ML091560522
| ML091560522 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/05/2009 |
| From: | David Helker Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML091560522 (17) | |
Text
Exelon Nuclear www.exeloncorp.com 200 Exelon Way Nuclear Kennett Square, PA 19348 TS 6.9.1.12 June 5, 2009 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 10, Cycle 11, Revision 6 Enclosed is a copy of the revised Core Operating Limits Report (COLR) for Limerick Generating Station (LGS), Unit 2, Reload 10, Cycle 11, Revision 6. Revision 6 of this report is being revised to add additional conditions concerning the turbine bypass valve and recirculation pump trip functions.
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.
Respectfully, David P. Helker Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachment cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, LGS USNRC Project Manager, LGS R. R. Janati, Bureau of Radiation Protection
Exelon Nuclear Fuels Doc 10: COLR Limerick 2, Rev. 6 CORE OPERATING LIl\nTS REPORT FOR LIl\'IERICK GENERATING STATION UNIT 2 RELOAD 10, CYCLE 11 Prepared By: Date: 5"/;1/09' Reviewed By: ftw.lJffR ~" ee-l.a G. Rubinaccio Date: 5.Izt/09 Independent Reviewer tI~ !J/27J09 Approved By: Date:
J. J. Tusar Manager - BWR Design (GNF)
Station Qualified Reviewed By: 2JJ~- Robert Potter Date: e>R1k; Station Qualified Reviewer Page 1 of 16
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 Table of Contents Page 1.0 Terms And Definitions 4 2.0 General Information 5 3.0 MAPLHGR Limits 6 4.0 MCPRLimits 7 5.0 Linear Heat Generation Rate Limits 10 6.0 Control Rod Block Setpoints 13 7.0 TmbineByp~sVillveParmn~e~ 14 8.0 Stability Protection Setpoints 15 9.0 Modes Of Operation 15 10.0 Methodology 16 11.0 References 16 Page 2 of 16
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 List of Tables Page TABLE 3-1 MAPLHGR Versus Average Planar Exposure 6 TABLE 3-2 MAPLHGR Single Loop Operation (SLO) Reduction Factor 6 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 8 TABLE 4-2 Power Dependent MCPR Limit Adjustments and Multipliers 9 TABLE 4-3 Flow Dependent MCPR Limits MCPR(F) 9 TABLE 5-1 Linear Heat Generation Rate Limits for UO z Rods 10 TABLE 5-2 Linear Heat Generation Rate Limits for Gad Rods 11 TABLE 5-3 Linear Heat Generation Rate Limits for Gad Rods 11 TABLE 5-4 LHGR Single Loop Operation (SLO) Reduction Factor 11 TABLE 5-5 Power Dependent LHGR Multiplier LHGRFAC(P) 12 TABLE 5-6 Flow Dependent LHGR Multiplier LHGRFAC(F) 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 of16
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 1.0 Terms And Definitions ARTS APRM, RBM, and Technical Specification Improvement Program BASE CASE A case analyzed with Turbine Bypass System in service and Recirculation Pump Trip in service and Feedwater Temperature Reduction allowed (FFWTR includes feedwater heater OOS or final feedwater temperature reduction) at any point during the cycle in Dual Loop mode.
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 3458 MWth 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 Trip Setpoint ICF Increased Core Flow ITSP Rod Block Monitor Intermediate Trip Setpoint LHGR Linear Heat Generation Rate LHGRFAC(F) ARTS LHGR thermal limit flow dependent multipliers LHGRFAC(P) ARTS LHGR thermal limit power dependent multipliers LTSP Rod Block Monitor Low Trip Setpoint MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) ARTS MCPR flow dependent thermal limit MCPR(P) ARTS MCPR power dependent thermal limit MELLLA Maximum Extended Load Line Limit Analysis OLMCPR Operating Limit Minimum Critical Power Ratio OPRMPBDA Oscillation Power Range Monitor Period Based Detection Algorithm RPTIS Recirculation Pump Trip In Service Page 4 of16
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 RPTOOS Recirculation Pump Trip Out of Service SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation TBVIS Turbine Bypass Valves In Service TBVOOS Turbine Bypass Valves Out of Service 2.0 General Information This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 2 Cycle 11:
- Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
- Minimum Critical Power Ratio (MCPR)
- Rod Block Monitor (RBM) setpoints
- MAPLHGR single loop operation reduction factor
- LHGR single loop operation reduction factor
- Linear Heat Generation Rate (LHGR)
- Turbine Bypass Valve parameters
- Reactor Coolant System Recirculation Flow Upscale Trips
- Oscillation Power Range Monitor Period Based Detection Algorithm Trip Setpoints These values have been determined using NRC-approved methodology (Reference 6), 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 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 81 % ofrated 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 11 and the associated operating domains discussed above is available in References 2 and 10.
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Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 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) ofeach fuel type as a function ofaverage planar exposure is given in Table 3-1 (Reference 2). The limiting MAPLHGR value is the same for all fuel types in the Limerick Unit 2 Cycle 11 core. For single loop operation, a reduction factor is used which is shown in Table 3-2 (Reference 2). MAPFAC(P) and MAPFAC(F) are 1.0 for all power and flow conditions. The power and flow dependent multipliers for MAPLHGR have been removed and replaced with LHGRFAC(P) and LHGRFAC(F) (See Reference 3). LHGRFAC(P) and LHGRFAC(F) are addressed in Section 5.0.
TABLE 3-1 MAPLHGR Versus Average Planar Exposure All Fuel Types (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 Single Loop Operation (SLO) Reduction Factor (Reference 2)
SLO Reduction Factor I 0.80 Page 6 of16
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description Table 4-1 is derived from the References 2 and 10 analyses and is valid for all Cycle 11 fuel types and operating domains. Table 4-1 includes treatment of these MCPR limits for SLO. Bounding MCPR values are also provided for RPTOOS and/or TBVOOS. These three options represent the Equipment Out of Service conditions.
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 (Reference 2). In addition, there are eight sets of power-dependent MCPR multipliers for use with the TBVIS, TBVOOS, RPTIS, RPTOOS, Dual Loop Operation and SLO conditions (References 2, 3, 9 and 10). Section 7.0 contains the conditions for Turbine Bypass Valve Operability. These adjustments are provided in Table 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. The MCPR(P) values are independent of recirculation pump trip operability (Reference 3).
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Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)l (References 2 and 10)
SCRAM Cycle Exposure Time < EOR-2700 2:; EOR-2700 EOOS Combination Option 2 MWd/ST MWd/ST B 1.34 1.39 BASE A 1.37 1.42 B 1.44(3) 1.44(3)
BASESLO A 1.44(3) 1.44 B 1.37 1.43 TBVOOS A 1.40 1.46 B 1.44(3) 1.45 TBVOOSSLO A 1.44(3) 1.48 B 1.40 1.47 RPTOOS A 1.51 1.64 B 1.44(3) 1.49 RPTOOS SLO A 1.53 1.66 B 1.43 1.50 RPTOOS TBVOOS A 1.54 1.67 RPTOOS TBVOOS B 1.45 1.52 SLO A 1.56 1.69 1 This table is valid for all Cycle 11 fuel types.
2 When Tau does not equal 0 or 1, detennine OLMCPR via linear interpolation.
3 OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure (Reference 2)
Page 8 of 16
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 TABLE 4-2 Power Dependent MCPR Limit Adjustments And Multipliers (References 2, 3, 9 and 10)
Core Core Thermal Power (0/0 of Rated)
Flow 0 25 <30 >30 45 60 100 EOOS Combination (% of Operating Limit MCPR rated) MCPR(P)
Multiplier, Kp
<60 2.66 2.66 2.44 Base 1.481 1.280 1.150 1.000
>60 3.39 3.39 2.93
<60 2.68 2.68 2.46 Base SLO 1.481 1.280 1.150 1.000
>60 3.41 3.41 2.95
<60 2.66 2.66 2.44 RPTOOS 1.481 1.280 1.150 1.000
>60 3.39 3.39 2.93
<60 2.68 2.68 2.46 RPTOOSSLO 1.481 1.280 1.150 1.000
>60 3.41 3.41 2.95
<60 3.07 3.07 2.63 TBVOOS 1.481 1.280 1.150 1.000
>60 4.54 4.54 3.77
<60 3.09 3.09 2.65 TBVOOSSLO 1.481 1.280 1.150 1.000
>60 4.56 4.56 3.79
<60 3.07 3.07 2.63 RPTOOS TBVOOS 1.481 1.280 1.150 1.000
>60 4.54 4.54 3.77 RPTOOSTBVOOS <60 3.09 3.09 2.65 1.481 1.280 1.150 1.000 SLO >60 4.56 4.56 3.79 TABLE 4-3 Flow Dependent MCPR Limits MCPR(F)
(Reference 2)
Flow MCPR(F)
(%) rated) Limit 30.0 1.53 79.0 1.25 110.0 1.25 Page 9 of16
Kxelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 5.0 Linear Heat Generation Rate Limits 5.1 Technical Specification Section 3.2.4 5.2 Description The LHGR limit is the product ofthe exposure dependent LHGR limit (from Table 5-1 for V02 fuel rods and Tables 5-2 and 5-3 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 reduction factor is used, which is shown in Table 5-4 (Reference 2).
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 LGHR multipliers for dual-loop and single-loop operation (References 2 and 5). In addition, there are eight sets of power-dependent LHGR multipliers for use with the TBVIS, TBVOOS, RPTIS, RPTOOS, Dual Loop Operation and SLO conditions (References 2,3,9 and 10).
Section 7.0 contains the conditions for Turbine Bypass Valve Operability. The LHGR multipliers are shown in Tables 5-5 and 5-6.
Thermal limit monitoring must be performed with the more limiting LHGR limit resulting from the power- and flow-biased calculation. The LHGRFAC(P) values are independent of recirculation pump trip operability (Reference 3).
TABLE 5-1 Linear Heat Generation Rate Limits for U02 Rods*
(Reference 8)
Peak Pellet Exposure LHGR Limit (kW1ft)
(GWd/ST) 0.00 13.40 14.51 13.40 57.61 8.00 63.50 5.00 1 Linear interpolation should be used for points not listed in Table 5-1. The values listed in Table 5-1 are limiting for all bundle types.
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Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 TABLE 5-2 Linear Heat Generation Rate Limits for Gad Rods 1 Bundle Types 2950, 2951, 2952, 2953, 2954, 2955, 2956, 2832, 2833, 3159, 3160 and 3161 (Reference 8)
Peak Pellet Exposure LHGR Limit (kW/ft)
(GWd/ST) 0.00 11.76 12.08 11.76 54.21 7.02 59.98 4.39 TABLE 5-3 Linear Heat Generation Rate Limits for Gad Rods l Bundle Types 3157 and 3158 (Reference 8)
Peak Pellet Exposure LHGR Limit (kW/ft)
(GWd/ST) 0.00 12.00 12.17 12.00 54.59 7.16 60.39 4.48 TABLE 5-4 LHGR Single Loop Operation (SLO) Reduction Factor (Reference 2)
I SLO Reduction Factor 2 I 0.80 1 Linear interpolation should be used for points not listed in Tables 5-2 and 5-3.
2 Applied through Table 5-6 Page 11 of16
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 TABLE 5-5 Power Dependent LHGR Multiplier LHGRFAC(p)
(References 2, 3, 9 and 10)
Core Core Thermal Power (% of rated)
Flow EOOS Combination 0 25 <30 >30 100 (0/0 of rated) LHGRFAC(P) Multiplier
<60 0.485 0.485 0.490 Base 0.634 1.000
>60 0.434 0.434 0.473
<60 0.485 0.485 0.490 Base SLO 0.634 1.000
>60 0.434 0.434 0.473
<60 0.485 0.485 0.490 RPTOOS 0.634 1.000
>60 0.434 0.434 0.473
<60 0.485 0.485 0.490 RPTOOS SLO 0.634 1.000
>60 0.434 0.434 0.473
<60 0.463 0.463 0.490 TBVOOS 0.634 1.000
>60 0.352 0.352 0.386
<60 0.463 0.463 0.490 TBVOOSSLO 0.634 1.000
>60 0.352 0.352 0.386
<60 0.463 0.463 0.490 RPTOOS TBVOOS 0.634 1.000
>60 0.352 0.352 0.386 RPTOOS TBVOOS <60 0.463 0.463 0.490 0.634 1.000 SLO >60 0.352 0.352 0.386 TABLE 5-6 Flow Dependent LHGR Multiplier LHGRFAC(F)
(References 2, 3 and 5)
Core Flow (0/0 of rated)
EOOS Combination o 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.5055 0.9732 1.00 1.00 Single Loop 0.5055 0.80 0.80 0.80 Page 12 of16
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 6.0 Control Rod Block Setpoints 6.1 Technical Specification Section 3.3.6 6.2 Description 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 Reactor Coolant System Recirculation Flow Upscale Trip is a cycle-specific value and as such is found in Table 6-2 of this COLR. Table 6-2 lists the Nominal Trip Setpoint and Allowable Value. These setpoints are set high enough to allow full utilization of the enhanced ICF domain up to 110% of rated core flow. Additionally, the ARTS Rod Block Monitor provides for power-dependent RBM trips. The trip setpoints/allowable values and applicable RBM signal filter time constant data are shown in Table 6-1. These values are for use with Technical Specification 3.3.6.
TABLE 6-1 Rod Block Monitor Setpoints 1 (References 2 and 7)
Nominal Trip Setpoint Allowable Value LTSP 121.5% 121.5%
ITSP 116.5% 116.5%
HTSP 111.0% 111.7%
DTSP 5.0% 2.0%
TABLE 6-2 Reactor Coolant System Recirculation Flow Upscale Trip (Reference 7)
Nominal Trip Setpoint 113.4%
Allowable Value 115.6%
1 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 1.30, which is less than or equal to the minimum cycle OLMCPR (see COLR References 2 and 7).
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Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 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 for use in Technical Specifications 3.7.8 and 4.7.8.C 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, must be used.
TABLE 7-1 Turbine Bypass System Response Time (Reference 4)
Maximum delay time before start ofbypass valve opening following generation ofthe 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 4)
Reactor Power No. of Valves in Service P~25% 7 Page 14 of16
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.1.2.F 8.2 Description The Limerick 2 Cycle 11 OPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System for use in Technical Specification 2.2.1 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 1 (Reference 2)
Corresponding Maximum PBDA Trip Amplitude Confrrmation Count Trip Setting
~ 1.14 ~ 16 9.0 Modes Of Operation TABLE 9-1 Modes Of Operation (References 2, 3, 5 and 10)
EOOS Options Operatine Reeion 2 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 Yes TBVOOS and RPTOOS, Option A or B Yes TBVOOS and RPTOOS SLO, Option A or B Yes 1 The station has conservatively decided to maintain the PDBA Trip Amplitude at 1.12 with a Corresponding Maximum Count Trip Setting of 14 until such time where these changes do not introduce a Unit difference at Limerick. This decision was agreed upon by Operations and Site Engineering.
2 Operating Region refers to operation on the Power to Flow map with or without FFWTR.
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Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 6 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", GNP Document, NEDE-24011-P-A-16, October 2007 and U.S. Supplement NEDE-24011-P-A-16-US, Revision 16, October 2007.
- 2. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications",
GENE Document, NEDO-32465-A, Rev. 0, 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 Generating Station Unit 2 Reload 10 Cycle 11",
Global Nuclear Fuel Document No. 0000-0087-4784-SRLR, Revision 0, February 2009.
- 3. "GEI4 Fuel Design Cycle-Independent Analyses for Limerick Generating Station Units 1 and 2", GENE Document, GE-NE-LI2-00884-00-01P Revision 0, March 2001.
- 4. "OPL-3 Parameters for Limerick 2 Cycle 11", TODI: ES0800031 Rev. 0, November 2008, Exelon Document.
- 5. "ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station", GENE Document NEDC-32847P, June 1998.
- 6. "General Electric Standard Application for Reactor Fuel", GNP Document, NEDE-24011-P-A-16, October 2007 and U.S. Supplement NEDE-24011-P-A-16-US, Revision 16, October 2007.
- 7. "Power Range Neutron Monitoring System Setpoint Calculations Limerick Generating Station, Units 1 & 2 Mod. No. P00224", LE-OI07, Rev. 0 (including minor revision OOC), April 2008, Exelon Document.
- 8. "Fuel Bundle Information Report for Limerick Generating Station Unit 2 Reload 10 Cycle 11", Global Nuclear Fuel Document No. 0000-0087-4784-FBIR, Revision 0, February 2009.
- 9. "Limerick Units 1 and 2 Off-Rated Analysis Below PLU Power Level With Credit for Backup Trip",
GENE Document, GE-NE-0000-0053-9467-Rl, August 2006.
- 10. "Limerick Generating Station Unit 2 Cycle 11 TBVOOS & RPTOOS Core Thermal Limits Evaluation",
GEH Document, 0000-0101-6009-RO, May 2009.
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