ML14112A582
| ML14112A582 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/25/2014 |
| From: | Bradish D, Jurgens T Exelon Generation Co, Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14113A026 | List: |
| References | |
| LG-14-055 | |
| Download: ML14112A582 (55) | |
Text
ENCLOSURE 3 UNIT 2 COLR FOR CYCLE 13 REV. 8 WITH APPENDIX A PROPRIETARY CLASS I (PUBLIC)
Ezeton Nudesr- Nuclear Fuels Doe ID: COLR Umerkk I, Rev. II Core Operating Limit Report Non-Propriftary Infonruden Submiettd in Acordance with O CFR 2.390 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 1 RELOAD 15 CYCLE 16 FCP ECR LG 13-00136 Rev. 1 Prepared By:;2/T Ju>g Date: 03/25/14 D. BrmdishtT. Jurgeni Reviewed By: QRAttfi TI1*k4Pg P9R TLLFC614 /e Dvle: L02I5 L F. Ttikur Indepednt Reviewer Reviewed By:
MOLThonm Reactor Elineefng Reviewer Reviewed By: L Date: 03/25/14 T. Bemnt Engineering Sfety Analysis Reviewer Approved By: Date:
J.Tusar L
Manager - BWR Design Qualified.
Station Review By: tIj l Daoe: -aIZ6L&
Page I of 54
ExcI4on Nuiclear - Nuaclear Fuels Doc II): COLR Limerick 1, Rev. I I Core Operating Limits Report Non-Proprictary Informatiton Submitted in Accordan~ce with~ 10 CFR 2.390 Table of Contentts Page 1.0 Terms and Definitions 4 2.0 General Information 6 3.0 MAPLJIGR Limits 7 4.0 MCPR Limits 8 5.0 LHIGR Limits 11 6.0 Control Rod Block Setpoints 13 7.0 Turbine Bypass Valve Parameters 14 8.0 Stability Protection Setpoints 15 9.0 Modes of Operation 16 10.0 Methodology 17 11.0 References 17 Appendix A 18 Page 2 of 54
Ixel(o Nuclear - Nuclear Fuels Moe !1): C()LI, Limerick I, Rev. I I Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 101CFR 2.390 List of Tables Page Table 3-1 MAPLI-IGR Versus Average Planar Exposure- GE14 7 Table 3-2 MAPLHGR Versus Average Planar Exposurec- GNF2 7 Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier- All Fuel Types 7 Table 4-I Operating Limit Minimum Critical Power Ratio (OLMCPR) - GE14 9 Table 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR).- GNF2 9 Table 4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp - All Fuel Types 10 Table 4-4 Flow Dependent MCPR Limits MCPR(F) - All Fuie Types 10 Table 5-I Linear Heat Generation Rate Limits - U0 2 Rods 11 Table 5-2 Linear Heat Generation Rate Limits- Gadolinia Rods 11 Table 5-3 LHIGR Single Loop Operation (SLO) Multiplier-- All Fuel Types 12 Table 5-4 Power Dependent LHGR Multiplier LHGRFAC(P) -- All Fuel Types 12 Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) - All Fuel Types 12 Table 6-1 Rod Block Monitor Setpoints 13 Table 6-2 Reactor Coolant System Recirculation Flow Upscale Trip 13 Table 7-1 Turbine Bypass System Response Time 14 Table 7-2 Minimum Required Bypass Valves To Maintain System Operability 14 Table 8-1 OPRM PBDA Trip Setpoints 15 Table 8-2 SLO OPRM PBDA Trip Setpoints 15 Table 9-I Modes of Operation 16 Page 3 of 54
Exclon Nuclear - Nudear Fuels Doc ID: COLR Limerick I, Rev. I I
('ore Operating Limits Report Non-Proprietary Infmiormation Submitted in Accordance with 10 CFR 2.390 1.0 Terms and Definitions ARTS APRM and RBM Technical Specification BASE A case analyzed with Turbine Bypass System in service, Recirculation Pump Trip in service, Feedwater Temperature Reduction allowed (FFWTR includes feedwater heater OOS or final feedwater temperature reduction) and PLUOOS allowed at any point in the cycle operation in Dual Loop mode.
DLO Dual Loop Operation DTSP Rod Block Monitor Downscale Trip Setpoint FOOS Equipment Out of Service FEOR End of Rated. The cycle exposure at which reactor power is equal to rated thermal power with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.
FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service HTSP Rod Block Monitor High Trp Setpoint ICF Increased Core Flow ITSP Rod Block Monitor Intermediate Trip Setpoint Kp Off-rated power dependent OLMCPR multiplier LHGR Linear Heat Generation Rate LHGRFAC(F) Off-rated LHGR thermal limit flow dependent multipliers LHGRFAC(P) Off-rated LHGR thermal limit power dependent multipliers LTSP Rod Block Monitor Low Trip Setpoint MAPFAC(F) Off-rated flow dependent MAPLHGR multiplier MAPFAC(P) Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) Off-rated MCPR flow dependent thermal limit MCPR(P) Off-rated MCPR power dependent thermal limit Page 4 of 54
Exeloin Nuclear - Nuclear Fuels Doe ID: COLR Limerick I, Rev. I I Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with I0)CFR 2.391)
M.ELLLA Maximum Extended Load Line Limit Analysis MSIVOOS Main Steam Isolation Valve Out of Service OLMCPR Operating Limit Minimum Critical Power Ratio OOS Out of Service OPRM Oscillation Power Range Monitor PBDA Period Based Detection Algorithm PLUOOS Power Load Unbalance Out of Service PROOS Pressurc Regulator Out of Service RBM Rod Block Monitor RPTIS Recirculation Pump Trip in Service RPTOOS Recirculation Pump Trip Out of Service SLO Single Loop Operation TBVIS Turbine Bypass Valves in Service TBVOOS Turbine Bypass Valves Out of Service TCV Turbine Control Valve TSV Turbine Stop Valve Page 5 of 54
Exelon Nuclear - Nuclear Fuels Doe II): COLR Limerick 1, Rev. I I Core Operating Limits Report Non-Proprietary Infirmation Submitted in Accordance with 10 CFR 2.390 2.0 General Information This report provides the following cycle-specific paiurneter limits for Limerick Generating Station Unit I Cycle 16:
- Maximum Average Planar Linear Heat Generation Rate (MAPLIHGR)
- Minimum Critical Power Ratio (MCPR)
- ARTS LH-IGR thermal limit multipliers (LHGRFAC(P) or LHIGRFAC(F))
- Rod Block Monitor (RBM) setpoints
- MAPLHGR single loop operation multiplier
- LHGR single loop operation multiplier
- Linear Heat Generation Rate (LHGR)
- Turbine Bypass Valve parameters
- Reactor Coolant System Recirculation Flow Upscale Trips
- Oscillation Power Range Monitor Period Based Detection Algorithm (OPRM PBDA) Trip Setpoints This report is prepared in accordance with Technical Specification 6.9.1.9 of Reference 1. Power and flow dependent limits are listed for various power and flow levels. Lincar interpolation is to be used to find intermedliate values.
The data presented in this report is valid for all licensed operating domains on the operating map, including:
- Maximum Extended Load Line Limit down to the minimum licensed core flow (i.e., 82.9% of rated) during full power operation
- Increased Core Flow (ICF) up to 110% of rated core flow
- Feedwater Heater Out of Service (FWHOOS) up to 60.0°F feedwater temperature reduction at any time during the cycle prior to cycle extension.
Further information on the cycle-specific analyses for Limerick Unit I Cycle 16 and the associated operating domains discussed above is available in Reference 2 and Reference 7.
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Eseloni Nuclear - Nuclear Fuels Doe ID: COLR Limnrcick I, Rev. I I Core Operating Limits Report Non-Proprietary Infornmationi Submitted in Accordance with 10 CFR 2.390 3.0 MAPLHGR Limits 3.1 Technical Specification Section 3.2.1 3.2 Description 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 Tables 3-1 and 3-2. For single loop operation, a multiplier is used, which is shown in Table 3-3. The power and flow dependent multipliers for MAPLIIGR have been removed and replaced with LHGRFAC(P) and LI-IGRFAC(F); therefore, MAPFAC(P) and MAPFAC(F) are equal to 1.0 for all power and flow conditions (Reference 2). LHGRFAC(P) and LHIGRFAC(F) are addressed in Section 5.0.
Table 3-1 MAPLHGR Versus Average Planar Exposure - GE14 (Reference 2)
Table 3-2 MAPLHGR Versus Average Planar Exposure - GNF2 (Reference 2)
Average Planar Exposure MAPLHGR Limit LGWD/ST[) (kW/ft) 0.00 13.78 13.24 13.78 17.52 13.78 60.78 7.50 63.50 6.69 Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier - All Fuel Types (Reference 2)
I SLO Multiplier 0.80 Page 7 of 54
Excloi Nuclear - Nuclear Fuels Doc I): COLR Limerick I, Rev. I I Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CIR 2.390 4.0 MCPR Limits
- 4. I Technical Specification Section 3.2.3 4.2 Description Tables 4-1 and 4-2 are derived from References 2 and 7 and are valid for all Cycle 16 operating domains. Table 4-1 is valid for GE14 fuel and Table 4-2 is valid for GNF2 fuel. Tables 4-1 and 4-2 include treatment of these MCPR limits for all conditions listed in Section 9.0, Modes of Operation.
Limerick Unit I Cycle 16 has a mid-cycle MCPR breakpoint, as defined in Tables 4-1 and 4-2. The BASE, TBVOOS, and RPTOOS MCPR limits include the conservative assumption of simultaneous TC.V and TSV closure during a turbine trip, as discussed in Reference 7. Less restrictive MCPR limits for the BASE DLO Option B condition are provided for a 100 ins or greater delay in the start of TCV closure following a turbine trip. The less restrictive limits may only be used if it is confirmed that the 100 ins or greater delay exists following Digital EHC modification.
ARTS provides for power and flow dependent thermal limit adjustments and multipliers, which allow for a more reliable administration of the MCPR thermal limit. The flow dependent adjustment MCPR(F) is sufficiently generic to apply to all fuel types and operating domains.
The power dependent adjustment MCPR(P) is independent of recirculation pump trip operability.
MCPR(P) and MCPR(F) are independent of Scram Time Option. In addition, there are six sets of power dependent MCPR multipliers (Kp) for use With the BASE, TBVOOS, and RPTOOS conditions, in DLO and SLO operation. The PLUOOS condition is included in the BASE MCPR(P) and MCPR(F) limits and Kp multipliers and is bounded by the TBVOOS limits and multipliers; therefore, no additional adjustments are required for PLUOOS in those operating conditions. The PLUOOS condition has not been analyzed concurrent with the RPTOOS operating condition. Operation in the PLUOOS condition concurrent with the RPTOOS condition requires core thermal power < 55% of rated (Reference 3). Section 7.0 contains the conditions for Turbine Bypass Valve Operability. MCPR(P) and MCPR(F) adjustments for all fuel types are provided in Table 4-3 and 4-4, respectively. The OLMCPR is determined for a given power and flow condition by evaluating the power dependent MCPR and the flow dependent MCPR and selecting the greater of the two.
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E'xelon Nuclear - Nuclear Fuels Doc II): COLR Limerick 1, Rev. I I Core Operating Limits Report Non-Proprietary Information Submitted in Accordanmce with 10 CFR 2.390 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) - GE14 (References 2 n(1 7)
Cycle Exposure SCRAM Time < EOR - 3234 > EOR - 3234 EOOS Combination Option, MWd/ST MWd/ST B 1.39 1.41 BASE B (21 1.38 (' 1.41 (2)
A 1.47 1.49 B 1.46 1.46 BASESW BASE__LO_ A 1.50 1.52 B 1.42 1.44 TBVOOS A 1.51 1.53 TBVOOS SLO' B 1.46 1.47 A 1.54 1.56 B 1.42 1.53 A 1.59 1.70 1.46 1.56 RPTOOS SLO3 B H A 1.62 1.73 Table 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) - GNF2
,(References 2 and 7)
Cycle Exposure SCRAM Time < EOR - 3234 > EOR - 3234 EOOS Combination Option 1 MWd/ST MWd/ST B 1.39 1.41 BASE B 2) 1.38 (21 1.41 (2)
A 1.47 1.49 1.58 1.58 BASE SLO3 B A 1.58 1.58 B 1.42 1.44 A 1.51 1.53 3 B 1.58 1.58 TBVOOS SL0 A 1.58 1.58 B 1.42 1.53 RPOSA 1.59 1.70 RPTOOS SLO3 B 1.58 1.58 A 1.62 1.73 1When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.
2 Limit is only applicable if it is confirmed that a 100 ms or greater delay exists in the start of TCV closure following a turbine trip.
3 For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed two loop value.
However, a minimnum value of 1.46 for GEM4 fuel and 1.58 for GNF2 fuel is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).
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Exelon Nuclear - Nuclear Fuels D)oc II): COI.,I Limerick I, Rev. I I Core Operating Limits Report Non-Proprietary Inforimation Subimitted in Accordance with 10 CFR 2.390 Table 4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp - All Fuel Types (References 2 and 7)
Core Core Thermal Power (% of Rated)
EOOS Flow 0 2S <30 >301 65 185 100 Combination (% of Operating Limit MCPR, Operating Limit MCPR rated) MCPR(P) Multiplier, Kp BASE *60 2.50 2.50 2.40 1.340 1.131 1.067 1.000
> 60 2.75 2.75 2.55
- <60 2.53 2.53 2.43 BASE SLO >60 2.78 2.78 2.58 1.340 1.131 1.067 1.000 TBVOOS *<60 3.25 3.25 2.75 1.340 1.131 1.067 1.000
> 60 3.75 3.75 3.25 TBVOOS *60 3.28 3.28 2.78 1.340 1.131 1.067 1.000 SLO > 60 3.78 3.78 3.28 RPTOOS *60 2.50 2.50 2.40 1.340 1.131 1.067 1.000
> 60 2.75 2.75 2.55 RPTOOS S 60 2.53 2.53 2.43 1.340 1.131 1.067 1.000 SLO > 60 2.78 2.78 2.58 1 1 Table 4-4 Flow Dependent MCPR Limits MCPR(F) - All Fuel Types (References 2 and 7)
Flow MCPR(F)
(%rated) Limit 0.0 1.70 30.0 1.53 79.0 1.25 110.0 1.25 Page 10 of 54
Exelon Nuclear - Nuclear Fuels Doe ID: COIR Limerick 1, Rev. I I Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2-390 5.0 LIFIGR Limits 5.1 Technical Specification Section 3.2.4 5.2 Description The LHGR limit is the product of the exposure dependent LHIGR limit (firom Table 5-1 for U02 ftel rods and Table 5-2 for Gad6linia fuel rods) and the minimum of: the power dependent LHIGR Factor, LI-IGRFAC(P), and the flow dependent LFIGR Factor, LI-IGRFAC(F). For single loop operation, a multiplier is used, which is shown in Table 5-3 and applied in Table 5-5. No further Single Loop Operating multipliers need to be applied to the values in Tables 5-4 and 5-5.
ARTS provides for power and flow dependent thermal limit multipliers, which allow for a more reliable administration of the LHGR thermal limits. There are two sets of flow dependent LIIGR multipliers for dual-loop and single-loop operation. In addition, there are six sets of power dependent LHGR multipliers for use with the BASE, TBVOOS, and RPTOOS conditions, in DLO and SLO operation. The PLUOOS condition is included in the BASE LI-IGRFAC(P) and LUIGRFAC(F) multipliers and is bounded by the TBVOOS multipliers; therefore, no additional adjustments are required for PLUOOS in those operating conditions.
The PLUOOS condition has not been analyzed concurrent with the RPTOOS operating condition. Operation in the PLUOOS condition concurrent with the RPTOOS condition requires core thermal power <55% of rated (Reference 3). Tables 5-4 and 5-5 for LIIGRFAC(P) and LHGRFAC(F), respectively, are applicable to both GE14 and GNF2 fuel types. Section 7.0 contains the conditions for Turbine Bypass Valve Operability. Linear interpolation should be used for points not listed in Appendix A.
Thermal limit monitoring must be performed with the more limiting LHGR limit resulting from the power and flow biased calculation. The LHGRFAC(P) curves are independent of recirculation pmnp trip operability.
Table 5-1 Linear Heat Generation Rate Limits - U0 2 Rods (Reference 5)
Fuel Type LHGR GE14 See Appendix A GNF2 See Appendix A Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods (Reference 5)
Fuel Type LHGR GEM4 See Appendix A GNF2 See Appendix A Page 11 of 54
IExchlo Nuclear - Nuclear Fuels Doe ID: COIR Limerick I, Rev. I I Core Operating Uinits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier - All Fuel Types (Reference 2)
I SLO Multiplier' 1 0.8()
Table 5-4 Power Dependent LHGR Multiplier LHGRFAC(P) - All Fuel Types (Reference 2)
Core Core Thermal Power (% of rated)
EO O S Flow 0_2_,_ <_30 _1 _a_30_1_6-5 Combination (% of 0 25 <30 >30 65 85 100 rated) LHGRFAC(P) Multiplier BASE
- 60 0.485 0.485 0.490 0.750 0.817 0.922 1.000
> 60 0.434 0.434 0.473 BASE SLO
- 60 0.485 0.485 0.490 0.750 0.817 0.922 1.000
> 60 0.434 0.434 0.473 TBVOOS : 60 0.463 0.463 0.490 0.750 0.817 0.922 1.000
> 60 0.352 0.352 0.386 TBVOOS SLO *60 0,463 0.463 0,490 0.750 0.817 0.922 1.000
> 60 0.352 0.352 0.386 RPTOOS *60 0.485 0.485 0.490 0.750 0.817 0.922 1.000
> 60 0.434 0.434 0.473 1
< 60 0.485 0.485 0.490 RPTOOS SLO 0.750 0.817 0.922 1.000
> 60 0.434 0.434 0.473 Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) - All Fuel Types (Reference 2)
Core Flow (% of rated)
EOOS Combination 0 30 44.1 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.506 0.706 0.973 1.000 1.000 Single Loop 0.506 0.706 0.800 0.800 1Applied through Table 5-5 Page 12 of 54
Exelon Nuclear - Nuclear Fuels I)oc ID: COLR Limerick I, Rev. I I Core Operating Limits Report Non-Proprietary Intormation Submitted in Accordance with 1) CFR 2.390 6.0 Control Rod Block Sctpoints 6.1 Technical Specification Sections 3.1.4.3 and 3.3.6 6.2 Description The ARTS Rod Block Monitor provides for power dependent RBM trips. Technical Specification 3.3.6 states control rod block instrumentation channels shall be OPERABLE with their trip selpoints consistent with the values shown in the Trip Sctpoint column of Technical Specification Table 3.3.6-2. The trip setpoints/allowable values and applicable RBM signal filter time constant data are shown in Table 6-I. The Reactor Coolant System Recirculation Flow Upscale Trip is shown in Table 6-2. These setpoints are set high enough to allow fuill utilization of the enhanced ICF domain up to 110% of rated core flow.
Table 6-1 Rod Block Monitor Setpoints' (References 2 and 4)
Power Level Analytical Allowable Nominal Trip Limit Value Setpoint LTSP 123.0% 121.5% 121.5%
ITSP 118.0% 116.5% 116.5%
FITSP 113.2% 111.7% 111.0%
DTSP No Limitation 2.0% 5.0%
Table 6-2 Reactor Coolant System Recirculation Flow Upscale Trip (Reference 4)
Analytical Limit N/A Allowable Value 115.6%
Nominal Trip Setpoint 113.4%
' These setpoints (with Rod Block Monitor filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated RWE MCPR limit of 1.37, which is less than the minimumr cycle OLMCPR.
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Exehon Nuclear - Nuclear Fuels Doc I D: COLR Limerick 1, Rev. I I Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2390 7.0 Turbine Bypass Valve Parameters
- 7. I Technical Specification Sections 3.7.8 and 4.7.8.c 7.2 Description The operability requirements for the steam bypass system are found in Tables 7-I and 7-2. If these requirements cannot be met, the MCPR, MCPR(P) and LI-IGRFAC(P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service (TBVOOS), must be used.
Additional infonnation on the operability of the turbine bypass system can be found in Reference 6.
Table 7-1 Turbine Bypass System Response Time (Reference 3)
Maximum delay time before start of bypass valve opening 0.11 sec following initial turbine inlet valve movement Maximum time after initial turbine inlet valve movement' for bypass valve position to reach 80% of fill flow (includes the 0,31 sec above delay time)
First movement of any TSV or any TCV or generation of the turbine bypass valve flow signal (whichever occurs first)
Table 7-2 Minimum Required Bypass Valves To Maintain System Operability (Reference 3)
Reactor Power No. of Valves in Service P > 25% 7 Page 14 of 54
Exelon Nuclear - Nuclear Fuels D)oe ID: COIAR Limerick I, Rev. I I Core Operating Limiits Report Non-Proprielary hIformation Submitted in Accordance with 10 CFR 2390) 8.0 Stability Protection Sctpoints
- 8. I Tcchnical Specification Section 2.2.1 8.2 Description The Limerick Unit I Cycle 16 OPRM PBDA Trip Setpoints for the OPRM System, are found in Table 8-I. These values are based on the cycle specific analysis documented in Reference 2. The setpoints provided in Table 8-I are bounding for all modes of operation shown in Table 9-1. The setpoints provided in Table 8-2 are acceptable for use in Single Loop Operation. The standard two loop operation OPRM Setpoints specified in Table 8-1 must be implemented prior to restarting the idle pumnp when exiting the SLO condition.
Table 8-1 OPRM PBDA Trip Setpoints (Reference 2)
PBDA Trip Amplitude C Corresponding Maximum Confirmation Count Trip Setting
PBDA Trip Amplitude I Con'esponding Maximum iA Confirmation Count Trip Setting
- 1.15 *< 16 Page 15 of 54
Exclon Nuclear - Nuclear Fuels Doc I): COLR Limerick 1, Rev. II Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10)CF1Z2.390 9.0 Modes of Operation
- 9. I Description The allowable modes of operation arc found in Table 9-1. Operation with PROOS, I MSIVOOS, or I TCViTSV OOS is supported in all modes of operation, provided the restrictions identified in the applicable station procedures arc met. All FOOS options also support the allowance of I TIPOOS. A nominal LPRM calibration interval of 2000 EFPH (2500 EFPH maximum) is supported in accordance with Technical Specification 4.0.2 and 4.3.1.1. All FOOS options allow for 2 inoperable safety relief valves. The Operating Region in Table 9-1 refers to operation on the Power to Flow map with or without FWI-IOOS/FFWTR.
Table 9-1 Modes of Operation (Reference 2)
EOOS Options Operating Region BASE, Option A or B Yes, BASE SLO, Option A or B Yes_
TBVOOS, Option A or B Yes' TBVOOS SLO, Option A or B Yes_
RPTOOS, Option A or B yes_
RPTOOS SLO, Option A or B Yes2 TBVOOS and RPTOOS, Option A or B No TBVOOS and RPTOOS SLO, Option A or B No 1The PLUOOS condition is supported in this mode of operation with no power reduction required.
2 The PLUOOS condition requires core thermal power level < 55% of rated (Reference 3).
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Exehoi Nuclear - Nuclear Fuels Dc II): COLR Limerick I, Rev. II Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 10.0 Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
I. "General Electric Standard Application for Reactor Fuel," NEDE-2401 I -P-A-20, December 2013 and U.S.
Supplement N EDE-2401 I-P-A-20-US, December 2013.
- 2. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," NEDO-32465-A, August 1996.
11.0 References
- 1. "Technical Specifications and Bases for Limerick Generating Station Unit I", Docket No. 50-352, License No. NPF-39.
- 2. "Supplemental Reload Licensing Report for Limerick I Reload 15 Cycle 16", Global Nuclear Fuel Document No. 000N3893-R I-SRLR, Revision I, February 2014.
- 3. "Final Resolved OPL-3 Parameters for Limerick Unit I Cycle 16", Exelon TOD] ES1300017 Rev. 0, October 23, 2013.
- 4. "GE NUMAC PRNM Setpoint Study", Exelon Design Analysis LE-0107, Rev. 2, February 23, 2012.
- 5. "Fuel Bundle Information Report for Limerick I Reload 15 Cycle 16", Global Nuclear Fuel Document No.
000N5028-FBIR-NP, Revision 1, February 2014.
- 6. "Tech Eval Stop Valve Load Limit Documentation", Exelon Document IR 917231 Assignment 7, November 11, 2009.
000N5273-RO, March 10, 2014.
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Exelon Nuclear - Nuclear Fuels Doc II): COI,R limerick I, Rev. II Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Page 18 of 54
Exelon Nuclear - Nuclear FueLs Doc ID: COLR Limerick 1, Rev. II Core Operating Limits Repoil Non-Propiietary Information Submitted in Accordance wilh 10 CFR 2.390 Global Nuclear Fuel GNCF Global Nuclear Fuel A Joint Vanloe d OETozhiba, & Hitachi 000N5028-FBIR-NP Revision 1 February 2014 Non-ProprietaiyInformation - Class I (Public)
Fuel Bundle Information Report for Limerick 1 Reload 15 Cycle 16 Copyright2014 Global Nuclear Fuel - Americas, LLC All Rights Reserved Page 19 of 54
Exclon Nuclear - Nuclear Fuels Doc ID: COLR iimerick 1, Rev. II Core Operating Limits Reporl Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5029-FBIR-NP Reload 15 Class I (Public) Revision I Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF-A) solely for use by Exelon Corporation ("Recipient") in support of the operating license for Limerick Unit I (the "Nuclear Plant").
The information contained in this report (the "Information") is believed by GNF-A to be an accurate and true representation of the licts known by, obtained by or provided to GNF-A at the time this report was prepared.
The only undertakings of GNF-A respecting the Information are contained in the contract between Recipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") and nothing contained in this document shall be construed as amending or modifying the Fuel Contract. The use of the Information for any purpose other than that for which it was intended under the Fuel Contract, is not authorized by GNF-A. In the event of any such unauthorized use, GNF-A neither (a) makes any representation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness of the Information or that such unauthorized use may not infringe privately owned rights, nor (b) assumes any responsibility for liability or damage of any kind which may result from such use of such information.
Information Notice This is a non-proprietary version of the document 000N5028-FBIR-P, Revision 1, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here )).
A.
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Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. I I Core Operating Limits Report Nou-Propiietaity Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I I. Introduction and Summary This report, which supplements the Supplemential Reload Licensing Report, contains thernmal-nmechanical linear heat generation rate (L-IGR) limits f'or the GNF-A fuel designs to be loaded into Limerick I Ifr Cycle 16. These LHGR limits are obtained firom thermal-mechanical considerations only. Approved GNF-A calculation models documented in Reference I were used in performing this analysis.
LHIGR limits as a I'unction of`exposure for each bundle of'the core design are given in Appendix A. The LI-IGR values provided in Appendix A provide upper and lower exposure dependent LHIGR boundaries which envclope ihe actual gadolinia dependent LHGR limits. The LHGRs reported have been rounded to two places past the decimal.
Appendix B contains a description of the fuel bundles. Table B-I contains a summary of bundle-specific information, and the figures provide the enrichment distribution and gadolinium distribution for the fuel bundles included in this appendix. These bundles have been approved for use under the fuel licensing acceptance criteria of Reference I.
Page 21 of 54 Page 3
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. II Core Operating Limits Report Non-Proprietary Infortualion Submitled in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary inllbrmation 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I
- 2. References Ge.,neral Heei'criw: *Slcma'd AI lpliccilio~t~firIR I. 1r tl, NEE-2401 I -P-A-20, [)Dcember 201 31 ind the U.S. Supple*cmnl, N EDE-24() I -I1-A-20-US, Deccmbcr 2013.
Page 22 of 54 Page 4
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. II Core Operating Limits Repoil Non-Proprietary Information Submited in Accordance wvilh 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 00ON5028-FBIR-NP Reinad 15 Class I (Puiblic'! Revision I Appendix A U0 2/Gd Thermal-Mechanical LHGR Limits Bundlc Tl'ypc: GE 14-PI OCNA[3394-15IGZ- 120T- 150-T6-3271 (GEI14C)
Bundle Number: 3271 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft
((
Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft
((
Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Page 23 of 54 Page 5
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick I, Rev. I I Core Operating Limits Report Non-Proprietary Information Submitled in Accordance with 10 CFR 2394)
Limerick Unit I Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 0OCNAB401-13GZ- 120T- 150-T'6-3273 (GE 14C)
Bundle Number: 3273 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft
((
Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 2 GWd/MT (GWd/ST) kW/ft 2 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design R[ I].
Page 24 of 54 Page 6
Exelon Nuclear - Nuclear Fuels D)oc ID: COLR Limerick 1, Rev. II
('ore Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2390 Limerick Unit I Non-Proprictary Inflornation 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I U02 /Gd Thermal-Mechanical LHGR Limits 3undlC Typc: GF 14-P I OCNA [B402-1 3GZ- 120T- 150-T6-3274 (GE I4C)
Bundle Number: 3274 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft rr Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 3 GWd/MT (GWd/ST) kW/ft
(( ___________________
Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design
(( )).
Page 25 of 54 Page 7
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. I I Core Operating L.imits Reporl Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P I OCNAB398-12GZ- 120"1"- 150-T6-3275 (GE I 4C)
Bundle Number: 3275 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 4 SGWd/MT (GWd/ST) kW/ft
((I
_____________________________))
4 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design R ]I-Page 26 of 54 Page 8
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Linerick I, Rev. II Core Operating Limits Report Non-Propiietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary infornmation 000N5028-FBI R-NP Reload 15
- Class I (Public) Revision I UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: iF I4-P10OCNAB394-1I5GZ- 1201'- 150-1"6-3272 (GE 14C)
Bundle Number: 3272 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft S Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design
(( )).
Page 27 of 54 Page 9
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 11 Core Operating Limits Reporl Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: ON F2-P I 0CG21B393-I 0G7.0/2G6.0-120T2-1550-T6-4048 (GN F2)
Bundle Number: 4048 Peak Pellet Exposure UO2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 6 GWd/MT (GWd/ST) kW/ft
((i____________________
_______________________________ ))
6 Bounding gadolinia LHGR limit for all gadolinium conccntrations occurring in this bundle design
[1 1].
Page 28 of 54 Page 10
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. II Core Operating Limits Report Non-Propiietary Information Submitted in Accordance with 10 CFR 2.39.0 Limerick Unit I Non-Proprietary Information 000N5028-FBI R-NP Reload 15 Class I (Public) Revision I UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GN F2- PI 0CG2B404-12G6.0- 100'1"2-150--f6-4044 (ON F2)
Bundle Number: 4044 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 7 GWd/MT (GWd/ST) kW/ft 7 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design
(( ]I-Page 29 of 54 Page I I
Exelon Nuclear - Nuclear Fuels Doc ID: COLR L.imerick 1, Rev. 11 Core Operating Limits Repoil Non-Proplietfry Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Informnation 000N5028-FBI R-NP Reload 15 Class I (Public) Revision I UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GN F2-PIOCG2B404-12G6.0-120T2-150-T6-3643 (G NF2)
Bundle Number: 3643 Peak Pellet Exposure U0 2 LHGR Limit GWd/MNT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWdtST) kW/ft
_____________________ i Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design
(( ))i.
Page 30 of 54 Page 12
Exelon Nuclear - Nuclear Fuels Doc ID: COLR iimerick 1, Rev. I I Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Inlformation 000N5028-FI3IR-NP Reload I 5 (-lass I (Public) Revision I U0 2/Gd Thermal-Mechanical LHGR Limits B3undlC Typc: GN F2-PI 0CG2B387-15GZ- I 2012-150-1'6-4045 (GNF2)
Bundle Number: 4045 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 9 GWd/MT (GWd/ST) kW/ft
((
______________________________ ))
9 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design
[I I].
Page 31 of 54 Page 13
Exclon Nuclear - Nuclear Fuels Doc ID: COI.R L.imerick 1, Rev. II Cove Operating Limits Reporl Non-Proprietai lmnfornmation Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Infonmmation 000N5028-FBIR-NP Reload IS Clas.Is I (Public) . Revision I U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GN F2-P I 0C'G2B388-13GZ- 120T2-150-'1*6-4046 (GN F2)
Bundle Number: 4046 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit "0 GWd/MT (GWd/ST) kW/ft
((
10 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Page 32 of 54 Page 14
E'xelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 1 Core Operating Limits Report Non-Proprietary Information Submitled in Accordance with 10 CFR 2.390 Limerick Unit 1 Non-Proprietary Information 000N5029-FBIR-NP Reload 15 Class I (Public) Revision I UO2lGd Thermal-Mechanical LHGR Limits Bundle Typc: GNF2-P I 0CG2B392-15GZ- 120T2-150-T6-4047 (CiNF2)
Bundle Number: 4047 Peak Pellet Exposure U0 2 LHGR Limit CWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' 1 GWd/MT (GWd/ST) kW/ft
((
_____________________________]1
" Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Page 33 of 54 Page 15
Exelon Nuclear - Nuclear Fuecs Doc [D: COOLR Limerick 1, Rev. II Core Operating Limits Reporl Non-Proplietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit 1 Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-1" I 0CG2B386-l46Z- 120T2-1 50-T6-4272 (GNF2)
Bundle Number: 4272 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' 2 GWd/MT (GWd/ST)- kW/ft
((___________________1 32 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design If fl.
Page 34 of 54 Page 16
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. I I Core Operating Limits Report Non-Proprie(ary lnfornation Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Inlformation 000N5028-FBIR-NP Reload Is Class I (Ptblicl Revision I UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P I 0CG2B387-13(i7.0-120T2-150-T'6-4274 (ON F2)
Bundle Number: 4274 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/S'T) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' 3 GWd/MT (GWd/ST) kW/ft t((
'* Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Page 35 of 54 Page 17
Exelon Nuclear - Nuclear Fuels Doc ID: COLR L.imerick 1, Rev. I I
('ore Operating Limits Report Non-Proprietary Information Submitted in Accordance wifh 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I UO2 Gd Thermal-Mechanical LHGR Limits Bundle Type: GN F2-P IOCG2 B400-13Gi7.0-120T2-150-T6-4275 (GN F2)
Bundle Number: 4275 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 14 GWd/MT (GWd/ST) kW/ft
((I 14 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design 11 1i.
Page 36 of 54 Page 18
Exeloti Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. I I Core Operating Limits Report Non-Proprietary Inlormation Submitted in Accordance with 10 (FR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-FBI R-NP Reload 15 Class I (Public) Revision I UO21Gd Thermal-Mechanical LHGR Limits Bundle Type: GN F2- PI 0CG2B387-12G7.0-120'T'2-150-'1"6-4273 (GN F2)
Bundle Number: 4273 Peak Pellet Exposure UO 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit's GWd/MT (GWd/ST) kW/ft
((l
'5 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design
(( )).
Page 37 of 54 Page 19
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. I I Core Operating Limits Report Non-Proprietary Information Submilled in Accordance willh 10 CFR 2.390 Limerick Unit 1 Non-Proprictary Inflormation 000N5028-FIBIR-NP Reload 15 Class I (Public) Revision I Appendix B .
Fuel Bundle Information Table B-I Bundle Specific Information Bundle Enrichment Weight Weight Max Exposure Fuel of U0 2 of U ky at at Max k, Bundle Number (wt% U-235) 20 0C GWd/MT (kg) (kg) 16 (GWd/ST)
GE14-P IOCNAB394-15GZ-120"1'-150-T6-3271 (GE14C)
GEI4-PI 0CNAB40I- I13GZ-120T-150-T6-3273 (GEI4C)
GE 14-P I OCNAB402-13GZ-120T- 150-T6-3274 (GE 14C)
GEI4-PIOCNAB398-12GZ- 3275 120T- I 50-T6-3275 (GE I4C)
GE I4-P I OCNAB394-15GZ-120T-150-T6-3272 (GE14C)
GNF2-PI0CG2B393-I0G7.0/2G6.0-120T2-150-T6- 4048 4048 (GNF2)
GNF2-P 10CG2B404-12G6 .0-100T2-150-T6-4044 (GNF2)
GNF2-P 10CG2B404-12G6.0-120T2-150-T6-3643 (GNF2)
GNF2-P I0CG2B387-15GZ-120T2-150-T6-4045 (GNF2)
GNF2-P1OCG2B388-13GZ-120T2-150-T6-4046 (GNF2)
GNF2-PI 0CG2B392-15GZ-120T2-150-T6-4047 (GNF2)
GNF2-P 10CG2B386-14GZ-120T2-150-T6-4272 (GNF2)
GNF2-Pl0CG2B387-13G7.0-120T2-150-T6-4274 (GNF2) 16 Maximum lattice k. for the most reactive uncontrolled state plus a (( )) adder for uncertainties.
Page 38 of 54 Page 20
FLxelon Nuclear - Nuclear Fuels Doc ID: C'OLR Literick I, Rev. I I Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CI.R 2.390 Limerick Unit I Non-Proprietary Inlformation 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I Table B-I Bundle Specific Information Bundle Enrichment Weight Weight Max Exposure Fuel Fue BudleEnrchmntOf U.02 Of U Ic 0
at at Max kc-,
Bundle Number (wt U-235) oU o 20 C GWd/MT (kg) (kg) , (GWd/ST)
(GNF2-P I OCG2 B400-13M7.0-12012-150-T6-4275 (GNF2)
(vNF2-P10CG2B387-12G7.0-120T2-150-T'6-4273 (GNF2)
Page 39 of 54 Page 21
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Uinierick 1. Revi. I I Core Operating Lhniis Report Non-Proprietary Information Submitted in Accoilance %iOlh 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I ff
))
Figure B-I Enrichment and Gadolinium Distribution for EDB No. 3271 Fuel Bundle GE14-PIOCNAB394-15GZ-120T-150-T6-3271 (GE14C)
Page 40 of 54 Page 22
Exelon Nuclear - Nuclear Fuels D)oc ID: COLR Limerick 1, Rev. 11
('ore Operating Limits Report Non-Proprietary Inflrmation Submitled in Accordance wvith 10 ('FR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I 11 Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 3273 Fuel Bundle GEl4-PIOCNAB401-13GZ-120T-150-T6-3273 (GE14C)
Page 41 of 54 Page 23
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. II Core Operating Limits Reporl Non-Proprietary Informallon Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-F'B IR-N P Reload 15 Class I (Public) Revision I Figure B-3 Enrichment and Gadolinium Distribution for EDB No. 3274 Fuel Bundle GEl4-PIOCNAB402-13GZ-120T-150-T6-3274 (GEl4C)
Page 42 of 54 Page 24
Exelon Nuclear - Nuclear Fuels .Doc ID: COLR Limerick .1,Rev. II Core Operating Limits Reporl Non-Proprielanr Information Submitted in Accordance wvith 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I i1 Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 3275 Fuel Bundle GEl4-PIOCNAB398-12GZ-120T-150-T6-3275 (GEl4C)
Page 43 of 54 Page 25
Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 11 Core Operating Limits Repoil Non-Proprietary Inforlmation Submitted iln Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-F'BIR-NP Reload 15 Class I (Public) Revision I
((
))
Figure B-5 Enrichment and Gadolinium Distribution for EDB No. 3272 Fuel Bundle GEl4-P1OCNAB394-15GZ-120T-150-T6-3272 (GEl 4C)
Page 44 of 54 Page 26
Exclon Nuclear - Nuclear Fuels Doc ID: COLR L.imerick 1, Rev. 1 Core Operating Limits Report Non-l'ropiietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 00ON5029-FBIR-NP Reload IS Class I (lPublic) Revision I
))
Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 4048 Fuel Bundle GNF2-PIOCG2B393-10G7.0/2G6.0-120T2-150-T6-4048 (GNF2)
Page 45 of 54 Page 27
E~xelon Nuclear - Nuclear Fuels Doc liD: COLR Limerick 1, Rev. II Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I H[
))
Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 4044 Fuel Bundle GNF2-PIOCG2B404-12G6.0-100T2-150-T6-4044 (GNF2)
Page 46 of 54 Page 28
EAelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. II Core Operating Limits Reporl Non-Proprietary Inlfrmation Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 00ONS02-FBIR-NP Reload 15 Class I (Public) Revision I
[F Figure B-8 Enrichment and Gadolinium Distribution for EDB No. 3643 Fuel Bundle GNF2-PI0CG2B404-12G6.0-120T2-150-T6-3643 (GNF2)
Page 47 of 54 Page 29
Exelon Nuclear - Nuclear Fuels Doc ID: COI.R Limerick 1, Rev. 1I
('ore Operating itmits Report Non-Proprielan" Informalion Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Infonriation 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I 1I 11 Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 4045 Fuel Bundle GNF2-PIOCG2B387-15GZ-1 20T2-150-T6-4045 (GNF2)
Page 48 of 54 Page 30
xelon Nuclear - Nuclear Fuel% Doc ID: COLR Limerick 1, Rev. I I Core Operating Limils Report Non-Propoietary Informalion Submitted in Accordance nith 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I
((
1]
Figure B-10 Enrichment and Gadolinium Distribution for EDB No. 4046 Fuel Bundle GNF2-PI 0CG2B388-13GZ-120T2-150-T6-4046 (GNF2)
Page 49 of 54 Page 31
Exclon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. I I Core Operating Limits Report Non-Proprietary Inforantion Submitled in Accordance wiith 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5029-FBIR-NP Reload 15 Class I (Public) Revision I f[
1]
Figure B-I 1 Enrichment and Gadolinium Distribution for EDB No. 4047 Fuel Bundle GN F2-PI 0CG2B392-1 5GZ-120T2-150-T6-4047 (GNF2)
Page 50 of 54 Page 32
Exclon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1. Rev. 11 Core Operating Limits Report Non-Proprielary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Infornation 000N5028-FBIR-NP Reload 15 Class I (Public) Revision I If
))
Figure B-12 Enrichment and Gadolinium Distribution for EDB No. 4272 Fuel Bundle GNF2-PI 0CG2B386-14GZ- I2OT2-150-T6-4272 (GNF2)
Page 51 of 54 Page 33
Exelon Nuclear - Nuclear Fuels i)oc ID: COLR limerick 1, Rev. 11 Core Operating Limits Report Non-Proprietary Iniormation Submilted in Accordance with 10 (FR 2.390 Limerick Unit 1 Non-Proprietary Information 000N5028-FBIR-NP Reload 15 C(ass I (PulieHh Revision I
[1 1]
Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 4274 Fuel Bundle GNF2-PIOCG2B387-13G7.0-120T2-150-T6-4274 (GNF2)
Page 52 of 54 Page 34
Exeloh Nuclear - Nuclear Fuels Doc ID: COLR Limnerick 1, Rev. 11 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 00ON5028-FBIR-NP Reload 15 Class I (Public) Revision I Figure B-14 Enrichment and Gadolinium Distribution for EDB No. 4275 Fuel Bundle GNF2-PI OCG2B400-13G7.0-120T2-150-T6-4275 (GNF2)
Page 53 of 54 Page 3 5
Exelon Nuclear - Nuclear Fuels i)oc IID: COLR Limerick .1,Rev. II Core Operating Linmits Repoil Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information 000N5028-FBIR-NP Reload 15 Class I (Publiel Revision I 11 Figure B-15 Enrichment and Gadolinium Distribution for EDB No. 4273 Fuel Bundle GNF2-P10CG2B387-12G7.0-120T2-150-T6-4273 (GNF2)
Page 54 of 54 Page 36