Limerick 1 Cycle 10 is 1.10 for Dual Loop Operation and 1.11 for Single Loop Operation. These values are documented in Reference 2.
REFERENCES
- 1. "Technical Specifications and Bases for Limerick Generating Station Unit 1", Docket No. 50-352, License No. NPF-39.
- 2. "Supplemental Reload Licensing Report for Limerick Generating Station Unit 1 Reload 9 Cycle 10", Global Nuclear Fuel Document No. J1I-03984SRLR, Revision 0, January 2002.
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 LIR9 Core Operating Limits Report Page 6, Rev. 0
- 3. "Lattice Dependent MAPLHGR Report for Limerick Generating Station Unit 1 Reload 9 Cycle 10", Global Nuclear Fuel Document No. JlI-03984MAPL, Revision 0, January 2002.
- 4. "'GEl4 Compliance with Amendment 22 of NEDE-24011-P-A (GESTAR II), NEDC-32868P, Revision 0, December 1998.
- 5. "GEl4 Fuel Design Cycle-Independent Analyses for Limerick Generating Station Units 1 and 2", GE-NE-L12-00884-00-01P, March 2001.
- 6. "OPL-3 Transient Protection Parameters Verification for Reload Licensing Analyses for Limerick 1 Reload 9 Cycle 10", Resolved, as transmitted by e-mail from C. P. Collins to R. Wolfgang, November 12, 2001.
- 7. -- Limerick Generating Station Units 1 and 2 ECCS-LOCA Evaluation for GEl4", 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.
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LlR9 LlR9 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-P9CTB417-13GZ-100T-146-T (GEl3)
(Reference 3)
This Figure is Referred to by Technical Specification 3.2.1 13.0 12.0 11.0 S10.0 S 9.0 8.0 7.0 6.04 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 10.46 7.0 11.53 25.0 12.01 0.2 10.54 8.0 11.69 30.0 11.59 1.0 10.65 9.0 11.85 35.0 10.96 2.0 10.79 10.0 12.02 40.0 10.32 3.0 10.93 12.5 12.26 45.0 9.66 4.0 11.08 15.0 12.45 50.0 8.97 5.0 11.22 17.5 12.44 55.0 7.43 6.0 11.37 20.0 12.32 58.03 6.29
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LlR9 LlR9 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-P9CTB417-11GZ-100T-146-T (GEl3)
(Reference 3)
This Figure is Referred to by Technical Specification 3.2.1 M
6.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 Average Planar Exposure (CJd/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 10.79 7.0 11.75 25.0 12.00 0.2 10.85 8.0 11.91 30.0 11.60 1.0 10.93 9.0 12.06 35.0 10.96 2.0 11.05 10.0 12.21 40.0 10.33 3.0 11.17 12.5 12.43 45.0 9.67 4.0 11.31 15.0 12.55 50.0 8.98 5.0 11.45 17.5 12.47 55.0 7.49 6.0 11.59 20.0 12.32 58.2 6.29
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 LIR9 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-PIOCNAB417-7G8.0/8G7.0-100T-150-T-2527 (GEI4C)
(Reference 3)
This Figure is Referred to by Technical Specification 3.2.1 12.0 11.0 10.0 9.0 M
8.0
,-1 7.0 6.0 5.0 4.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 Average Planar Eposure (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 10.00 7.0 10.81 25.0 10.34 0.2 10 .01 8.0 10.91 30.0 9.87 1.0 10 .03 9.0 10.99 35.0 9.39 2.0 10 .11 10.0 11.07 40.0 8.91 3.0 10 .22 12.0 11.17 45.0 8.40 4.0 10.34 15.0 11.04 50.0 7.87 5.0 10.49 17.0 10.95 55.0 5.89 6.0 10.64 20.0 10.76 57.06 4.86
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 LlR9 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-PIOCNAB417-13GZ-1OOT-150-T-2528 (GE14C)
(Reference 3)
This Figure is Referred to by Technical Specification 3.2.1 12.0 11.0 10.0 4., 9.0 M
8.0 0
7.0 6.0 5.0 4.0 1 0.0 10.0 20.0 30.0 40.0 50.0 60.0 Average Planar Exposure (GJd/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 10.17 7.0 10.92 25.0 10.34 0.2 10.22 8.0 11.02 30.0 9.86 1.0 10.26 9.0 11.09 35.0 9.38 2.0 10.32 10.0 11.15 40.0 8.90 3.0 10.42 12.0 11.25 45.0 8.40 4.0 10.53 15.0 11.09 50.0 7.86 5.0 10.66 17.0 10.98 55.0 5.91 6.0 10.81 20.0 10.78 S7.12 4.85
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 Page 11, Rev. 0 LIR9 Core Operating Limits Report Figure 5 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE GE14-PIOCNAB417-7G8.0/8G7.0-8OU45R-150-T-2531 (GE14C)
(Reference 3)
This Figure is Referred to by Technical Specification 3.2.1 12.0 11.0 10.0 9.0 M
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 (G(d/ST)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft)
(GWd/ST) 10.08 7.0 10.86 25.0 10.36 0.0 10.09 8.0 10.95 30.0 9.88 0.2 9.0 11.02 35.0 9.40 1.0 10.10 10.18 10.0 11.10 40.0 8.91 2.0 10.28 12.0 11.21 45.0 8.40 3.0 10.40 15.0 11.07 50.0 7.86 4.0 10.54 17.0 10.98 55.0 5.91 5.0 20.0 10.79 57.13 4.85 6.0 10.70
EXELON-COLR-LIR9 EXELON Nuclear, Nuclear Fuel Management Page 12, Rev. 0 LIR9 Core Operating Limits Report Figure 6 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE GE13-P9CTB412-13GZ-100T-146-T (GE13)
(Reference 3)
This Figure is Referred to by Technical Specification 3.2.1 M
6.0 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 (kW/ft) (GWd/ST) (kW/ft) (GWd/ST) (kW/ft)
(GWd/ST) 10.89 7.0 11.92 25.0 11.87 0.0 8.0 12.02 30.0 11.47 0.2 10.95 9.0 12.12 35.0 10.85 1.0 11.04 11.18 10.0 12.21 40.0 10.22 2.0 11.33 12.5 12.31 45.0 9.58 3.0 15.0 12.35 50.0 8.90 4.0 11.49 17.5 12.31 55.0 7.34 5.0 11.65 20.0 12.17 57.93 6.24 6.0 11.78
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 LIR9 Core Operating Limits Report Page 13, Rev. 0 Figure 7 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE GE13-P9CTB413-14GZ-100T-146-T (GE13)
(Reference 3)
This Figure is Referred to by Technical Specification 3.2.1 13.0 12.0 11.0 44, S10.0 0 S9.
8.0 7.0 6.0 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 10.76 7.0 11. 90 25.0 11.87 0.2 10. 83 8.0 12.01 30.0 11.47 1.0 10 .97 9.0 12.11 35.0 10.85 2.G 11 18 10.0 12.21 40.0 10.22 3.0 11.34 12.5 12.30 45.0 9.58 4.0 11.50 15.0 12.35 50.0 8.90 11 66 17.5 12.31 55.0 7.33 5.0 6.0 11.78 20.0 12.17 57.91 6.24
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LlR9 LlR9 Core Operating Limits Report Page 14, Rev. 0 FIGURE 8 POWER DEPENDENT 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 0.8 1 0.6343 MAPLHGR(P) = MAPFAC(P) MAPLHGRstd 0.6 t < 60% Flow MAPLHGRstd = Standard MAPLHGR Limits For 25% > P : No Thermal Limits Monitoring Required 0.485 0.490 No Limits Specified 0.434 0.473 For 25% < P < 30%: MAPFAC(P) = 0.490 + 0.0010(P - 30%)
04 For < 60% Core Flow
> 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 Fuel Management EXELON-COLR-LIR9 LlR9 Core Operating Limits Report Page 15, Rev. 0 FIGURE 9 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 1.0 0.8 C,. MAPLHGR(P) = MAPFAC(P) *MAPLHGRstd Fo0 0 MAPLHGRstd =Standard MAPLHGR Limits Limits Monitoring Required For 25% > P: No Thermnal fJ 0.463No Limits Specified 0.4 0.386 0.352For 25% < P < 30%: MAPFAC(P) = 0.490 + 0.0054(P - 30%)
For < 60% Core Flow
> 60% Flow MAPFAC(P) = 0.386 + 0.0068(P - 30%)
For > 60% Core Flow 0.2 For 30% < P: MAPFAC(P) =1 .0W 0.005224(P - 100%)
II 0.0 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 L1R9 Core Operating Limits Report Page 16, Rev. 0 FIGURE 10 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)
THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS EXCLUDING SINGLE LOOP OPERATION (References 5 and 8)
This Figure is Referred to by Technical Specification 3.2.1 1.1 1.0 0.9 V0.8 O
U L.2 MAPLHGRQ ) = MAPFAC(F)
C,, 0 .7t For Tmo Loop Operation, > 70%/6 WT
-J MAPFAC(F) = The Mirnmum of EITHER 1.0 OR {0.0268 x (Wr-70)10 + 0.9732}
0.6 +
For Two Loop Operation, < 70% WT MAPFAC(F) = {0.6682 x (W100)+ 0.5055}
WT = % Rated Core Flow 0.5 +
I I 0.4 30 40 50 60 70 80 90 100 10 Core Flow (% Rated)
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 L1R9 Core Operating Limits Report Page 17, Rev. 0 FIGURE 11 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 +
0.9 t S0.8 0.7 MAPLHGR(F) = MAPFAC(F)
- MAPLHGRstd 0.6 For Single Loop Operation, MAPFAC(F) = The Minimum of EfTHER 0.79 OR {0.6682 x (WT/100) + 0.5055}
0.5 + WT = % Rated Core Flow 0.4 30 40 50 60 70 80 90 100 Core Flow (% Rated)
Note: The above multiplier is capped at the SLO Reduction factor provided in Table 3.
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 LIR9 Core Operating Limits Report Page 18, Rev. 0 TABLE 1 OPERATING LIMIT MINIMUM CRITICAL POWER RATIO (OLMCPR)
Use in conjunction with Figures 12, 13 and 14.
(References 2 and 5)
"* This table is valid for all Cycle 10 fuel types.
"* 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 OPT. A OPT. B OPT. A OPT. B (,C= A OPT.i) (1)
('C= 0) (1) (,r= i) (1) ('C= 0) (1) (,r= i) (1) ('C= 0) (1)
Two Loop BOC 1.35 1.38 1.43 1.46 1.47 1.64 Operation to EOR 2000 MWd/ST Two Loop oprton EOR 200 1.39 1.42 1.43 1.46 1.47 1.64 Operation 2000 MWd/ST to EOC Single BOC 1.47(2) 1.47(2) 1.47(2) 1.47 1.48 1.65 Loop to Operation EOR 2000 MWd/ST Single EOR - 1.47(2) 1.47(2) 1.47(2) 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 Fuel Management EXELON-COLR-LIR9 LlR9 Core Operating Limits Report Page 19, Rev. 0 FIGURE 12 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 UMIT MCPR(P) = Kp - OPERAllNG LIMIT MCPR(100) 3.6 FOR P < 25%: NO TFHERMAL UMIT MONITORING REQUIRED 3.48 > 60% Flow NO UMITS SPECIFIED 3.4 FOR 25% < P < PBYPASS : (PBYPASS = 30%)
3.2 3.01 OLMCPR(P) = [ 2.51 + 0.044(30% - P)]
3.0 FOR <= 60% CORE FLOW S2.8 OLMCPR(P) = [3.01 + 0.094(30% - P)]
2.73 . 60% Flow FOR > 60% CORE FLOW F 2.6 2.51 FOR 30% < P < 45%: Kp = 1.28 + 0.0134(45% - P) 9' 2.4 FOR 45% < P < 60%: Kp = 1.15 + 0.00867(60% - P)
- 2.2 FOR 60% < P: Kp = 1.00 + 0.00375(100% - P)
"* 2.0 1.8 1.6 1.4 1.2 1.0 I J I ] I 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-L1R9 LlR9 Core Operating Limits Report Page 20, Rev. 0 FIGURE 13 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 I 4.66 OPERATING UMIT MCPR(P) = Kp
- OPERATING LIMIT MCPR(100) 4.6 t
> 60% Flow FOR P < 25%: NO THERMAL UMIT MONITORING REQUIRED NO UMITS SPECIFIED 4.2 t FOR 25% < P < PBYPASS: (PSYPASS = 30%)
3.88 3.8 + OLMCPR(P) = [2.70 + 0.090(30% - P)]
FOR <= 60% CORE FLOW 3.4 t OLMCPR(P) = [3.88 + 0.156(30% - P)]
3.16 <60% Flow FOR > 60% CORE FLOW 3.0 t :OR 30% < P < 45%: Kp= 1.28 + 0.0134(45% - P) 2.70 :OR 45% < P < 60% : Kp = 1.15 + 0.00867(60% - P) 2.6 t FOR 60% < P: K, = 1.00 + 0.00375(100% - P) 2.2t 1.8 -
1.4 f 1.0 I J I [ L I 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 LIR9 Core Operating Limits Report Page 21, Rev. 0 FIGURE 14 FLOW DEPENDENT MCPR LIMITS MCPR(F)
THIS FIGURE IS VALID FOR ALL OPERATING DOMAINS (References 8 and 11)
This Figure is Referred to by Technical Specification 3.2.3 2.00 For Two Loop Operation, SLMCPR < 1.12 1.90 t MCPR(F) = The Maximum of EITHER 1.25 OR {-0.5784 x (WT/100) + 1.7073}
WT = % Rated Core Flow 1.80 t 1.70 T I. 1.60 1.50-1.40t 1.30-1.20 t 1.10 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 LlR9 Core Operating Limits Report Page 22, 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 1.35 (SLMCPR=1.10), 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 Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 LlR9 Core Operating Limits Report Page 23, 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 10 core.
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LlR9 LlR9 Core Operating Limits Report Page 24, Rev. 0 TABLE 4 LINEAR HEAT GENERATION RATE LIMITS This Information is Referred to by Technical Specification 3.2.4 FUEL TYPE MAXIMUM VALUE GE13 14.4 kW/ft GE14 13.4 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 Reference 3 (GNF proprietary).
EXELON-COLR-LlR9 EXELON Nuclear, Nuclear Fuel Management Page 25, Rev. 0 LIR9 Core Operating Limits Report 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 0.31 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)
MINIMUM REQUIRED BYPASS VALVES TO MAINTAIN SYSTEM OPERABILITY Number of valves = 7
EXELON Nuclear, Nuclear Fuel Management EXELON-COLR-LIR9 Page 26, Rev. 0 LIR9 Core Operating Limits Report 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%