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{{Adams
#REDIRECT [[BSEP 15-0022, Cycle 22 Core Operating Limits Report (COLR)]]
| number = ML15091A406
| issue date = 03/23/2015
| title = Brunswick, Unit 2 - Cycle 22 Core Operating Limits Report (Colr)
| author name = Pope A H
| author affiliation = Duke Energy Carolinas, LLC, Duke Energy Corp
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000324
| license number = DPR-062
| contact person =
| case reference number = BSEP 15-0022
| document report number = 2B21-2020, Rev. 0
| document type = Fuel Cycle Reload Report, Letter
| page count = 42
}}
 
=Text=
{{#Wiki_filter:~ENERGY,Brunswick Nuclear PlantP.O. Box 10429Southport, NC 28461March 23, 2015Serial: BSEP 15-002210 CFR 50.4U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001
 
==Subject:==
Brunswick Steam Electric Plant, Unit No. 2Renewed Facility Operating License No. DPR-62Docket No. 50-324Unit 2 Cycle 22 Core Operating Limits Report (COLR)
 
==Reference:==
Letter from Annette H. Pope (Duke Energy) to NRC Document Control Desk,Unit 2 Cycle 21 Core Operating Limits Report (COLR), dated April 23, 2013,ADAMS Accession Number ML1 3142A031Ladies and Gentlemen:Enclosed is a copy of the Core Operating Limits Report (COLR) for Brunswick Steam ElectricPlant (BSEP), Unit 2 Cycle 22 operation. Duke Energy Progress, Inc., is providing the enclosedCOLR in accordance with Brunswick Unit 2 Technical Specification 5.6.5.d. The enclosed COLRsupersedes the report previously submitted by letter dated April 23, 2013.This document contains no regulatory commitments. Please refer any questions regarding thissubmittal to Mr. Lee Grzeck, Manager -Regulatory Affairs, at (910) 457-2487.Sincerely,Annette H. PopeDirector -Organizational EffectiVenessBrunswick Steam Electric PlantWRM/wrm
 
==Enclosure:==
Brunswick Unit 2, Cycle 22 Core Operating Limits Report, March 2015A00 U.S. Nuclear Regulatory CommissionPage 2 of 2cc (with enclosure):U.S. Nuclear Regulatory Commission, Region IIATTN: Mr. Victor M. McCree, Regional Administrator245 Peachtree Center Ave, NE, Suite 1200Atlanta, GA 30303-1257U.S. Nuclear Regulatory CommissionATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only)11555 Rockville PikeRockville, MD 20852-2738U.S. Nuclear Regulatory CommissionATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector8470 River RoadSouthport, NC 28461-8869Chair -North Carolina Utilities CommissionP.O. Box 29510Raleigh, NC 27626-0510 BSEP 15-0022EnclosureBrunswick Unit 2, Cycle 22 Core Operating Limits Report, March 2015 Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign Calc. No. 2B21-2020Page 1, Revision 0BRUNSWICK UNIT 2, CYCLE 22CORE OPERATING LIMITS REPORTMarch 2015Prepared By:Verified By:Approved By:3 /5Ryin e. WellsBWR Fuel EngineeringPeter M. NoelBWR Fuel EngineeringE"WR Fuel Engineering -Manager Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign Calc. No. 2B21-2020Page 2, Revision 0LIST OF EFFECTIVE PAGESPaQe(s)1-39Revision0This document consists of 39 total pages.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 2621-2020B2C22 Core Operating Limits Report Page 3, Revision 0TABLE OF CONTENTSSubject PaqeCover ...............................................................1List of Effective Pages ...................................................................................................................... 2Table of Contents ............................................................................................................................. 3L is t o f T a b le s .................................................................................................................................... 4L ist o f F ig u re s ................................................................................................................................... 5N o m e n c la tu re ................................................................................................................................... 6Introduction and Sum mary ........................................................................................................ 8A P L H G R L im its ................................................................................................................................ 9M C P R L im its .................................................................................................................................... 9L H G R L im its ................................................................................................................................... 1 0PBDA Setpoints .............................................................................................................................. 10R B M S e tp o in ts ................................................................................................................................ 1 1Equipment Out-of-Service .............................................................................................................. 11Single Loop Operation .................................................................................................................... 12Inoperable Main Turbine Bypass System .......................................... .......................................... 12Feedwater Tem perature Reduction ............................................................................................ 12R e fe re n c e s ..................................................................................................................................... 1 4 Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 2B21-2020B2C22 Core Operating Limits Report Page 4, Revision 0CAUTIONReferences to COLR Figures or Tables should be made using titles only; Figure and Table numbersmay change from cycle to cycle.LIST OF TABLESTable Title PaeeTable 1: R BM System Setpoints ............................................................................................ 16Table 2: RBM O perability Requirem ents ................................................................................ 17T able 3: P B D A S etpoints .................................................................................................... ..18Table 4: Exposure Basis for Brunswick Unit 2 Cycle 22 Transient Analysis ........................... 19Table 5: Power-Dependent MCPRp Lim its ............................................................................. 20NSS Insertion Times -BOC to < NEOCTable 6: Power-Dependent MCPRp Lim its ............................................................................. 21TSSS Insertion Times -BOC to < NEOCTable 7: Power-Dependent MCPRp Lim its ............................................................................. 22NSS Insertion Times -BOC to < EOCLBTable 8: Power-Dependent MCPRp Lim its ............................................................................. 23TSSS Insertion Times -BOC to < EOCLBTable 9: Power-Dependent MCPRp Lim its ............................................................................. 24NSS Insertion Times -BOC to < MCE (FFTR/Coastdown)Table 10: Power-Dependent MCPRp Lim its ............................................................................. 25TSSS Insertion Times -BOC to < MCE (FFTR/Coastdown)Table 11: Flow-Dependent M CPRf Lim its ................................................................................. 26Table 12: AREVA Fuel Steady-State LHGRss Limits ............................................................... 27Table 13: AREVA Fuel Power-Dependent LHGRFACp Multipliers ............................................. 28NSS Insertion Times -BOC to < EOCLBTable 14: AREVA Fuel Power-Dependent LHGRFACp Multipliers ............................................. 29TSSS Insertion Times -BOC to < EOCLBTable 15: AREVA Fuel Power-Dependent LHGRFACp Multipliers ............................................. 30NSS Insertion Times -BOC to < MCE (FFTR/Coastdown)Table 16: AREVA Fuel Power-Dependent LHGRFACp Multipliers ............................................. 31TSSS Insertion Times -BOC to < MCE (FFTR/Coastdown)Table 17: AREVA Fuel Flow-Dependent LHGRFACf Multipliers ............................................... 32Table 18: AREVA Fuel Steady-State MAPLHGRss Limits ........................................................ 33 Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Caic. No. 2B21-2020B2C22 Core Operating Limits Report Page 5, Revision 0I CAUTIONReferences to COLR Figures or Tables should be made using titles only; Figure and Table numbersmay change from cycle to cycle.LIST OF FIGURESFigure Title or Description PageFigure 1: Stability O ption III Power/Flow Map .......................................................................... 34OPRM Operable, Two Loop Operation, 2923 MWtFigure 2: Stability O ption III Power/Flow Map .......................................................................... 35OPRM Inoperable, Two Loop Operation, 2923 MWtFigure 3: Stability O ption III Power/Flow Map .......................................................................... 36OPRM Operable, Single Loop Operation, 2923 MWtFigure 4: Stability O ption III Power/Flow M ap .......................................................................... 37OPRM Inoperable, Single Loop Operation, 2923 MWtFigure 5: Stability O ption III Power/Flow M ap .......................................................................... 38OPRM Operable, FWTR, 2923 MWtFigure 6: Stability O ption III Power/Flow M ap .......................................................................... 39OPRM Inoperable, FWTR, 2923 MWt Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign CaIc. No. 2821-2020Page 6, Revision 02PTAPLHGRAPRMARTSBOCBSPBWROGCAVEXCOLRCRWEDIVOMEFPDEOCEOCLBEOFPEOOSFFHOOSFFTRFWTRGEHCOMHPSPHTSPICFIPSPITSPNOMENCLATURETwo Recirculation Pump TripAverage Planar Linear Heat Generation RateAverage Power Range Monitor (Subsystem)APRM/RBM Technical SpecificationBeginning of CycleBackup Stability ProtectionBWR Owners GroupCore Average ExposureCore Operating Limits ReportControl Rod Withdrawal ErrorDelta CPR Over Initial MCPR Versus Oscillation MagnitudeEffective Full Power DayEnd of CycleEnd of Cycle Licensing BasisEnd of Full PowerEquipment Out of ServiceFlow (Total Core)Feedwater Heater Out of ServiceFinal Feedwater Temperature ReductionFeedwater Temperature ReductionGeneral ElectricHot Channel Oscillation MagnitudeHigh Power Set PointHigh Trip Set PointIncreased Core FlowIntermediate Power Set PointIntermediate Trip Set PointLimiting Condition of OperationLinear Heat Generation RateSteady-State Maximum Linear Heat Generation RateLinear Heat Generation Rate FactorFlow-Dependent Linear Heat Generation Rate FactorPower-Dependent Linear Heat Generation Rate FactorLocal Power Range Monitor (Subsystem)Low Power Set PointLead Test AssemblyLow Trip Set PointMaximum Average Planar Linear Heat Generation RateSteady-State Maximum Average Planar Linear Heat Generation RateMaximum Average Planar Linear Heat Generation Rate FactorLCOLHGRLHGRssLHGRFACLHGRFACfLHGRFACpLPRMLPSPLTALTSPMAPLHGRMAPLHGRssMAPFAC Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign Calc. No. 2B21-2020Page 7, Revision 0NOMENCLATURE (continued)MAPFACfMAPFACPMAPFACSLOMCEMCPRMCPRfMCPRpMELLLMEODMSIVOOSNEOCNFWTNRCNSSOLMCPROPRMOOSPPBDAPRNMRBMRFWTRPTRTPSLMCPRSLOSRVSRVOOSSSSTPTBVTBVINSTBVOOSTIPTLOTSTSSSFlow-Dependent Maximum Average Planar Linear Heat Generation Rate FactorPower-Dependent Maximum Average Planar Linear Heat Generation Rate FactorMaximum Average Planar Linear Heat Generation Rate Factor when in SLOMaximum Core ExposureMinimum Critical Power RatioFlow-Dependent Minimum Critical Power RatioPower-Dependent Minimum Critical Power RatioMaximum Extended Load Line LimitMaximum Extended Operating DomainMain Steam Isolation Valve Out of ServiceNear End of CycleNominal Feedwater TemperatureNuclear Regulatory CommissionNominal SCRAM SpeedOperating Limit Minimum Critical Power RatioOscillation Power Range MonitorOut of ServicePower (Total Core Thermal)Period Based Detection AlgorithmPower Range Neutron Monitoring (System)Rod Block Monitor (Subsystem)Reduced Feedwater TemperatureRecirculation Pump TripRated Thermal PowerSafety Limit Minimum Critical Power RatioSingle Loop OperationSafety Relief ValveSafety Relief Valve Out of ServiceSteady-StateSimulated Thermal PowerTurbine Bypass ValveTurbine Bypass Valves In ServiceTurbine Bypass Valves Out of Service (all bypass valves OOS)Traversing Incore ProbeTwo Loop OperationTechnical SpecificationTechnical Specification SCRAM Speed Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign Calc. No. 2B21-2020Page 8, Revision 0CAUTIONReferences to COLR Figures or Tables should be made using titles only; Figure and Table numbersmay change from cycle to cycle.IIntroduction and SummaryThe Brunswick Unit 2, Cycle 22 COLR provides values for the core operation limits and setpointsrequired by Technical Specifications (TS) 5.6.5.a.Required Core NRCOperating Limit Approved Related TS ItemsTS 5.6.5.a) Methodology(TS 5.6.5.b)1. APLHGR forTS 3.2.1. 1, 2, 6, 7,16, -TS 3.2.1 LCO (APLHGR)17 -TS 3.4.1 LCO (Recirculation loopsoperating)-TS 3.7.6 LCO (Main Turbine Bypass out ofservice)2. MCPR for TS 3.2.2. 1, 2, 6, 7, 8, 9, -TS 3.2.2 LCO (MCPR)10, 11, 12, 13, -TS 3.4.1 LCO (Recirculation loops14, 21 operating)-TS 3.7.6 LCO (Main Turbine bypass out ofservice)3. LHGR for TS 3.2.3. 2, 3, 4, 5, 6, 7, -TS 3.2.3 LCO (LHGR)8, 9, 10, 12 -TS 3.4.1 LCO (Recirculation loops13, 20 operating)-TS 3.7.6 LCO (Main Turbine bypass out ofservice)4. PBDA setpointfor 8, 14, 18, 19, -TS Table 3.3.1.1-1, Function 2.fFunction 2.f, APRM -OPRM 21 (APRM -OPRM Upscale)Upscale, for TS 3.3. 1.1. -TS 3.3.1.1, Condition I (Alternate instabilitydetection and suppression)5. The Allowable Values and 6, 8 -TS Table 3.3.2.1-1, Function 1 (RBMpower range setpoints for Rod upscale and operability requirements)Block Monitor UpscaleFunctions for TS 3.3.2.1.The required core operating limits and setpoints listed in TS 5.6.5.a are presented in the COLR,have been determined using NRC approved methodologies (COLR References 1 through 21) inaccordance with TS 5.6.5.b, have considered all fuel types utilized in B2C22, and are establishedsuch that all applicable limits of the plant safety analysis are met in accordance with TS 5.6.5.c.In addition to the TS required core operating limits and setpoints, this COLR also includes mapsshowing the allowable power/flow operating range including the Option III stability ranges.The generation of this COLR is documented in Reference 30 and is based on analysis resultsdocumented in References 27-29.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 2B21-2020B2C22 Core Operating Limits Report Page 9, Revision 0APLHGR LimitsSteady-state MAPLHGRss limits are provided for AREVA Fuel (Table 18). These steady-stateMAPLHGRss limits must be modified as follows:* AREVA Fuel MAPLHGR limits do not have a power, flow, or EOOS dependency. Power-dependent MAPFACP multipliers and flow-dependent MAPFACf multipliers with a constant valueof 1.0 under all conditions have been assigned to AREVA Fuel.* The applied MAPLHGR limit is dependent on the number of recirculation loops in operation.The steady-state MAPLHGR limit must be modified by a MAPFACSLO multiplier when in SLO.MAPFACSLO has a fuel design dependency as shown below.The applied TLO and SLO MAPLHGR limits are determined as follows:MAPLHGR LimitTLO = MAPLHGRss x (MAPFACp, MAPFACf, 1.0)minMAPLHGR LimitSLO = MAPLHGRss x (MAPFACp, MAPFACf, MAPFACSLO)minwhere MAPFACSLO = 0.80 for ATRIUM 10XMand ATRIUM 11 fuelLinear interpolation should be used to determine intermediate values between the values listed in thetable.MCPR LimitsThe MCPR limits presented in Tables 5 through 11 are based on the TLO and SLO SLMCPRs listed inTechnical Specification 2.1.1.2 as >1.08 and >1.11, respectively.* MCPR limits have a core power and core flow dependency. Power-dependent MCPRp limits arepresented in Tables 5 through 10 while flow-dependent MCPRf limits are presented in Table 11.* Power-dependent MCPRp limits are dependent on CAVEX, SCRAM insertion speed, EOOS,fuel design, number of operating recirculation loops (i.e., TLO or SLO), core flow and corethermal power. Values for the CAVEX breakpoints are provided in Table 4. See COLR sectiontitled "Equipment Out-of-Service" for a list of analyzed EOOS conditions. Care should be usedwhen selecting the appropriate limits set.* The MCPR limits are established such that they bound all pressurization and non-pressurizationevents.* The power-dependent MCPRP limits (Tables 5-10) must be adjusted by an adder of +0.03 whenin SLO.The applied TLO and SLO MCPR limits are determined as follows:MCPR LimitTLO = (MCPRp, MCPRf)maxMCPR LimitSLO = (MCPRp + 0.03, MCPRf)maxLinear interpolation should be used to determine intermediate values between the values listed in thetables. Some of the limits tables show two breakpoints at 26.0%P and 50.0%P. IF performing a handcalculation of a limit AND the power is exactly on the breakpoint (i.e. 26.0 or 50.0), THEN select themost restrictive limit associated with the breakpoint.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 2B21-2020B2C22 Core Operating Limits Report Page 10, Revision 0LHGR LimitsSteady-state LHGRss limits are provided for AREVA Fuel (Table 12). These steady-state LHGRsslimits must be modified as follows:* AREVA Fuel LHGR limits have a core power and core flow dependency. AREVA Fuelpower-dependent LHGRFACp multipliers (Tables 13-16) and flow-dependent LHGRFACfmultipliers (Table 17) must be used to modify the steady-state LHGRss limits (Table 12) foroff-rated conditions." AREVA Fuel power-dependent LHGRFACp multipliers are dependent on CAVEX, SCRAMinsertion speed, EOOS, fuel design, core flow and core thermal power. Values for the CAVEXbreakpoints are provided in Table 4. See COLR section titled "Equipment Out-of-Service" for alist of analyzed EOOS conditions. Care should be used when selecting the appropriatemultiplier set." The applied LHGR limit is not dependent on the number of operating recirculation loops. Noadjustment to the LHGR limit is necessary for SLO.The applied LHGR limit is determined as follows:LHGR Limit = LHGRss x (LHGRFACP, LHGRFACf)minLinear interpolation should be used to determine intermediate values between the values listed in thetables. Some of the limits tables show two breakpoints at 26.0%P and 50.0%P. IF performing a handcalculation of a limit AND the power is exactly on the breakpoint (i.e. 26.0 or 50.0), THEN select themost restrictive limit associated with the breakpoint.PBDA SetpointsBrunswick Unit 2 has implemented BWROG Long Term Stability Solution Option III (OPRM) with themethodology described in Reference 23. Plant specific analysis incorporating the Option III hardware isdescribed in Reference 24. Reload validation has been performed in accordance with Reference 19.The analysis was performed at 100%P assuming a two pump trip (2PT) and at 45%F assuming steady-state (SS) conditions at the highest rod line power (60.5%). The PBDA setpoints are set such thateither the least limiting MCPRp limit or the least limiting MCPRf limit will provide adequate protectionagainst violation of the SLMCPR during a postulated reactor instability. Based on the MCPR limitspresented in Tables 5 through 11, the required Amplitude Trip Setpoint (1.10) is set by the least limiting100%P MCPRp limit (1.34) with an allowance for conservative margin, which has an associatedConfirmation Count Setpoint (13). The PBDA setpoints shown in Table 3 are valid for any feedwatertemperature.Evaluations by GE have shown that the generic DIVOM curves specified in Reference 19 may not beconservative for current plant operating conditions for plants which have implemented Stability OptionIll. To address this issue, AREVA has performed calculations for the relative change in CPR as afunction of the calculated HCOM. These calculations were performed with the RAMONA5-FA code inaccordance with Reference 26. This code is a coupled neutronic-thermal-hydraulic three-dimensionaltransient model for the purpose of determining the relationship between the relative change in ACPRand the HCOM on a plant specific basis. The stability-based OLMCPRs are based upon using themost limiting ACPR calculated for a given oscillation magnitude or the generic value provided inReference 19.In cases where the OPRM system is declared inoperable, Backup Stability Protection (BSP) inaccordance with Reference 25 is provided. Analyses have been performed to support operation withnominal feedwater temperature conditions and reduced feedwater temperature conditions Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 2B21-2020B2C22 Core Operating Limits Report Page 11, Revision 0(FHOOS and FFTR).The power/flow maps (Figures 1-6) were validated for B2C22 based on Reference 29 to facilitateoperation under Stability Option III as implemented by Function 2.f of Table 3.3.1.1-1 and LCOCondition I of Technical Specification 3.3.1.1. The generation of these maps is documented inReference 28. All maps illustrate the region of the power/flow map above 25% RTP and below 60%drive flow (correlated to core flow) where the system is required to be enabled. Figures 1-6 wereincluded in the COLR as an operator aid and not a licensing requirement. Figures 5 and 6 are thepower/flow maps for use in FWTR.The maps supporting an operable OPRM (Figures 1, 3 and 5) show a Scram Avoidance Region, whichis not a licensing requirement but is an operator aid to illustrate where the OPRM system may generatea scram to avoid an instability event. Note that the STP scram and rod block limits are defined inTechnical Specifications, the Technical Requirements Manual, and/or Plant procedures, and areincluded in the COLR as an operator aid rather than a licensing requirement.Figures 3 and 4 implement the corrective action for AR-217345 which restricts reactor power to nomore than 50% RTP when in SLO with OPRM operable or inoperable. This operator aid is intended tomitigate a spurious OPRM trip signal which could result from APRM noise while operating at highpower levels.RBM SetpointsThe nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation arepresented in Table 1 and were determined to be consistent with the bases of the ARTS program(Reference 22). These setpoints will ensure the power-dependent MCPR limits will provide adequateprotection against violation of the SLMCPR during a postulated CRWE event. Reference 27 revisedthese setpoints to reflect changes associated with the installation of the NUMAC PRNM system. RBMoperability requirements, consistent with Notes (a) through (e) of Technical SpecificationTable 3.3.2.1-1, are provided in Table 2.Equipment Out-of-ServiceBrunswick Unit 2, Cycle 22 is analyzed for the following operating conditions with applicable MCPR,APLHGR and LHGR limits.* Base Case Operation* SLO* TBVOOS" FHOOS" Combined TBVOOS and FHOOSBase Case Operation as well as the above-listed EOOS conditions assume all the items OOS below.These conditions are general analysis assumptions used to ensure conservative analysis results andwere not meant to define specific EOOS conditions beyond those already defined in TechnicalSpecifications.0 Any 1 inoperable SRV* 2 inoperable TBV (Note that for TBVOOS and TBVOOS/FHOOS all 10 TBVs are assumedinoperable)* Up to 40% of the TIP channels OOS0 Up to 50% of the LPRMs OOSPlease note that during FFTR/Coastdown, FHOOS is included in Base Case Operation and TBVOOS.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design CaIc. No. 2B21-2020B2C22 Core Operating Limits Report Page 12, Revision 0Single Loop OperationBrunswick Unit 2, Cycle 22 may operate in SLO up to a maximum core flow of 45 Mlbm/hr whichcorresponds to a maximum power level of 71.1% RTP with applicable MCPR, APLHGR and LHGRlimits. The following must be considered when operating in SLO:" SLO is not permitted with RFWT (FHOOS)." SLO is not permitted with TBVOOS.* SLO is not permitted with MSIVOOS.Various indicators on the Power/Flow Maps are provided not as operating limits but rather as aconvenience for the operators. The purposes for some of these indicators are as follows:" The SLO Entry Rod Line is shown on the TLO maps to avoid regions of instability in the event ofa pump trip." A maximum core flow line is shown on the SLO maps to avoid vibration problems.* APRM STP Scram and Rod Block nominal trip setpoint limits are shown at the estimated coreflow corresponding to the actual drive flow-based setpoints to indicate where the Operator mayencounter these setpoints (See LCO 3.3.1.1, Reactor Protection System InstrumentationFunction 2.b: Average Power Range Monitors Simulated Thermal Power -High Allowable Value).* When in SLO, Figures 3 and 4 implement the corrective action for AR-217345 which restrictsreactor power to no more than 50% RTP with OPRM operable or inoperable. This operator aidis intended to mitigate a spurious OPRM trip signal which could result from APRM noise whileoperating at high power levels.Inoperable Main Turbine Bypass SystemBrunswick Unit 2, Cycle 22 may operate with an inoperable Main Turbine Bypass System over theentire MEOD range and cycle with applicable APLHGR, MCPR and LHGR limits as specified in theCOLR. An operable Main Turbine Bypass System with only two inoperable bypass valves wasassumed in the development of the Base Case Operation limits. Base Case Operation is synonymouswith TBVINS. The following must be considered when operating with TBVOOS:" Three or more inoperable bypass valves renders the entire Main Turbine Bypass Systeminoperable requiring the use of TBVOOS limits. The TBVOOS analysis supports operation withall bypass valves inoperable.* Prior to reaching the EOCLB exposure breakpoint, operation with FWTR >1O&deg;F and reactorpower > 50% RTP requires use of the TBVOOS/FHOOS limits. At or below 50% RTP,TBVOOS limits bound FHOOS limits.* TBVOOS operation coincident with FHOOS is supported using the combined TBVOOS/FHOOSlimits." SLO is not permitted with TBVOOS.Feedwater Temperature ReductionBrunswick Unit 2, Cycle 22 may operate with RFWT over the entire MEOD range and cycle withapplicable APLHGR, MCPR and LHGR limits as specified in the COLR. NFWT is defined as the rangeof feedwater temperatures from NFWT to NFWT -10'F. NFWT and its allowable variation wereassumed in the development of the Base Case Operation limits. The FHOOS limits andFFTR/Coastdown limits were developed for a maximum feedwater temperature reduction of 110.3&deg;F.The following must be considered when operating with RFWT:* Although the acronyms FWTR, FHOOS, RFWT and FFTR all involve reduced feedwatertemperature, the use of FFTR is reserved for cycle energy extension using reduced feedwater Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design CaIc. No. 2B21-2020B2C22 Core Operating Limits Report Page 13, Revision 0temperature at and beyond a core average exposure of EOCLB using FFTR/Coastdown limits.* Prior to reaching the EOCLB exposure breakpoint, operation with FWTR >1O&deg;F and reactorpower > 50% RTP requires use of the FHOOS limits. At or below 50% RTP, Base CaseOperation limits bound FHOOS limits." Until a core average exposure of EOCLB is reached, implementation of the FFTR/Coastdownlimits is not required even if coastdown begins early." When operating with RFWT, the appropriate Stability Option III Power/Flow Maps (Figures 5and 6) must be used." FHOOS operation coincident with TBVOOS is supported using the combined TBVOOS/FHOOSlimits." SLO is not permitted with RFWT.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design CaIc. No. 2B21-2020B2C22 Core Operating Limits Report Page 14, Revision 0ReferencesIn accordance with Brunswick Unit 2 Technical Specification 5.6.5.b, the analytical methods fordetermining Brunswick Unit 2 core operating limits have been specifically reviewed and approved bythe NRC and are listed as References 1 through 21.1. NEDE-2401 1-P-A, "GESTAR II -General Electric Standard Application for Reactor Fuel," and USSupplement, Revision 15, September 2005.2. XN-NF-81-58(P)(A) and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-MechanicalResponse Evaluation Model," Revision 2, March 1984.3. XN-NF-85-67(P)(A), "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel,"Revision 1, September 1986.4. EMF-85-74(P) Supplement 1(P)(A) and Supplement 2(P)(A), "RODEX2A (BWR) Fuel RodThermal-Mechanical Evaluation Model," Revision 0, February 1998.5. ANF-89-98(P)(A), "Generic Mechanical Design Criteria for BWR Fuel Designs," Revision 1,May 1995.6. XN-NF-80-19(P)(A) Volume 1 and Volume 1 Supplement 1 and 2, "Exxon Nuclear Methodologyfor Boiling Water Reactors -Neutronic Methods for Design and Analysis," March 1983.7. XN-NF-80-19(P)(A) Volume 4, "Exxon Nuclear Methodology for Boiling Water Reactors:Application of the ENC Methodology to BWR Reloads," Revision 1, June 1986.8. EMF-2158(P)(A), "Siemens Power Corporation Methodology for Boiling Water Reactors:Evaluation and Validation of CASMO-4/MICROBURN-B2," Revision 0, October 1999.9. XN-NF-80-19(P)(A) Volume 3, "Exxon Nuclear Methodology for Boiling Water Reactors,THERMEX: Thermal Limits Methodology Summary Description," Revision 2, January 1987.10. XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, "XCOBRA-T: A ComputerCode for BWR Transient Thermal-Hydraulic Core Analysis," February 1987.11. ANP-10307PA, "AREVA MCPR Safety Limit Methodology for Boiling Water Reactors," Revision 0,June 2011.12. ANF-913(P)(A) Volume 1 and Volume 1 Supplements 2, 3, 4, "COTRANSA2: A ComputerProgram for Boiling Water Reactor Transient Analyses," Revision 1, August 1990.13. ANF-1358(P)(A), "The Loss of Feedwater Heating Transient in Boiling Water Reactors,"Revision 3, September 2005.14. EMF-2209(P)(A), "SPCB Critical Power Correlation," Revision 3, September 2009.15. EMF-2245(P)(A), "Application of Siemens Power Corporation's Critical Power Correlations toCo-Resident Fuel," Revision 0, August 2000.16. EMF-2361(P)(A), "EXEM BWR-2000 ECCS Evaluation Model," Revision 0, May 2001.17. EMF-2292(P)(A), "ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients," Revision 0,September 2000.18. EMF-CC-074(P)(A) Volume 4, "BWR Stability Analysis -Assessment of STAIF with Input fromMICROBURN-B2," Revision 0, August 2000.19. NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodologyfor Reload Applications," August 1996.20. BAW-1 0247PA, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling WaterReactors," Revision 0, April 2008.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design Calc. No. 2B21-2020B2C22 Core Operating Limits Report Page 15, Revision 021. ANP-10298PA, "ACE/ATRIUM 10XM Critical Power Correlations," Revision 0, March 2010.22. NEDC-31654P, "Maximum Extended Operating Domain Analysis for Brunswick Steam ElectricPlant," February 1989.23. NEDO-31960-A, "BWR Owners Group Long-Term Stability Solutions Licensing Methodology(Supplement 1)," November 1995, NRC ADAMS Accession No. ML14093A211.24. GENE-C51-00251-00-01, "Licensing Basis Hot Bundle Oscillation Magnitude for Brunswick 1and 2," Revision 0, March 2001.25. OG 02-0119-260 "Backup Stability Protection (BSP) for Inoperable Option III Solution, GE NuclearEnergy," July 17, 2002.26. BAW-10255PA, "Cycle Specific DIVOM Methodology Using the RAMONA5-FA Code," Revision 2,May 2008.27. BNP Design Calculation 2C51-0001, "Power Range Neutron Monitoring System SetpointUncertainty and Scaling Calculation (2-C51-APRM-1 through 4 Loops and 2-C51-RBM-A and BLoops)," Revision 3, May 2004.28. BNP Design Calculation 0B21-1015, "BNP Power/Flow Maps," Revision 7, March 2008.29. ANP-3369(P), "Brunswick Unit 2 Cycle 22 Reload Safety Analysis," Revision 0, January 2015.30. BNP Design Calculation 2B21-2020, "Preparation of the B2C22 Core Operating Limits Report,"Revision 0.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign Calc. No. 2821-2020Page 16, Revision 0Table 1RBM System Setpoints1Setpoint a Setpoint Value Allowable ValueLower Power Setpoint (LPSP b) < 27.7 < 29.0Intermediate Power Setpoint (IPSPb) < 62.7 < 64.0High Power Setpoint (HPSP b) < 82.7 < 84.0Low Trip Setpoint (LTSPc' d) < 114.1 < 114.6Intermediate Trip Setpoint (ITSPc'd) < 108.3 < 108.8High Trip Setpoint (HTSPc'd) < 104.5 < 105.0RBM Time Delay (td2) 0 seconds < 2.0 secondsa See Table 2 for RBM Operability Requirements.b Setpoints in percent of Rated Thermal Power.c Setpoints relative to a full scale reading of 125. For example, < 114.1 means< 114.1/125.0 of full scale.d Trip setpoints and allowable values are based on a HTSP Analytical Limit of107.4 with RBM filter.1 This table is referred to by Technical Specification 3.3.2.1 (Table 3.3.2.1-1) and 5.6.5.a.5.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design82C22 Core Operating Limits ReportDesign Calc. No. 2B21-2020Page 17, Revision 0Table 2RBM Operability Requirements2IF the following conditions are met, THENRBM Not Required OperableThermal Power ATRIUM 1OXM ATRIUM 11 LTA(% rated) MCPR MCPR2 <1.91 TLO -1.55 TLO291.96 SLO ->1.60 SLO-90% -1.52 TLO ->1.36 TLO2 Requirements valid for all fuel designs, all SCRAM insertion times and all core average exposure ranges.
Duke Energy, Nuclear Fuels Engineering,B2C22 Core Operating Limits ReportNuclear Fuel DesignTable 3PBDA Setpoints3Design Calc. No. 2B21-2020Page 18, Revision 0Amplitude Trip OLMCPR(SS) OLMCPR(2PT)Setpoint (SP)1.05 1.20 1.211.06 1.22 1.231.07 1.23 1.251.08 1.25 1.271.09 1.27 1.291.10 1.29 1.311.11 1.31 1.331.12 1.33 1.351.13 1.35 1.371.14 1.37 1.391.15 1.40 1.41Acceptance Criteria Off-rated OLMCPR @ Rated Power45% Flow OLMCPR3 This table is referred to by Technical Specification 3.3.1.1 (Table 3.3.1.1-1) and 5.6.5.a.4.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportTable 4Exposure Basis4 forBrunswick Unit 2 Cycle 22Transient AnalysisDesign Calc. No. 2B21-2020Page 19, Revision 0CoreAverageExposure Comments(MWd/MTU)33,206 Break point for exposure-dependent MCPR,limits (NEOC)35,012 Design basis rod patterns toEOFP + 15 EFPD (EOCLB)36,797 End of cycle with FFTR/Coastdown -Maximum Core Exposure (MCE)4 The exposure basis for the defined break points is the core average exposure (CAVEX) values shown aboveregardless of the actual BOC CAVEX value of the As-Loaded Core.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign CaIc. No. 2B21-2020Page 20, Revision 0Table 5Power-Dependent MCPRp Limits5NSS Insertion TimesBOC to < NEOCEOOS Power ATRIUM 1OXM ATRIUM 11 LTACondition (% rated) MCPRp MCPRp100.0 1.34 1.3590.0 1.39 1.3750.0 1.67 1.53Base Case > 65%F < 65%F > 65%F < 65%FOperation 50.0 1.86 1.71 1.89 1.7426.0 2.18 2.04 2.25 2.0826.0 2.20 2.05 2.27 2.1123.0 2.26 2.11 2.33 2.18100.0 1.37 1.3790.0 1.40 1.4050.0 1.67 1.54> 65%F < 65%F > 65%F < 65%FTBVOOS 50.0 1.86 1.71 1.89 1.7426.0 2.18 2.04 2.25 2.0826.0 2.95 2.65 3.13 2.8523.0 3.14 2.85 3.31 3.08100.0 1.34 1.3590.0 1.39 1.3750.0 1.67 1.53> 65%F 5 65%F > 65%F < 65%F50.0 1.86 1.71 1.89 1.7426.0 2.18 2.04 2.25 2.0826.0 2.20 2.05 2.27 2.1123.0 2.26 2.11 2.33 2.18100.0 1.37 1.3790.0 1.40 1.4050.0 1.67 1.57TBVOOS > 65%F < 65%F > 65%F < 65%Fandand 50.0 1.86 1.71 1.89 1.7426.0 2.18 2.04 2.25 2.0826.0 2.95 2.65 3.13 2.8523.0 3.14 2.85 3.31 3.08Limits support operation with any combination of any 1 inoperable SRV, 2 inoperable TBV, up to 40% of theTIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLOMCPRp limits shown above must be adjusted by adding 0.03. SLO not permitted for FHOOS, TBVOOS orMSIVOOS.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportTable 6Power-Dependent MCPRp Limits6TSSS Insertion TimesBOCto<NEOCDesign Calc. No. 2B21-2020Page 21, Revision 0EOOS Power ATRIUM 1OXM ATRIUM 11 LTACondition (% rated) MCPRp MCPRp100.0 1.38 1.3890.0 1.39 1.4050.0 1.68 1.53Base Case > 65%F < 65%F > 65%F < 65%FOperation 50.0 1.88 1.73 1.91 1.7526.0 2.19 2.04 2.26 2.0926.0 2.20 2.05 2.27 2.1123.0 2.26 2.11 2.33 2.18100.0 1.40 1.4190.0 1.43 1.4350.0 1.68 1.56> 65%F < 65%F > 65%F < 65%FTBVOOS 50.0 1.88 1.73 1.91 1.7526.0 2.19 2.04 2.26 2.0926.0 2.95 2.65 3.13 2.8523.0 3.14 2.85 3.31 3.08100.0 1.38 1.3890.0 1.39 1.4050.0 1.68 1.53> 65%F < 65%F > 65%F < 65%F50.0 1.88 1.73 1.91 1.7526.0 2.19 2.04 2.26 2.0926.0 2.20 2.05 2.27 2.1123.0 2.26 2.11 2.33 2.18100.0 1.40 1.4190.0 1.43 1.43TBVOOS 50.0 1.68 1.60and > 65%F < 65%F > 65%F < 65%FFHOOS 50.0 1.88 1.73 1.91 1.7526.0 2.19 2.04 2.26 2.0926.0 2.95 2.65 3.13 2.851 23.0 3.14 2.85 3.31 3.086 Limits support operation with any combination of any 1 inoperable SRV, 2 inoperable TBV, up to 40% of theTIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLOMCPRp limits shown above must be adjusted by adding 0.03. SLO not permitted for FHOOS, TBVOOS orMSIVOOS.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign Caic. No. 2B21-2020Page 22, Revision 0Table 7Power-Dependent MCPRp Limits7NSS Insertion TimesBOC to < EOCLBEOOS Power ATRIUM 1OXM ATRIUM 11 LTACondition (% rated) MCPRp MCPRp100.0 1.35 1.3790.0 1.39 1.3950.0 1.67 1.53Base Case > 65%F < 65%F > 65%F < 65%FOperation 50.0 1.86 1.71 1.89 1.7426.0 2.18 2.04 2.25 2.0826.0 2.20 2.05 2.27 2.1123.0 2.26 2.11 2.33 2.18100.0 1.37 1.3990.0 1.40 1.4250.0 1.67 1.54> 65%F < 65%F > 65%F < 65%FTBVOOS 50.0 1.86 1.71 1.89 1.7426.0 2.18 2.04 2.25 2.0826.0 2.95 2.65 3.13 2.8523.0 3.14 2.85 3.31 3.08100.0 1.35 1.3790.0 1.39 1.3950.0 1.67 1.53> 65%F < 65%F > 65%F < 65%F50.0 1.86 1.71 1.89 1.7426.0 2.18 2.04 2.25 2.0826.0 2.20 2.05 2.27 2.1123.0 2.26 2.11 2.33 2.18100.0 1.37 1.3990.0 1.40 1.42TBVOOS 50.0 1.67 1.57and > 65%F < 65%F > 65%F < 65%FFHOOS 50.0 1.86 1.71 1.89 1.7426.0 2.18 2.04 2.25 2.0826.0 2.95 2.65 3.13 2.8523.0 3.14 2.85 3.31 3.08Limits support operation with any combination of any 1 inoperable SRV, 2 inoperable TBV, up to 40% of theTIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLOMCPRp limits shown above must be adjusted by adding 0.03. SLO not permitted for FHOOS, TBVOOS orMSIVOOS.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportTable 8Power-Dependent MCPRp Limits8TSSS Insertion TimesBOC to < EOCLBDesign CaIc. No. 2B21-2020Page 23, Revision 0EOOS Power ATRIUM 1OXM ATRIUM 11 LTACondition (% rated) MCPRp MCPRp100.0 1.40 1.4190.0 1.40 1.4250.0 1.68 1.53Base Case > 65%F < 65%F > 65%F s 65%FOperation 50.0 1.88 1.73 1.91 1.7526.0 2.19 2.04 2.26 2.0926.0 2.20 2.05 2.27 2.1123.0 2.26 2.11 2.33 2.18100.0 1.42 1.4490.0 1.44 1.4650.0 1.68 1.56> 65%F < 65%F > 65%F < 65%FTBVOOS 50.0 1.88 1.73 1.91 1.7526.0 2.19 2.04 2.26 2.0926.0 2.95 2.65 3.13 2.8523.0 3.14 2.85 3.31 3.08100.0 1.40 1.4190.0 1.40 1.4250.0 1.68 1.53> 65%F 5 65%F > 65%F < 65%F50.0 1.88 1.73 1.91 1.7526.0 2.19 2.04 2.26 2.0926.0 2.20 2.05 2.27 2.1123.0 2.26 2.11 2.33 2.18100.0 1.42 1.4490.0 1.44 1.46TBVOOS 50.0 1.68 1.60and > 65%F < 65%F > 65%F < 65%FFHOOS 50.0 1.88 1.73 1.91 1.7526.0 2.19 2.04 2.26 2.0926.0 2.95 2.65 3.13 2.851 23.0 3.14 2.85 3.31 3.088 Limits support operation with any combination of any 1 inoperable SRV, 2 inoperable TBV, up to 40% of theTIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLOMCPRp limits shown above must be adjusted by adding 0.03. SLO not permitted for FHOOS, TBVOOS orMSIVOOS.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportTable 9Power-Dependent MCPRP Limits9NSS Insertion TimesBOC to < MCE (FFTR/Coastdown)Design CaIc. No. 2B21-2020Page 24, Revision 0EOOS Power ATRIUM 1OXM ATRIUM 11 LTACondition (% rated) MCPR, MCPRPBase Case 100.0 1.36 1.38Operation 90.0 1.39 1.4050.0 1.67 1.53(FFTR/FHOOS > 65%F < 65%F > 65%F  65%Fincluded) 50.0 1.86 1.71 1.89 1.7426.0 2.18 2.04 2.25 2.08(Bounds operation 26.0 2.20 2.05 2.27 2.11with NFWT) 23.0 2.26 2.11 2.33 2.18100.0 1.37 1.39TBVOOS 90.0 1.40 1.4250.0 1.67 1.57(FFTR/FHOOS > 65%F < 65%F > 65%F < 65%Fincluded) 50.0 1.86 1.71 1.89 1.74(Bounds operation 26.0 2.18 2.04 2.25 2.08with NFWT) 26.0 2.95 2.65 3.13 2.8523.0 3.14 2.85 3.31 3.08Limits support operation with any combination of any 1 inoperable SRV, 2 inoperable TBV, up to 40% of theTIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLOMCPRp limits shown above must be adjusted by adding 0.03. SLO not permitted for FHOOS, TBVOOS orMSIVOOS.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign Calc. No. 2B21-2020Page 25, Revision 0Table 10Power-Dependent MCPRP Limits1&deg;TSSS Insertion TimesBOC to < MCE (FFTR/Coastdown)EOOS Power ATRIUM 1OXM ATRIUM 11 LTACondition (% rated) MCPRP MCPRpBase Case 100.0 1.44 1.48Operation 90.0 1.45 1.5150.0 1.68 1.55(FFTR/FHOOS > 65%F < 65%F > 65%F < 65%Fincluded) 50.0 1.88 1.73 1.93 1.7726.0 2.19 2.04 2.28 2.11(Bounds operation 26.0 2.20 2.05 2.29 2.13with NFWT) 23.0 2.26 2.11 2.35 2.20100.0 1.46 1.50TBVOOS 90.0 1.46 1.5150.0 1.70 1.64(FFTR/FHOOS > 65%F < 65%F > 65%F < 65%Fincluded) 50.0 1.90 1.75 1.94 1.78(Bounds operation 26.0 2.21 2.06 2.29 2.12with NFWT) 26.0 2.97 2.67 3.16 2.8823.0 3.16 2.87 3.34 3.1110 Limits support operation with any combination of any 1 inoperable SRV, 2 inoperable TBV, up to 40% of theTIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLOMCPRp limits shown above must be adjusted by adding 0.03. SLO not permitted for FHOOS, TBVOOS orMSIVOOS.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign Caic. No. 2B21-2020Page 26, Revision 0Table 11Flow-Dependent MCPRf Limits11Core Flow ATRIUM 1OXM ATRIUM 11 LTA(% of rated) MCPRf MCPRf0.0 1.70 1.7031.0 1.70 1.7055.0 1.59 1.59100.0 1.20 1.20107.0 1.20 1.2011 Limits valid for all SCRAM insertion times and all core average exposure ranges.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign Caic. No. 2B21-2020Page 27, Revision 0Table 12AREVA Fuel Steady-State LHGRss LimitsPeak ATRIUM 1OXM ATRIUM 11 LTAPellet Exposure LHGR LHGR(GWd/MTU) (kW/ft) (kW/ft)0.0 14.1 12.218.9 14.1 12.274.4 7.4 6.4 Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign CaIc. No. 2B21-2020Page 28, Revision 0Table 13AREVA Fuel Power-Dependent LHGRFACP Multipliers12NSS Insertion TimesBOC to < EOCLBEOOS Power ATRIUM 1OXM ATRIUM 11 LTACondition (% rated) LHGRFACp LHGRFACP100.0 1.00 1.0090.0 1.00 1.0050.0 0.92 0.92Base Case > 65%F < 65%F > 65%F < 65%FOperation 50.0 0.86 0.86 0.86 0.8626.0 0.64 0.66 0.64 0.6626.0 0.64 0.66 0.64 0.6623.0 0.60 0.64 0.60 0.64100.0 1.00 1.0090.0 1.00 1.0050.0 0.92 0.92> 65%F < 65%F > 65%F < 65%FTBVOOS 50.0 0.86 0.86 0.86 0.8626.0 0.64 0.66 0.64 0.6626.0 0.39 0.46 0.39 0.4623.0 0.36 0.42 0.36 0.42100.0 1.00 1.0090.0 1.00 1.0050.0 0.92 0.92> 65%F < 65%F > 65%F < 65%F50.0 0.86 0.86 0.86 0.8626.0 0.64 0.66 0.64 0.6626.0 0.64 0.66 0.64 0.6623.0 0.60 0.64 0.60 0.64100.0 1.00 1.0090.0 1.00 1.0050.0 0.92 0.92TBVOOS> 65%F < 65%F > 65%F < 65%FandFnd 50.0 0.86 0.86 0.86 0.8626.0 0.64 0.66 0.64 0.6626.0 0.39 0.46 0.39 0.4623.0 0.36 0.42 0.36 0.4212 Limits support operation with any combination of any 1 inoperable SRV, 2 inoperable TBV, up to 40% of theTIP channels out-of-service, and up to 50% of the LPRMs out-of-service.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel Design Design CaIc. No. 2B21-2020B2C22 Core Operating Limits Report Page 29, Revision 0Table 14AREVA Fuel Power-Dependent LHGRFACP Multipliers13TSSS Insertion TimesBOC to < EOCLBEOOS Power ATRIUM 1OXM ATRIUM 11 LTACondition (% rated) LHGRFAC, LHGRFAC,100.0 1.00 1.0090.0 1.00 1.0050.0 0.92 0.92Base Case > 65%F < 65%F > 65%F < 65%FOperation 50.0 0.86 0.86 0.86 0.8626.0 0.64 0.66 0.64 0.6626.0 0.64 0.66 0.64 0.6623.0 0.60 0.64 0.60 0.64100.0 1.00 1.0090.0 1.00 1.0050.0 0.92 0.92> 65%F < 65%F > 65%F < 65%FTBVOOS 50.0 0.86 0.86 0.86 0.8626.0 0.64 0.66 0.64 0.6626.0 0.39 0.46 0.39 0.4623.0 0.36 0.42 0.36 0.42100.0 1.00 1.0090.0 1.00 1.0050.0 0.92 0.92> 65%F < 65%F > 65%F < 65%F50.0 0.86 0.86 0.86 0.8626.0 0.64 0.66 0.64 0.6626.0 0.64 0.66 0.64 0.6623.0 0.60 0.64 0.60 0.64100.0 1.00 1.0090.0 1.00 1.0050.0 0.92 0.92TBVOOSand > 65%F < 65%F > 65%F < 65%FFHd 50.0 0.86 0.86 0.86 0.86FHOOS26.0 0.64 0.66 0.64 0.6626.0 0.39 0.46 0.39 0.4623.0 0.36 0.42 0.36 0.4213 Limits support operation with any combination of any 1 inoperable SRV, 2 inoperable TBV, up to 40% of theTIP channels out-of-service, and up to 50% of the LPRMs out-of-service.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign CaIc. No. 2B21-2020Page 30, Revision 0Table 15AREVA Fuel Power-Dependent LHGRFACP Multipliers14NSS Insertion TimesBOC to < MCE (FFTR/Coastdown)EOOS Power ATRIUM 1OXM ATRIUM 11 LTACondition (% rated) LHGRFACp LHGRFACpBase Case 100.0 1.00 1.00Operation 90.0 1.00 1.0050.0 0.92 0.92(FFTR/FHOOS > 65%F < 65%F > 65%F < 65%Fincluded) 50.0 0.86 0.86 0.86 0.8626.0 0.64 0.66 0.64 0.66(Bounds operation 26.0 0.64 0.66 0.64 0.66with NFWT) 23.0 0.60 0.64 0.60 0.64100.0 1.00 1.00TBVOOS 90.0 1.00 1.0050.0 0.92 0.92(FFTR/FHOOS > 65%F < 65%F > 65%F < 65%Fincluded) 50.0 0.86 0.86 0.86 0.86(Bounds operation 26.0 0.64 0.66 0.64 0.66with NFWT) 26.0 0.39 0.46 0.39 0.4623.0 0.36 0.42 0.36 0.4214 Limits support operation with any combination of any 1 inoperable SRV, 2 inoperable TBV, up to 40% of theTIP channels out-of-service, and up to 50% of the LPRMs out-of-service.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign CaIc. No. 2B21-2020Page 31, Revision 0Table 16AREVA Fuel Power-Dependent LHGRFACP Multipliers15TSSS Insertion TimesBOC to < MCE (FFTR/Coastdown)EOOS Power ATRIUM 1OXM ATRIUM 11 LTACondition (% rated) LHGRFACP LHGRFACPBase Case 100.0 1.00 1.00Operation 90.0 1.00 1.0050.0 0.92 0.92(FFTR/FHOOS > 65%F < 65%F > 65%F < 65%Fincluded) 50.0 0.86 0.86 0.86 0.8626.0 0.64 0.66 0.64 0.66(Bounds operation 26.0 0.64 0.66 0.64 0.66with NFWT) 23.0 0.60 0.64 0.60 0.64100.0 1.00 1.00TBVOOS 90.0 1.00 1.0050.0 0.92 0.92(FFTR/FHOOS > 65%F < 65%F > 65%F < 65%Fincluded) 50.0 0.86 0.86 0.86 0.86(Bounds operation 26.0 0.64 0.66 0.64 0.66with NFWT) 26.0 0.39 0.46 0.39 0.4623.0 0.36 0.42 0.36 0.4215 Limits support operation with any combination of any 1 inoperable SRV, 2 inoperable TBV, up to 40% of theTIP channels out-of-service, and up to 50% of the LPRMs out-of-service.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign Calc. No. 2621-2020Page 32, Revision 0Table 17AREVA Fuel Flow-Dependent LHGRFACf Multipliers16Core Flow ATRIUM 10XM ATRIUM 11 LTA(% of rated) LHGRFACf LHGRFACf0.0 0.58 0.5831.0 0.58 0.5875.0 1.00 1.00107.0 1.00 1.0016 Multipliers valid for all SCRAM insertion times and all core average exposure ranges.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportDesign CaIc. No. 2B21-2020Page 33, Revision 0Table 18AREVA Fuel Steady-State MAPLHGRss Limits17' 18Average Planar Exposure ATRIUM 1OXM ATRIUM 11 LTA(GWd/MTU) MAPLHGR MAPLHGR(kW/ft) (kW/ft)0.0 13.1 10.515.0 13.1 10.567.0 7.7 5.917 AREVA Fuel MAPLHGR limits do not have a power or flow dependency. Thus, the ATRIUM 1OXM andATRIUM 11 MAPFACp and the MAPFACf multipliers have a constant value of 1.0 under all conditions.18 ATRIUM 1OXM and ATRIUM 11 MAPLHGR limits must be adjusted by a 0.80 multiplier when in SLO. SLOnot permitted for FHOOS, TBVOOS or MSIVOOS.
Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportFigure 1Stability Option III Power/Flow MapOPRM Operable, Two Loop Operation, 2923 MWtDesign Calc. No. 2B21-2020Page 34, Revision 0I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3:]120.0110.0100.090.080.070.060.050.040.030.020.010.00.0Minimum Maximum(MELLL) (ICF)Core CorePower Flow Flowi Mlbs/hr Mlbs/hr100 76.19 80.4799 75.04 80.4798 73.89 80.4797 72.75 80.4796 71.61 80.4795 70.49 80.4794 69.36 80.4793 68.25 80.4792 67.13 80.4791 66.03 80.4790 64.93 80.4789 63.83 80.4788 62.74 80.4787 61.66 80.5186 60.58 80.6085 59.50 80.6984 58.43 80.7983 57.37 80.9082 56.31 81.0581 55.25 81.2180 54.20 81.3679 53.16 81.5178 52.12 81.6777 51.08 81.8276 50.05 81.9875 49.02 82.1374 48.00 82.2973 46.98 82.4472 45.96 82.6071 44.95 82.7570 43.94 82.9169 42.94 83.0668 41.94 83.2267 40.95 83.3766 39.96 83.5265 38.97 83.6864 37.99 83.8363 37.01 83.9962 36.04 84.1461 35.06 84.3060 34.10 84.4559 33.13 84.6158 32.17 84.700.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbslhr Core Flow0 10 20 30 4050 60 7080 90 100 110 120 %Core Flow
 
==Reference:==
0B21-1015, Revision 7 Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportFigure 2Stability Option III Power/Flow MapOPRM Inoperable, Two Loop Operation, 2923 MWtDesign CaIc. No. 2B21-2020Page 35, Revision 0I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3120.0110.0100.090.080.070.0o 60.050.040.030.020.010.00.0Minimum Maximum(MELLL) (ICF)Core CorePower Flow Flow% Mlbs/hr Mlbs/hr100 76.19 80.4799 75.04 80.4798 73.89 80.4797 72.75 80.4796 71.61 80.4795 70.49 80.4794 69.36 80.4793 68.25 80.4792 67.13 80.4791 66.03 80.4790 64.93 80.4789 63.83 80.4788 62.74 80.4787 61.66 80.5186 60.58 80.6085 59.50 80.6984 58.43 80.7983 57.37 80.9082 56.31 81.0581 55.25 81.2180 54.20 81.3679 53.16 81.5178 52.12 81.6777 51.08 81.8276 50.05 81.9875 49.02 82.1374 48.00 82.2973 46.98 82.4472 45.96 82.6071 44.95 82.7570 43.94 82.9169 42.94 83.0668 41.94 83.2267 40.95 83.3766 39.96 83.5265 38.97 83.6864 37.99 83.8363 37.01 83.9962 36.04 84.1461 35.06 84.3060 34.10 84.4559 33.13 84.6158 32.17 84.700.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow0 10 2030 4050 60 7080 90 100 110 120 % Core Flow
 
==Reference:==
0B21-1015, Revision 7 Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportFigure 3Stability Option III Power/Flow MapOPRM Operable, Single Loop Operation, 2923 MWtDesign Calc. No. 2B21-2020Page 36, Revision 0This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3120.0110.0100.090.080.070.0o 60.050.040.030.020.010.00.0Minimum Maximum(MELLL) (ICF)Core CorePower Flow FlowMlbs/hr Mlbs/hr100 76.19 80.4799 75.04 80.4798 73.89 80.4797 72.75 80.4796 71.61 80.4795 70.49 80.4794 69.36 80.4793 68.25 80.4792 67.13 80.4791 66.03 80.4790 64.93 80.4789 63.83 80.4788 62.74 80.4787 61.66 80.5186 60.58 80.6085 59.50 80.6984 58.43 80.7983 57.37 80.9082 56.31 81.0581 55.25 81.2180 54.20 81.3679 53.16 81.5178 52.12 81.6777 51.08 81.8276 50.05 81.9875 49.02 82.1374 48.00 82.2973 46.98 82.4472 45.96 82.6071 44.95 82.7570 43.94 82.9169 42.94 83.0668 41.94 83.2267 40.95 83.3766 39.96 83.5265 38.97 83.6864 37.99 83.8363 37.01 83.9962 36.04 84.1461 35.06 84.3060 34.10 84.4559 33.13 84.6158 32.17 84.700.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow0 10 20 30 40 50 60 7080 90 100 110 120 % Core Flow
 
==Reference:==
0B21-1015, Revision 7 Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportFigure 4Stability Option III Power/Flow MapOPRM Inoperable, Single Loop Operation, 2923 MWtDesign Calc. No. 2B21-2020Page 37, Revision 0This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3120.0110.0100.090.080.070.0o 60.050.040.030.020.010.00.0Minimum Maximum(MEULL) (ICF)Core CorePower Flow Flow%e M b___hr_ Mlbs/hr100 76.19 80.4799 75.04 80.4798 73.89 80.4797 72.75 80.4796 71.61 80.4795 70.49 80.4794 69.36 80.4793 68.25 80.4792 67.13 80.4791 66.03 80.4790 64.93 80.4789 63.83 80.4788 62.74 80.4787 61.66 80.5186 60.58 80.6085 59.50 80.6984 58.43 80.7983 57.37 80.9082 56.31 81.0581 55.25 81.2180 54.20 81.3679 53.16 81.5178 52.12 81.6777 51.08 81.8276 50.05 81.9875 49.02 82.1374 48.00 82.2973 46.98 82.4472 45.96 82.6071 44.95 82.7570 43.94 82.9169 42.94 83.0668 41.94 83.2267 40.95 83.3766 39.96 83.5265 38.97 83.6864 37.99 83.8363 37.01 83.9962 36.04 84.1461 35.06 84.3060 34.10 84.4559 33.13 84.6158 32.17 84.700.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow
 
==Reference:==
0B21-1015, Revision 7 Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportFigure 5Stability Option III Power/Flow MapOPRM Operable, FWTR, 2923 MWtDesign CaIc. No. 2B21-2020Page 38, Revision 0I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3120.0110.0100.090.080.070.01 60.050.040.030.020.010.00.0Minimum Maximum(MELLL) (ICF)Core CorePower Flow FlowMlbs/hr Mlbs/hr100 76.19 80.4799 75.04 80.4798 73.89 80.4797 72.75 80.4796 71.61 80.4795 70.49 80.4794 69.36 80.4793 68.25 80.4792 67.13 80.4791 66.03 80.4790 64.93 80.4789 63.83 80.4788 62.74 80.4787 61.66 80.5186 60.58 80.6085 59.50 80.6984 58.43 80.7983 57.37 80.9082 56.31 81.0581 55.25 81.2180 54.20 81.3679 53.16 81.5178 52.12 81.6777 51.08 81.8276 50.05 81.9875 49.02 82.1374 48.00 82.2973 46.98 82.4472 45.96 82.6071 44.95 82.7570 43.94 82.9169 42.94 83.0668 41.94 83.2267 40.95 83.3766 39.96 83.5265 38.97 83.6864 37.99 83.8363 37.01 83.9962 36.04 84.1461 35.06 84.3060 34.10 84.4559 33.13 84.6158 32.17 84.700.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow0 10 20 30 40 50 60 7080 90 100 110 120 % Core Flow
 
==Reference:==
0B21-1015, Revision 7 Duke Energy, Nuclear Fuels Engineering, Nuclear Fuel DesignB2C22 Core Operating Limits ReportFigure 6Stability Option III Power/Flow MapOPRM Inoperable, FWTR, 2923 MWtDesign Calc. No. 2B21-2020Page 39, Revision 0I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3120.0110.0100.090.080.070.0o 60.050.040.030.020.010.00.0Minimum Maximum(MELLL) (ICF)Core CorePower Flow Flow% Mlbs/hr Mlbs/hr100 76.19 80.4799 75.04 80.4798 73.89 80.4797 72.75 80.4796 71.61 80.4795 70.49 80.4794 69.36 80.4793 68.25 80.4792 67.13 80.4791 66.03 80.4790 64.93 80.4789 63.83 80.4788 62.74 80.4787 61.66 80.5186 60.58 80.6085 59.50 80.6984 58.43 80.7983 57.37 80.9082 56.31 81.0581 55.25 81.2180 54.20 81.3679 53.16 81.5178 52.12 81.6777 51.08 81.8276 50.05 81.9875 49.02 82.1374 48.00 82.2973 46.98 82.4472 45.96 82.6071 44.95 82.7570 43.94 82.9169 42.94 83.0668 41.94 83.2267 40.95 83.3766 39.96 83.5265 38.97 83.6864 37.99 83.8363 37.01 83.9962 36.04 84.1461 35.06 84.3060 34.10 84.4559 33.13 84.6158 32.17 84.700.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow0 10 20 30 40 50 60 7080 90 100 110 120 % Core Flow
 
==Reference:==
0B21-11015, Revision 7}}

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