ML18113A188
| ML18113A188 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/23/2018 |
| From: | Libra R W Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LG-18-057 | |
| Download: ML18113A188 (21) | |
Text
Exelon Generation LG-18-057 April 23, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Limerick Generating
- Station, Unit 1 Renewed Facility Operating License No NPF-39 NRG Docket Nos. 50-352 T.S. 6.9.1.12
Subject:
Issuance of the Core Operating Limits Report (COLA) for Unit 1 Reload 17, Cycle 18 Enclosed is a copy of the Core Operating Limits Report (COLA) for Limerick Generating Station (LGS) Unit 1 Reload 17 Cycle 18 which incorporates the revised cycle specific parameters resulting from the new configuration implemented for LGS, Unit 1. The COLA is being submitted to the NRG in accordance with LGS, Unit 1 Technical Specification 6.9.1.12.
If you have any questions or require additional information, please contact Shawn Pinney at 610-718-3560.
Respectfully,
' Richard W. Libra Site Vice President-Limerick Generating Station Exelon Generation
- Company, LLC
Attachment:
Core Operating Limits Report (COLA) for Unit 1 Reload 17, Cycle 18 cc: D. Dorman, Administrator, Region I, USNRC S. Rutenkroger, USNRC Sr. Resident Inspector, LGS V. Sreenivas, USN RC Project Manager for LGS R. Janati, PADEP-BRP (w/attachments)
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Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 1 of 20 CORE OPERATING LIMITS REPORT FORLIMERICK GENERATING STATION UNIT 1 RELOAD 17 CYCLE 18 Prepared By: Date: K. E. Pfingsten/T. J. Stathes PreparerReviewed By: Date: R. C. Potter Independent ReviewerReviewed By: Date: A. Stefanczyk Reactor Engineering Reviewed By: Date: A. M. Olson Engineering Safety Analysis Approved By: Date: A. R. Johnson Sr.Manager - BWR Cycle Management Station Qualified Review By: Date: D.DoranStation Qualified Reviewer KKKKKKKKKKKEEEEEEEPfingMarch 26, 201803/26/2018 l03/27/2018 27MAR18ARJohnhhhhnhhhhnhhhhnhnhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhhson04/01/18 Exelon Nuclear -Nuclear FuelsCOLR Limerick 1, Rev. 14Core Operating Limits Reportfor Limerick 1 Cycle 18Page 2of20Table of ContentsPageRevision History3List of Tables4 1.0Terms and Definitions 5 2.0General Information7 3.0MAPLHGRLimits84.0MCPRLimits95.0LHGRLimits13 6.0Control Rod Block Setpoints16 7.0Turbine Bypass Valve Parameters17 8.0Stability Protection Setpoints18 9.0Modes of Operation19 10.0Methodology2011.0References20 Exelon Nuclear -Nuclear FuelsCOLR Limerick 1, Rev. 14Core Operating Limits Reportfor Limerick 1 Cycle 18Page 3of20 Revision HistoryRevisionDescriptionRevision 14New issue for Cycle 18.
Exelon Nuclear -Nuclear FuelsCOLR Limerick 1, Rev. 14Core Operating Limits Reportfor Limerick 1 Cycle 18Page 4of20List of TablesPageTable 3-1MAPLHGR Versus Average Planar Exposure8 Table 3-2MAPLHGR Single Loop Operation (SLO)Multiplier8 Table 4-1Operating Limit Minimum Critical Power Ratio (OLMCPR)10 Table 4-2Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp 11 Table 4-3Flow Dependent MCPR Limits MCPR(F)12Table 4-4Single Loop Operation (SLO)Flow Dependent MCPR Limits MCPR(F)12Table 5-1Linear Heat Generation Rate Limits -UO 2Rods13Table 5-2Linear Heat Generation Rate Limits -GadoliniaRods13Table 5-3LHGR Single Loop Operation (SLO) Multiplier14 Table 5-4Power Dependent LHGR Multiplier LHGRFAC(P)14 Table 5-5Flow Dependent LHGR Multiplier LHGRFAC(F)15Table 6-1Rod Block Monitor Setpoints16Table 6-2Reactor Coolant System Recirculation Flow Upscale Trip16 Table 7-1Turbine Bypass System Response Time17Table 7-2Minimum Required Bypass Valves To Maintain System Operability17 Table 8-1OPRM PBDA Trip Setpoints18 Table 9-1Modes of Operation19 Table 9-2"BASE" EOOS Option -Included Conditions 19 Exelon Nuclear -Nuclear FuelsCOLR Limerick 1, Rev. 14Core Operating Limits Reportfor Limerick 1 Cycle 18Page 5of201.0Terms and DefinitionsARTSAPRM, RBM,andTechnical Specification Improvement ProgramBASEThis condition is defined by a group of individual operating conditions that are applicable to all Modes of Operation discussed in Section 9.The "BASE" condition includes the EOOS conditions provided in Table 9-2 as well as operation with FWHOOS/FFWTR.DLODual Loop Operation DTSPRod Block Monitor Downscale Trip SetpointEOOS Equipment Out of ServiceEOREnd of Rated,the cycle exposure at which reactor power is equal to rated thermal powerwith recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium xenon.FFWTRFinal Feedwater Temperature Reduction FWHOOSFeedwater Heater(s)Out of Service HTSPRod Block Monitor High Trip Setpoint ICFIncreased Core FlowITSPRod Block Monitor Intermediate Trip SetpointKpOff-rated power dependent OLMCPR multiplier LHGRLinear Heat Generation Rate LHGRFAC(F)ARTSLHGRthermal limit flow dependent multipliers LHGRFAC(P)ARTSLHGR thermal limit power dependent multipliers LTSPRod Block Monitor Low Trip SetpointMAPFAC(F)Off-rated flow dependent MAPLHGRmultiplierMAPFAC(P)Off-rated power dependent MAPLHGRmultiplier MAPLHGRMaximum Average Planar Linear Heat Generation Rate MCPRMinimum Critical Power RatioMCPR(F)Off-rated flow dependent OLMCPR multiplier Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 6 of 20 MCPR(P) Off-rated power dependent OLMCPR multiplier MELLLA 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 Pressure Regulator Out of Service RBM Rod Block Monitor RPTOOS Recirculation Pump Trip Out of Service RWE Rod Withdrawal Error SLO Single Loop Operation SRVOOS Safety Relief Valve(s) Out of Service TBSOOS Turbine Bypass System Out of Service TBVOOS Turbine Bypass Valve(s) Out of Service TCV Turbine Control Valve TCV/TSVOOS Turbine Control Valve Out of Service and/or Turbine Stop Valve Out of Service TSV Turbine Stop Valve Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 7 of 20 2.0General Information This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 1 Cycle 18: Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) Minimum Critical Power Ratio (MCPR) Single Loop Operation (SLO) OLMCPR adjustment Off-rated OLMCPR adjustments (MCPR(P) or MCPR(F)) Off-rated OLMCPR multipliers (Kp) 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 Final Feedwater Temperature Reduction (FFWTR) up to 105.0F during cycle extension operation Feedwater Heater Out of Service (FWHOOS) up to 60.0F feedwater temperature reduction at any time during the cycle prior to cycle extension. Further information on the cycle-specific analyses for Limerick Unit 1 Cycle 18 and the associated operating domains discussed above is available in Reference 2.
Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 8 of 20 3.0MAPLHGR Limits 3.1Technical Specification Section 3.2.1 3.2Description The limiting MAPLHGR value for the most limiting lattice for GNF2 fuel as a function of average planar exposure is given in Table 3-1. For single loop operation, a multiplier is used, which is shown in Table 3-2. 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 (Reference 2) Average Planar Exposure (GWD/ST) MAPLHGR Limit (kW/ft) 0.0013.7813.2413.7817.5213.7860.787.5063.506.69 Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2) SLO Multiplier 0.80 Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 9 of 20 4.0MCPR Limits 4.1Technical Specification Section 3.2.3 4.2Description The Operating Limit MCPR (OLMCPR) for GNF2 fuel is provided in Table 4-1. These values are determined by the cycle-specific reload analyses in Reference 2 and are valid for all Cycle 18 operating domains. Table 4-1 includes treatment of these MCPR limits for all conditions listed in Section 9.0, Modes of Operation. Limerick Unit 1 Cycle 18 has a mid-cycle MCPR breakpoint, as defined in Table 4-1. 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 operating domains. MCPR(P) and MCPR(F) are independent of Scram Time Option. In addition, there are ten sets of power dependent MCPR multipliers (Kp) for use with the BASE, TBSOOS, RPTOOS, and PROOS equipment out of service combinations, in both DLO and SLO, as well as PROOS+TBSOOS and PROOS+RPTOOS equipment out of service combinations for DLO only. The PROOS+TBSOOS and PROOS+RPTOOS combinations were developed by selecting the more limiting OLMPCR from the PROOS condition and the other EOOS condition (TBSOOS or RPTOOS) (Reference 8). Section 7.0 contains the conditions for Turbine Bypass Valve Operability. MCPR(P) and MCPR(F) adjustments are provided in Tables 4-2, 4-3, and 4-4. 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.
Exelon Nuclear -Nuclear FuelsCOLR Limerick 1, Rev. 14Core Operating Limits Reportfor Limerick 1 Cycle 18Page 10of20 Table 4-1Operating Limit Minimum Critical Power Ratio (OLMCPR)(References2and 8)EOOS CombinationSCRAM Time Option1Cycle Exposure< EOR -3968 MWd/STEOR -3968 MWd/STBASEB1.3731.38B41.373,41.374A1.411.46BASE SLO2B1.601.60A1.601.60TBSOOSB1.3731.41A1.451.50TBSOOS SLO 2B1.601.60A1.601.60RPTOOSB1.3731.40A1.531.57RPTOOS SLO 2B1.601.60A1.601.61PROOSB1.3731.38A1.411.46PROOS SLO 2B1.601.60A1.601.60PROOS+TBSOOSB1.3731.41PROOS+RPTOOSB1.3731.401When Tau(as defined per Technical Specification3.2.3)does not equal 0 or 1, determine OLMCPR via linear interpolation.
2For single-loop operation, the MCPR operating limit is 0.04 greater than the analyzed two loop value. However, a minimum value of 1.60 is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).
3Value is adjusted to obtain an OPRM amplitude setpoint of 1.11.
4Limit is only applicable if it is confirmed that a 45ms or greater delay exists between the time of the first TSV movement and the time of the first TCV movement following a turbine trip.
Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 11 of 20 Table 4-2 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp(References 2 and 8) EOOS CombinationCore Flow
(% of rated)Core Thermal Power (% of Rated) 025< 30 30 6585100Operating Limit MCPR, MCPR(P) Operating Limit MCPR Multiplier, Kp BASE 60 2.522.522.421.3401.1311.0671.000> 60 2.782.782.57BASE SLO 60 2.562.562.461.3401.1311.0671.000> 60 2.822.822.61TBSOOS 60 3.283.282.781.3401.1311.0671.000> 60 3.783.783.28TBSOOS SLO 60 3.323.322.821.3401.1311.0671.000> 60 3.823.823.32RPTOOS 60 2.522.522.421.3401.1311.0671.000> 60 2.782.782.57RPTOOS SLO 60 2.562.562.461.3401.1311.0671.000> 60 2.822.822.61PROOS 60 2.522.522.421.3671.2361.1601.000> 60 2.782.782.57PROOS SLO 60 2.562.562.461.3671.2361.1601.000> 60 2.822.822.61PROOS+TBSOOS 60 3.283.282.781.3671.2361.1601.000> 60 3.783.783.28PROOS+RPTOOS 60 2.522.522.421.3671.2361.1601.000> 60 2.782.782.57 Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 12 of 20 Table 4-3 Flow Dependent MCPR Limits MCPR(F)(Reference 2)Flow (% rated) MCPR(F) Limit 0.01.7030.01.5379.01.25110.01.25Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) (Reference 2) Flow (% rated) MCPR(F) Limit 0.01.7430.01.5779.01.29110.01.29 Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 13 of 20 5.0LHGR Limits 5.1Technical Specification Section 3.2.4 5.2Description The LHGR limit for the GNF2 fuel type is the product of the exposure dependent LHGR limit (from Table 5-1 for UO 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 Operation 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 ten sets of power dependent LHGR multipliers for use with the BASE, TBSOOS, RPTOOS, and PROOS equipment out of service combinations, in both DLO and SLO, as well as PROOS+TBSOOS and PROOS+RPTOOS equipment out of service combinations for DLO only. The PROOS+TBSOOS and PROOS+RPTOOS combinations were developed by selecting the more limiting LHGRFAC(P) from the PROOS condition and the other EOOS condition (TBSOOS or RPTOOS) (Reference 8). Section 7.0 contains the conditions for Turbine Bypass Valve Operability. The ARTS LHGR multipliers are shown in Tables 5-4 and 5-5 and are applicable to all operating domains. Linear interpolation should be used for points not listed in Appendix B of Reference 7. Thermal limit monitoring must be performed with the more limiting LHGR limit resulting from the power and flow biased calculation.
Table 5-1 Linear Heat Generation Rate Limits - UO 2 Rods (References 5 and 7) Fuel Type LHGR GNF2See Table B-1 of Reference 7 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods (References 5 and 7) Fuel Type LHGR GNF2See Table B-2 of Reference 7 Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 14 of 20 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier (Reference 2) SLO Multiplier 10.80Table 5-4 Power Dependent LHGR Multiplier LHGRFAC(P) (References 2 and 8) EOOS CombinationCore Flow (% of rated)Core Thermal Power (% of rated) 025< 30 306585100LHGRFAC(P) Multiplier BASE 60 0.4850.4850.4900.7500.8170.9221.000> 60 0.4340.4340.473BASE SLO 60 0.4850.4850.4900.7500.8170.9221.000> 60 0.4340.4340.473TBSOOS 60 0.4630.4630.4900.7500.8170.9221.000> 60 0.3520.3520.386TBSOOS SLO 60 0.4630.4630.4900.7500.8170.9221.000> 60 0.3520.3520.386RPTOOS 60 0.4850.4850.4900.7500.8170.9221.000> 60 0.4340.4340.473RPTOOS SLO 60 0.4850.4850.4900.7500.8170.9221.000> 60 0.4340.4340.473PROOS 60 0.4850.4850.4900.7250.8170.9221.000> 60 0.4340.4340.473PROOS SLO 60 0.4850.4850.4900.7250.8170.9221.000> 60 0.4340.4340.473PROOS+TBSOOS 60 0.4630.4630.4900.7250.8170.9221.000> 60 0.3520.3520.386PROOS+RPTOOS 60 0.4850.4850.4900.7250.8170.9221.000> 60 0.4340.4340.4731 Applied through Table 5-5 Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 15 of 20 Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) (Reference 2) EOOS Combination Core Flow (% of rated) 03044.17080110LHGRFAC(F) MultiplierDual Loop 0.5060.7060.9731.0001.000Single Loop 0.5060.7060.8000.800 Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 16 of 20 6.0Control Rod Block Setpoints 6.1Technical Specification Sections 3.1.4.3 and 3.3.6 6.2Description The ARTS Rod Block Monitor provides for power dependent RBM trips. Technical Specification 3.3.6states 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 constantdata are shown inTable 6-1.The Reactor Coolant System Recirculation Flow Upscale Trip is shown in Table 6-2, in percent of rated drive flow. 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 1(References 2 and 4) Power Level Analytical Limit Allowable Value Nominal Trip 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 LimitN/AAllowable Value 115.6%Nominal Trip Setpoint 113.4%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 1.34 (Reference 2).
Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 17 of 20 7.0Turbine Bypass Valve Parameters 7.1Technical Specification Sections 3.7.8 and 4.7.8.c 7.2Description 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 System Out Of Service (TBSOOS), 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 initial turbine inlet valve movement 10.11 sec Maximum time after initial turbine inlet valve movement 1 for bypass valve position to reach 80% of rated bypass valve flow (includes the above delay time) 0.31 sec 1First movement of any TSV or any TCV (whichever occurs first)
Table 7-2 Minimum Required Bypass Valves To Maintain System Operability (References 1 and 3) Reactor Power No. of Valves in Service P 25%7 Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 18 of 20 8.0Stability Protection Setpoints 8.1Technical Specification Section 2.2.1 8.2Description The Limerick Unit 1 Cycle 18 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 Corresponding Maximum Confirmation Count Trip Setting 1.11 14 Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 19 of 20 9.0Modes of Operation 9.1Description The following conditions are supported by the Limerick Unit 1 Cycle 18 licensing analysis; operation in a condition (or conditions) is controlled by station procedures. If a combination of options is not listed, it is not supported. Table 9-1 provides allowed modes of operation with thermal limit sets in this COLR. Table 9-2 provides allowed modes of operation that do not contain explicit thermal limit sets in this COLR.
Table 9-1 Modes of Operation (References 2 and 8)
EOOS Options 1Supported Scram Speed Option Supported Recirculation LoopsBASE2,3Option A or B DLO or SLO TBSOOS4Option A or B DLO or SLORPTOOS5Option A or B DLO or SLO PROOSOption A or B DLO or SLO PROOS+TBSOOS 4Option B DLO PROOS+RPTOOS 5Option B DLO TABLE 9-2 "BASE" EOOS Option - Included Conditions (Reference 2) Condition PLUOOS1 MSIVOOS 61 TCV/TSVOOS 42 TBVOOS 2 SRVOOS 1All EOOS Options include the "BASE" EOOSOption. Any restrictions beyond the "BASE" condition's restrictions are noted on the applicable EOOS option.
2The "BASE" condition includes the conditions listed in Table 9-2.
3The "BASE" condition includes operation with or without FWHOOS/FFWTR.
4 1 TCV/TSVOOS, alone or coincident with another EOOS condition, is valid only at 90% rated thermal power, except when coincident with TBSOOS, which is valid only at 85% rated thermal power.
5 PLUOOS is valid coincident with the RPTOOS condition, but only at power levels 55% rated thermal power. 61 MSIVOOS is valid only at power levels 75% rated thermal power.
Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Page 20 of 20 10.0Methodology 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: 1."General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-26, January 2018 and U.S. Supplement NEDE-24011-P-A-26-US, January 2018. 2."Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," NEDO-32465-A, August 1996.
11.0References 1."Technical Specifications and Bases for Limerick Generating Station Unit 1", Docket No. 50-352, License No. NPF-39, Exelon Document. 2."Supplemental Reload Licensing Report for Limerick Unit 1 Reload 17 Cycle 18", Global Nuclear Fuel Document No. 004N1986, Rev. 0, February 2018. 3."Final Resolved OPL-3 Parameters for Limerick Unit 1 Cycle 18",Exelon TODI ES1700022, Rev. 0, October 17, 2017. 4."GE NUMAC PRNM Setpoint Study", Exelon Design Analysis LE-0107, Rev. 2, February 23, 2012.
5."Fuel Bundle Information Report for Limerick Unit 1 Reload 17 Cycle 18", Global Nuclear Fuel Document No. 004N1987, Rev. 0, February 2018. 6."Tech Eval Stop Valve Load Limit Documentation", Exelon Document IR 917231 Assignment 7, November 11, 2009. 7."GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," Global Nuclear Fuel Document No. NEDC-33270P, Rev. 9, December 2017. 8."Limerick Generating Station (LGS) Units 1 and 2 TRACG Cycle-Independent PROOS Analysis Report", GE Hitachi Document No. 002N4397 R1, Rev. 1, January 2016.