ML13123A035
| ML13123A035 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/05/2013 |
| From: | Holmes M Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13123A035 (18) | |
Text
ENCLOSURE 3 UNIT 2 COLR FOR CYCLE 13 REV. 8 WITH APPENDIX A PROPRIETARY CLASS I (PUBLIC)
Exelon Nudear - Nudear Fuels Core Operating LinUis Report Non-Ptopnetaly Intonmatian Submited In Accrdance w(h 10 CFR 2.390 COLR Umentck 2 Rev. 8 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 2 RELOAD 8i, CYCLE 13 (This is a complete re-write; no annotations are used.)
Date: ____
Reviewed By: Date: L-I0-/,3 Independent Reviewer Reviewed By:.
L.Sanh catot Enginacernug Reviewed By:e- I a 5 Date:
T. Bement E*ginering Safety Analysis Approved By: Daft: 4/8/13 J. i. Tusar Manager - BWR Design (GNF)
Station Qualified Reviewed By: Date:
L Korbeil Station Qualified Reviewer page lof 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 Table of Contents Page 1.0 Terms and Definitions 4 2.0 General Information 6 3.0 MAPLHGR Limits 7 4.0 MCPR Limits 8 5.0 LHGR 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 15 10.0 Methodology 16 11.0 References 16 Appendix A 17 Page 2 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 List of Tables Page TABLE 3-1 MAPLHGR versus Average Planar Exposure - GE 14 7 TABLE 3-2 MAPLHGR versus Average Planar Exposure - GNF2 7 TABLE 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier - All Fuel Types 7 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) - All Fuel Types 9 TABLE 4-2 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp - All Fuel Types 10 TABLE 4-3 Flow Dependent MCPR Limits MCPR(F) - All Fuel Types 10 TABLE 5-1 Linear Heat Generation Rate Limits - U0 2 Rods 11 TABLE 5-2 Linear Heat Generation Rate Limits - Gad Rods 11 TABLE 5-3 LHGR 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 9-1 Modes of Operation 15 Page 3 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 1.0 Terms and Definitions ARTS APRM, RBM, and Technical Specification Improvement Program BASE A case analyzed with Turbine Bypass System in service and Recirculation Pump Trip in service and Feedwater Temperature Reduction allowed (FFWTR includes FWHOOS or final feedwater temperature reduction) and PLUOOS allowed at any point during the cycle in Dual Loop mode.
DLO Dual Loop Operation DTSP Rod Block Monitor Downscale Trip Setpoint EOOS Equipment Out of Service EOR 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 FWHO(OS Feedwater Heaters Out of Service HTSP Rod Block Monitor High Trip Setpoint ICF Increased Core Flow ITSP Rod Block Monitor Intermediate Trip Setpoint Kp Off-rated power dependent OLMCPR multiplier LHGR Linear Heat Generation Rate LHGRF?AC(F) ARTS LHGR thermal limit flow dependent multipliers LHGRF?AC(P) ARTS LHGR thermal limit power dependent multipliers LTSP Rod Block Monitor Low Trip Setpoint MAPFA*C(F) Off-rated flow dependent MAPLHGR multiplier MAPFA*C(P) Off-rated power dependent MAPLHGR multiplier MAPLEiGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR( F) Off-rated flow dependent OLMCPR multiplier MCPR( P) Off-rated power dependent OLMCPR multiplier Page 4 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 MELLLA Maximum Extended Load Line Limit Analysis OLMCPR Operating Limit Minimum Critical Power Ratio OPRM Oscillation Power Range Monitor PBDA Period Based Detection Algorithm PLUOOS Power Load Unbalance 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 Page 5 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 2.0 General Information This report provides the following cycle-specific parameter limits for Lime:rick Generating Station Unit 2 Cycle 13:
" Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
- Minimum Critical Power Ratio (MCPR)
" Off-rated OLMCPR adjustments (MCPR(P) or MCPR(F))
" Off-rated OLMCPR multipliers (K(P))
- Off-rated LHGR multipliers (LHGRFAC(P) or LHGRFAC(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. Preparation of this report was performed in accordance with Exelon Nuclear, Nuclear Fuels T&RM NF-AB-120-3600.
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 82.9% 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 60'F feedwater temperature reduction at any time during the cycle prior to cycle extension.
Further information on the cycle specific analyses for Limerick 2 Cycle 13 and the associated operating domains discussed above is available in Reference 2.
Page 6 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 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 MAPLHGR have been removed and replaced with LHGRFAC(P) and LHGRFAC(F); therefore, MAPFAC(P) and MAPFAC(F) are equal to 1.0 for all power and flow conditions (Reference 2). LHGRFAC(P) and LHGRFAC(F) are addressed in Section 5.0.
TABLE 3-1 MAPLHGR versus Average Planar Exposure - GE14 (Reference 2)
Average Planar Exposure MAPLHGR Limit (GWD/ST) (kW/ft) 0.0 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 TABLE 3-2 MAPLHGR versus Average Planar Exposure - GNF2 (Reference 2)
Average Planar Exposure MAPLHGR Limit (GWD/ST) (kW/ft) 0.0 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)
SLO Multiplier 0.80 1 Page 7 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description Table 4-1 is derived from Reference 2 and is valid for all fuel types and all operating domains. Table 4-1 includes treatment of these MCPR limits for all conditions listed in Section 9.0, Modes of Operation.
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 BASE, TBVOOS, RPTOOS, DLO and SLO conditions. 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 are provided in Tables 4-2 and 4-3. 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.
Page 8 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) - All Fuel Types (Reference 2)
SCRAM Cycle Exposure Time < EOR - 4827 __EOR - 4827 EOOS Combination Option°') MWd/ST MWd/ST B 1.47(2) 1.47(2)
BASE A 1.47(2) 1.47(2)
B 1.58 1.58 BASE SLOt ) A 1.58 1.58 B 1.47(2) 1.47(2)
TBVOOS A 1.47(2) 1.48 B 1.58 1.58 TBVOOS SLO(3 ) A 1.58 1.58 B 1.47(2) 1.47(2)
RPTOOS A 1.55 1.58 B 1.58 1.58 RPTOOS SLO(3 ) A 1.58 1.61 When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.
2 Value is set by the Loss of Stator Cooling (LOSC) event.
3 For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed two loop value.
However, a minimum value of 1.58 is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event.
Page 9 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 TABLE 4-2 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp - All Fuel Types (Reference 2)
Core Core Thermal Power (% of Rated)
EOOS Flow 0 25 <30 30 65 85 100 Combinatin rated) MCPR(P) Operating Limit MCPR 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 BaeSL < 60 2.53 2.53 2.43 Base SLO >!_60 60 2.78 2.78 2.78 2.78 2.58 2.58 1.340 1.131 1.067 1.000
< 60 3.25 3.25 2.75 TBVOOS > 60
> 60 3.75 3.75 3.75 3.75 3.25 3.25 1.340 1.131 1.067 1.000
< 60 3.28 3.28 2.78 TBVOOSSLO 3 1.340 1.131 1.067 1.000
> 60 3.78 3.78 3.28 RPTOO < 60
>10.340.7 2.50 2.50 2.40 25 1.131 1.067 1.000
- 56 2.53 2.53 2.43 RPTOOS SLO > 60 2.78 2.78 2.58 1.340 _____
1.131 1.067 1.000 TABLE 4-3 Flow Dependent MCPR Limits MCPR(F) - All Fuel Types (Reference 2)
Flow MCPR(F)
(% rated) Limit 0.0 1.70 30.0 1.53 79.0 1.25 110.0 1.25 Page 10 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 5.0 LHGR Limits 5.1 Technical Specification Section 3.2.4 5.2 Description The LHGR limit is the product of the exposure dependent LHGR limit (from Table 5-1 for U0 2 fuel rods and Table 5-2 for Gadolinia fuel rods) and the minimum of: the power dependent LHGR Factor, LHGRFAC(P), and the flow dependent LHGR Factor, LHGRFAC(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 LHGR 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, RPTOOS, DLO and SLO conditions. The PLUOOS condition is included in the BASE LHGRFAC(P) and LHGRFAC(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). Section 7.0 contains the conditions for Turbine Bypass Valve Operability. The LHGR multipliers are shown in Tables 5-4 and 5-5. 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 pump 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 - Gad Rods (Reference 5)
Fuel Type LHGR GEl4 See Appendix A GNF2 See Appendix A Page 11 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 TABLE 5-3 LHGR Single Loop Operation (SLO) Multiplier - All Fuel Types (Reference 2)
SLO Multiplier' 0.80 TABLE 5-4 Power Dependent LHGR Multiplier LHGRFAC(P) - All Fuel Types (Reference 2)
Core Core Thermal Power (% of rated)
E OO S F lo w 0_2 5_<_3 0_3 0_1_6 5_ 1_ 85_ 1_ 100 Combination (% of 0 25 <30 Ž 30 65 85 100 rated) LHGRFAC(P) Multiplier BASE
- 60 0.48 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 0.81.7 0.922 1.000
> 60 0.434 0.434 0.473 TBVOOS < 60 0.463 0.463 0.490 0.750 0.81.7 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
- 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 44.082 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 1. 0.800 Applied through Table 5-5 Page 12 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 6.0 Control Rod Block Setpoints 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 setpoints consistent with the values shown in the Trip Setpoint 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 6-1. The Reactor Coolant System Recirculation Flow Upscale Trip is shown in Table 6-2.
These setpoints are set high enough to allow full 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%
HTSP 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 1.32, which is less than the minimum cycle OLMCPR.
Page 13 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 7.0 Turbine Bypass Valve Parameters 7.1 Technical Specification Section 3.7.8 and 4.7.8.c 7.2 Description The operability requirements for the steam bypass system are found in Tables 7-1 and 7-2. If these requirements cannot be met, the MCPR, MCPR(P) and LHGRFAC(P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service (TBVOOS), must be used.
Additional information 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 following generation of the turbine bypass valve flow signal
/ 0.11 sec Maximum time after generation of a turbine bypass valve flow signal for bypass valve position to reach 80% of full flow 0.31 sec (includes the above delay time)
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 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.1 8.2 Description The Limerick 2 Cycle 13 OPRM PBDA Trip Setpoints for the OPRM System are found in Table 8-
- 1. These values are based on the cycle specific analysis documented in Reference 2. The setpoints provided in Table 8-1 are bounding for all modes of operation shown in Table 9-1.
TABLE 8-1 OPRM PBDA Trip Setpoints (Reference 2)
PBDA Trip Amplitude CCorresponding Maximum I Confirmation Count Trip Setting
- 1.12 *< 14 9.0 Modes of Operation TABLE 9-1 Modes of Operation (Reference 2)
EOOS Options Operating Region BASE, Option A or B Yes2 BASE SLO, Option A or B Yes 2 TBVOOS, Option A or B Yes 2 TBVOOS SLO, Option A or B Yes 2 RPTOOS, Option A or B Yes 3 RPTOOS SLO, Option A or B Yes 3 TBVOOS and RPTOOS, Option A or B No TBVOOS and RPTOOS SLO, Option A or B No 1Operating Region refers to operation on the Power to Flow map with or without FFWTR/FWHOOS.
2 The PLUOOS condition is supported in this mode of operation with no power reduction required.
3 The PLUOOS condition requires core thermal power level < 55% of rated (Reference 3).
Page 15 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 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 document:
- 1. "General Electric Standard Application for Reactor Fuel", Global Nuclear Fuel Document, NEDE-24011 -P-A-19, May 2012 and the U.S. Supplement NEDE-2401 1-P-A-19-US, May 2012.
- 2. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications", GENE Document, NEDO-32465-A, August 1996.
11.0 References
- 1. "Technical Specifications and Bases for Limerick Generating Station Unit 2", Docket No. 50-353, License No. NPF-85, Exelon Document.
- 2. "Supplemental Reload Licensing Report for Limerick Unit 2 Reload 12 Cycle 13", Global Nuclear Fuel Document No. 0000-0157-6733-SRLR, Rev. 2, March 2013.
- 3. "Final Resolved OPL-3 Parameters for Limerick Unit 2 Cycle 13", Exelon TODI ES1200015 Rev. 0, November 7, 2012.
- 4. "GE NUMAC PRNM Setpoint Study", Exelon Design Analysis LE-0 107, Rev. 2, February 23, 2012.
- 5. "Fuel Bundle Information Report for Limerick Unit 2 Reload 12 Cycle 13", Global Nuclear Fuel Document No. 0000-0157-6733-FBIR-NP, Rev. 0, February 2013.
- 6. "Tech Eval Stop Valve Load Limit Documentation", Exelon Document IR 917231 Assignment 7, November 11, 2009.
Page 16 of 17
Exelon Nuclear - Nuclear Fuels Core Operating Limtis Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 2 Rev. 8 Appendix A (38 pages)
Page 17 of 17