GNRO-2016/00017, Core Operating Limits Report Cycle 21

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Core Operating Limits Report Cycle 21
ML16084A978
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 03/24/2016
From: Nadeau J
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2016/00017
Download: ML16084A978 (22)
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Text

  • '"':P Entergy GNRO-2016/00017March24,2016 U.S.Nuclear Regulatory Commission Attn: DocumentControlDeskWashington,DC20555-0001 Entergy Operations, Inc.P.O.Box756PortGibson,MS39150 James NadeauManager,RegulatoryAssuranceGrandGulfNuclearStationTel.(601)437-2103

SUBJECT:

DearSirorMadam:

Core OperatingLimitsReportCycle21GrandGulf NuclearStation,Unit1DocketNo.50-416LicenseNo.NPF-29 Entergy OperationsInc.(Entergy),is submittingarevisedCore OperatingLimitsReport(COLR)forGrandGulf NuclearStation(GGNS)asrequiredbyGGNS Technical Specification (TS)5.6.5.d.TherevisedCOLRisforCycle21operation.Theanalyticalmethodsusedto determinetheCycle21CoreOperatingLimitswere previouslyapprovedbythe Nuclear Regulatory Commission(NRC)andarelistedinGGNSTS5.6.5.Thislettercontainsnonew commitments.Shouldyouhaveany questionsorrequireadditionalinformation,pleasecontactJamesNadeauat 601-437-2103.

Sincerely, JJN/tmc

Attachment:

CoreOperatingLimitsReport(COLR)Cycle21cc:(seenextpage)

GNRO-2016/00017Page2of2 cc: U.S.Nuclear Regulatory CommissionATTN:Mr.JimKim, NRR/DORL (w/2)MailStopOWFN881Rockville,MD 20852-2738 U.S.Nuclear Regulatory CommissionATTN:Mr.MarcDapas(w/2)

Regional Administrator,RegionIV1600EastLamarBoulevardArlington,TX76011-4511 NRC Senior Resident InspectorGrandGulf Nuclear StationPortGibson,MS39150 Attachment to GNRO-2016/00017 Core OperatingLimitsReport(COLR)Cycle21 Grand Gulf Nuclear Station Core Operating Limits Report COLRPage1 LBDCR 16034 CORE OPERATING LIMITS REPORT REASON FOR REVISION This reV1Slon provides the Cycle 21 core operating limits.These limits are basedona core power of 4408 MWt.TABLE OF CONTENTS 1.0 PURPOSE 3 2.0 SCOPE 3

3.0 REFERENCES

4-6 3.1 Background References 4 3.2 Current Cycle References 4 3.3 Methodology References 5-6 4.0 DEFINITIONS 7 5.0 GENERAL REQUIREMENTS 8-9 5.1 Averaqe Planar Linear Heat Generation Rates 8 5.2 Minimum Critical Power Ratio 8 5.3 Linear Heat Generation Rate 9 5.4 Stability 9 5.5 Applicability 9 5.6 Limitations and Conditions 10 Table 1 OPRM Upscale CDA Amplitude Discriminator 11 Setpoint Table 2 BSP Endpoints for Normal Feedwater Temperature 11 Table 3 BSP Endpoints for Reduced Feedwater 11 Temperature Table 4 ABSP Setpoints for theScramRegion 11 Table 5 Margin toThermalOverpowerand Mechanical 11 Overpower Limits Figure(s)1 APLHGR Operating Limits 12 Figure(s)2 MCPR Operating Limits 13-15 Figure(s)3 LHGR Operating Limits 16-17 Figure 4 Backup Stability Protection Region Boundaries 18 for Normal Feedwater Temperature Figure 5 Backup Stability Protection Region Boundaries 19 for Reduced Feedwater Temperature COLRPage2 LBDCR 16034 CORE OPERATING LIMITS REPORT 1.0 PURPOSE On October 4, 1988, the NRC issued Generic Letter 88-16[3.1.1]encouraging licensees to remove cycle-specific parameter limits from Technical Specifications and to place these limits in a formal report to be prepared by the licensee.Aslongas the parameter limits were developed with methodologies, the letter indicated that thiswouldremove unnecessary burdens on licensee and NRC resources.

On October29,1992, Entergy Operations submitted a Proposed Amendment to the Grand Gulf Operating License requesting changes to the GGNS Technical Specifications to remove certain reactor physics parameter limits thatchangeeach fuel cycle[3.1.2].This amendment committed to placing these operating limits in a separate Core Operating Limits Report (COLR)which is defined in Technical Specifications.

This PCOL was approved by the NRC by SER dated January21,1993[3.1.3].The COLR is controlledasa License Basis Document and revised accordingly for each fuel cycle or remaining portion of a fuel cycle.Any revisions to the COLRmustbe submitted to the NRC for information as requiredbyTechSpec 5.6.5 and tracked by Licensing Commitment 29132.This COLR reports the Cycle 21 core operating and stability setpoint confirmation and regions.2.0 SCOPE As defi ned in Techni cal Speci fi cati on 1.1, the COLR is the GGNS document that provides the core operating limits for the current fuel cycle.This document is prepared in accordance with Technical Specification 5.6.5 for each reload cycle using NRC-approved analytical methods.The Cycle 21 core operating and stability limits included in this report are:*the Average Planar Linear Heat Generation Rate (APLHGR),*the Minimum Critical Power Ratio (MCPR)(including EOC-RPT inoperable),*the Linear Heat Generation Rate (LHGR)limit, and*the DSS-CD stability setpoint confirmation and regions.COLR Page 3 LBDCR 16034 CORE OPERATING LIMITS REPORT

3.0 REFERENCES

This section contains the background, cycle-specific, and methodology references used in the safety analysis of Grand Gulf Cycle 21.3.1 Background References 3.1.1 MAEC-88/0313, Generic Letter 88-16,"Removal of Cycle-Specific Parameter Limits from Technical Specifications", October4,1988.3.1.2 GNRO-92-00093, Proposed Amendment to Grand Gulf Operating License,92/07, dated October 29, 1992.3.1.3 GNRI-93-0008, Amendment 106 to Grand Gulf Operating License, January 21, 1993.3.1.4 GEXI 2000-00116, K.V.Walters to J.B.Lee,"Technical Specification and COLR References for Grand Gulf Nuclear Station and River Bend Station," November3,2000.3.2 Current Cycle References 3.2.1 ECH-NE-16-00004 Revision 0, Supplemental Reload Licensing Report for Grand Gulf Nuclear StationReload20 Cycle 21, dated March 2016.3.2.2 ECH-NE-I0-00021 Revision 4, GNF2 Fuel Design Cycle-Independent Analyses for Entergy Grand Gulf Nuclear Station, dated November 2013.3.2.3 ECH-NE-16-00006 Revision0,FuelBundle Information Report for Grand Gulf Nuclear StationReload20 Cycle 21, dated October 2015.3.2.4 NEDC-32910P, Revision1,Grand Gulf Nuclear Station SAFER/GESTR-LOCA Accident Analysis With Relaxed ECCS Parameters, dated October 1999.3.2.5 GGNS-NE-I0-00022 Revision0,Grand Gulf Nuclear Station MELLLA+Task T0407.ECCS-LOCA Performance, dated September 2012.3.2.6 GGNS-SA-09-00002 Revision1,Grand Gulf Nuclear Station GNF2 ECCS-LOCA Evaluation, datedDecember2009.

3.2.7 NEDC-33173P-A, Rev.4, Application of GE Methods to Expanded Operating Domains, dated November 2012 3.2.8 NEDC-33006P-A, Rev.3, GE BWR Maximum ExtendedLoadLine Limit Analysis Plus, dated June2009 3.2.9 ECH-NE-16-00010, Revision 0, GGNS Cycle 21 GESTAR Assessment, dated March 2016.3.2.10 ECH-NE-14-00014 Revision 2, GGNS RF19 Bundle Reconstitution ReportBundle GEQ830, dated April 2015.COLRPage4 LBDCR 16034 CORE OPERATING LIMITS REPORT 3.3 Methodology References The Technical Specifications (TS)supported by each methodology reference are provided in brackets ({}).3.3.1 XN-NF-81-58(P)(A)

Revision2and Supplements1and2,"RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company,March1984{TS 3.2.1, TS 3.2.2, TS 3.2.3}.3.3.2 XN-NF-85-67(P)(A)

Revision 1,"Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, September 1986{TS 3.2.3}.3.3.3 EMF-85-74(P)

Revision 0 Supplement 1 (P)(A)and Supplement 2 (P)(A),"RODEX2A (BWR)Fuel Rod Thermal-Mechanical EvaluationModel,Siemens Power Corporation," February 1998{TS 3.2.3}.3.3.4 ANF-89-98(P)(A)

Revision1and Supplement 1,"Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995{TS 3.2.3}.3.3.5 Deleted 3.3.6 XN-NF-80-19(P)(A)

Volume1and Supplements1and2,"Exxon Nuclear Methodology for Boiling Water Reactors-Neutronic Methods forDesignand Analysis, Exxon NuclearCompany,"March1983

{TS 3.2.1, TS 3.2.2, TS 3.2.3}.3.3.7 XN-NF-80-19(P)(A)

Volume 4 Revision1,"Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon NuclearCompany,"June1986

{TS 3.2.1, TS 3.2.2, TS 3.2.3}.3.3.8 EMF-2158(P)(A)

Revision 0,"Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-MICROBURN-B2,SiemensPower Corporation," October 1999{TS 3.2.2, TS 3.2.3}.3.3.9 XN-NF-80-19(P)(A)

Volume 3 Revision2,"Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987{TS 3.2.2}.3.3.10XN-NF-84-105(P)(A), Volume1and Supplements1and2,"XCOBRA-T:

A Computer Code for BWR Transient Thermal Hydraulic Core Analysis," Exxon Nuclear Company, February 1987{TS 3.2.2}.3.3.11 ANF-524(P)(A)

Revision2and Supplements1and2,"ANF Critical Power Methodology for Boiling Water Reactors," Advanced Nuclear Fuels Corporation, November 1990{TS 3.2.2}.3.3.12 ANF-913 (P)(A), Volume 1, Revision1and Volume 1 Supplements2,3and4,"COTRANSA2:AComputerProgram for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation,August1990

{TS 3.2.2}.3.3.13 XN-NF-825(P)(A)

Supplement 2,"BWR/6 Generic Rod Withdrawal Error Analysis, MCPR p for Plant Operation Within the Extended Operating Domain," Exxon Nuclear Company, October 1986{TS 3.2.2}.3.3.14 ANF-1358(P)(A)

Revision3,"TheLoss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005{TS 3.2.2}.COLRPage5 LBDCR 16034 CORE OPERATING LIMITS REPORT 3.3 Methodology References (continued) 3.3.15 3.3.16 3.3.17 3.3.18 3.3.19 3.3.20 3.3.21 3.3.22 3.3.23 3.3.24EMF-1997(P)(A)

Revision 0,"ANFB-I0 Critical Power Correlation," Siemens Power Corporation, July 1998{TS 3.2.2}.EMF-1997(P), Supplement I(P)(A), Revision 0,"ANFB-I0 Critical Power Correlation:HighLocal Peaking Results,SiemensPower Corporation," July 1998{TS 3.2.2}.EMF-2209(P)(A)

Revision 2,"SPCB Critical Power Correlation, Siemens Power Corporation," September 2003{TS 3.2.2}.EMF-2245(P)(A)

Revision 0,"Application ofSiemensPower Corporation's Critical Power Correlations to Co-Resident Fuel," Siemens Power Corporation, August 2000{TS 3.2.2}.EMF-2361 (P)(A)Revision 0,"EXEM BWR-2000 ECCS Evaluation Model," Framatome ANP Richland, Inc., May 2001{TS 3.2.1}.Deleted Deleted NEDC-33383P, Revision 1,"GEXL97 Correlation Applicable to ATRIUM-I0 Fuel," June, 2008{TS 3.2.2}.EMF-2292(P)(A)

Revision 0,"ATRIUM-I0:AppendixK Spray Heat Transfer Coefficients,SiemensPower Corporation," September 2000{TS 3.2.1}.Deleted NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel (GESTAR-II)

{TS 3.2.1, TS 3.2.2, TS 3.2.3}.NEDO-33075-A, Revision 8, Licensing Topical Report, Boiling Water Reactor Detect and Suppress Solution-Confirmation Density, November 2013{TS 3.2.2, 3.3.1.1}NEDO-33612-A, Revision 0, Safety Analysis Report for GGNS Maximum Extended Load Line Limit Analysis Plus, September 2013{TS 3.2.2, 3.3.1.1}3.3.28*GGNS-NE-I0-00076 Revision 0 (GEH 0000-012101122-RO), GGNS EPU Option B Scram Times, dated September 2010.{TS 3.2.2}*Note: These references are applicable when GE fuel is in the reactor.COLRPage6 LBDCR 16034 4.0 CORE OPERATING LIMITS REPORT DEFINITIONS 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 4.10 4.11 4.12 4.13 4.14 4.15 Average Planar Linear Heat Generation Rate (APLHGR)-the APLHGR shall be applicable to a specific planar height and is equal to the sum of the linear heat generation rates for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the specified height.Average Planar Exposure-the Average Planar Exposure shall be applicable to a specific planar height and is equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the specified height.Critical Power Ratio (CPR)-the ratio of that power in the assembly, which is calculated by application of the fuel vendor's appropriate boiling correlation, to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating.

Core Operating Limits Report (COLR)-TheGrand Gulf Nuclear Station specific document that provides core operating limits for the current reload cycle in accordance with Technical Specification 5.6.5.Linear Heat Generation Rate (LHGR)-the LHGR shall be the heat generation per unit length of fuel rod.It is the integral of the heat flux over the heat transfer area associated with the unit length.Minimum Critical Power Ratio (MCPR)-the MCPR shall be the smallest CPR which exists in the core.MCPR Safety Limit-the minimum value of the CPR at which the fuel could be operated with the expected number of rods in boiling transition not exceeding 0.1%of the fuel rods in the core.OscillationPowerRange Monitor (OPRM)-Provides automatic detection and suppression of reactor core thermal-hydraulic instabilities through monitoring neutron flux changes.Backup Stability Protection (BSP)ScramRegion-The area of the core power and flow operatingdomainwhere the reactor is susceptible to reactor instabilities under conditions exceeding the licensing basis of the current reactor system.An immediatemanualscram is required upon entry.Backup Stability Protection (BSP)Controlled EntryRegion-The area of the corepowerand flow operatingdomainwhere the reactor is susceptible to reactor instabilities.

Compliance with at least one alternate stability control is required upon entry.AutomatedBackup Stability Protection (ABSP)ScramRegion-An automated reactor scram region that bounds the BSPScramRegionand is initiated by the APRM flow-biased scram setpoint upon entry.End of Rated (EOR)-The Cycle exposure corresponding to all rods out, 100%power, 100%flow,andnormal feedwater temperature

[3.2.1].Middle of Cycle (MOC)-The Cycle 21 MOC Core Average Exposure (CAE)is EOR-2,752 MWdjST[3.2.1].End of Cycle (EOC)-The Cycle 21 EOC CAE is 31,283 MWdjST[3.2.1].Maximum Extended Load Line Limit Analysis Plus (MELLLA+)-The GGNS MELLLA+operating domain is depicted in Figure 4.COLRPage7 LBDCR 16034 CORE OPERATING LIMITS REPORT 5.0 GENERAL REQUIREMENTS 5.1 Average Planar Linear Heat Generation Rates Consistent with Technical Specification 3.2.1, all APLHGRs shall not exceed the exposure-dependent limits reported in Figure 1-1[3.2.1].5.2 Minimum Critical Power Ratio Consistent with Technical Specification 3.2.2, the greater than the limits reported in Figure(s)2as exposure,andscram speed.[3.2.1, 3.2.2, 3.3.28].the power-dependent MCPR shall be determined based as follows.[3.3.28]MCPR shall be equal to or functions of power, flow, For operation at powersonscram time surveillance data 1)If the average scram time satisfies the following:

rAVh'::;rB'then the power dependent MCPR shall be equal to or greater than the Option B limits reported in Figure(s)2asa function of exposure.2)If the average scram time TAV/:'>r B and T::;0.2, then the power-dependent MCPR shall be equal to or greater than the Tau 0.2 limits reported in Figure(s)2asa function of exposure, 3)If the average scram time rAVE>t Ban d t>0.2, then the power-dependent MCPR shall be equal to or greater than the Option A limits reported in Figure(s)2asa function of exposure.In the above equations:=average scram time to the 20%insertion position as calculated by equation 1 of Reference 3.3.28, r B adjusted analysis mean scram time for 20%insertion as calculated by equation 3 of Reference 3.3.28 and t: A VI-'-r B r=-, r A-r B where r A the technical specification limit on core average scram time to the 20 percent insertion position (0.503 seconds).COLRPage8 LBDCR 16034 CORE OPERATING LIMITS REPORT The limits determined above support operation with Turbine Bypass Valves Out of Service as described in Technical Specification 3.7.7.Additional MCPR operating limits are provided to support operation with EOC-RPT inoperable as described in Technical Specification 3.3.4.1.5.3 Linear Heat Generation Rate Consistent with Technical Specification 3.2.3, the LHGRs for any GNF2 fuel rod at any axial location shall not exceed the nodal exposure-dependent limits reported in Reference 3.2.3 multiplied by the smaller of either the power-dependent ordependent LHGR factors reported in Figures3-1and 3-2, respectively

[3.2.1].The limits determined above support operation with Turbine Bypass Valves Out of Service as described in Technical Specification 3.7.7.5.4 Stability The OPRM Upscale Confirmation Density Algorithm (CDA)Amplitude Discriminator setpoint is reported in Table 1.TheBackup Stability Protection (BSP)regions boundaries are reported in Figures 4and5[3.2.1].BSP measures support operation with the OPRM upscale trip function inoperable as described in Technical Specification 3.3.1.1 Condition J.The endpoints for the BSP region boundaries are provided for normal (NFWT)and reduced (RFWT)feedwater temperature operations in Tables2and3, respectively.

Figures4and5 depict the BSP region boundaries for NFWT and RFWT operations.

Note that Figures 4and5 also depict the MELLLA+and MELLLA domains, consistent with feedwater temperature operating limitations.

The ABSP APRM SimulatedThermalPower(STP) setpoints associated with the ABSP Scram Region are provided in Table4.The ABSP setpoints are applicable to TLO and SLO, and to bothnormaland reduced feedwater temperature operations.

The BSPBoundaryand Manual BSP region boundaries for normal feedwater temperature operations are valid for reductions in normal feedwater temperature as muchas(and including)

-10.0 of.5.5 Applicability The following core operating limits are applicable for operation in the Maximum Extended Operting Domain (MEOD), with Feedwater Heaters Out of Service (FHOOS), TurbineBypassOut of Service (TBVOOS), and EOC-RPT inoperable.

For operation with EOC-RPT inoperable, the alternate MCPR limits described in Section 5.2abovemust be implemented.

For single-loop operation (SLO), the following additional requirementsmustbe satisfied.

1.THE APLHGRs shall not exceed the exposure-dependent limits determined in accordance with Section 5.1 reducedbya 0.83 SLO multiplier.

[3.2.1].2.THE LHGRs shall not exceed the smaller of the nodal exposure-dependent limits determined in accordance with Section 5.3 above or the nodal exposure-dependent limits reported in Reference 3.2.3 reducedbya 0.83 SLO multiplier

[3.2.1].3.The MCPR shall be equal to or greater than the limits determined in accordance with Section 5.2 above increased by 0.00 to account for the difference between the two-loop and single-loop MCPR safety limits for the allowable range of single-loop operation[3.2.1].COLRPage9 LBDCR 16034 CORE OPERATING LIMITS REPORT Note that the above described limits are applicable to all bundles in the core;however,a re-inserted bundle (GEQ830-reconstituted in RF19)requires a multiplier to account for uncertainties in its predicted neutronic response during operation.

After re-constitution, the vendor documented analyses to determine its performance in C21[3.2.10];which concluded that a 10%setdown was required for the TLs of GEQ830 (MFLCPR, MFLPD, MAPRAT).This additional factorhasbeen incorporated into the C21 core monitoring system.5.6 Limitations and Conditions As required by Limitation and Condition 9.10/9.11 of licensing topical report33173P-A[3.2.7], the limitingThermaland Mechanical Overpower results are reported in Table5.The results aresummarizedasa percent margin to both of these limits.The results are confirmed to meet the required 10%margin to the design limits[3.2.1].As required by Limitation and Condition 12.10.b of licensing topical report33006P-A[3.2.8], the off-rated limits assumed in the ECCS-LOCA analyses are confirmed to be consistent with the cycle-specific off-rated LHGR multipliers provided Figures3-1and 3-2.These off-rated LHGR multipliers provide adequate protection for MELLLA+operation.

As required by Limitation and Condition 12.5.c of licensing topical report33006P-A[3.2.8], the plant specific power/flow map specifying the GGNS licensed MELLLA+operating domain is included as Figure 4.As required by Limitation and Condition 12.5.b of licensing topical report33006P-A[3.2.8], operation with Feedwater Heaters Out of Service (FWHOOS)is prohibited while in the MELLLA+operating domain[3.2.1].In addition, as required by Limitation and Condition 12.5.a of licensing topical report NEDC-33006P-A

[3.2.8], and described in GGNS TS 3.4.1 LCO, SLO is prohibited in the MELLLA+operating domain[3.2.1].Therefore, operations with RFWT and/or SLO must adhere to the operating domain shown in Figure 5.Table 1 OPRM Upscale CDA Amplitude Discriminator Setpoint Amplitude Discriminator Trip 1.10 Table 2 BSP Endpoints for Normal Feedwater Temperature Endpoint Power(%)Flow(%)Definition Al 72.3 44.2ScramReaion Boundary, HFCL B1 37.5 25.5ScramReaion Boundary, NCL A2 67.3 50.0 Controlled Entrv Reaion Boundary.HFCL B2 26.4 24.4 Controlled Entry Reaion Boundary, NCL A3 100.0 85.5 BSP Boundary Intercept, HFCL B3 81.0 67.2 BSP Boundary Interceot, MELLLA Line COLRPage10 LBDCR 16034 CORE OPERATING LIMITS REPORT Table 3 BSP Endpoints for Reduced Feedwater Temperature Endpoint Power(%)Flow(%)Definition Al 63.0 44.8ScramRegion Boundary, HFCL Bl 30.0 24.8ScramReqion Boundary, NCL A2 67.3 50.0 Controlled Entry Region Boundary, HFCL B226.424.4 Controlled Entry Reqion Boundary, NCL Table 4 ABSP Setpoints for the Scram Region Parameter Symbol Value Slope of ABSP APRM flow-biased trip linear segment m,nTn 0.64 ABSP APRM flow-biased trip setpoint power intercept.

p 31.0%RTp 1 ConstantPowerLine for Trip from zero Drive Flow to BSP-TRIP Flow Breakpoint.

ABSP APRM flow-biased trip setpoint drive flow WBSP-TRIP 39.0%RDP intercept.

ConstantFlowLine for Trip.Flow Breakpoint value WBSP-BREAK 2.0%RDP 1.RTP-RatedThermalPower 2.RDF-Reclrculatlon Drlve Flow COLRPage11 Table 5 Margin to ThermalOverpowerandMechanicalOverpower Limits Criteria GNF2 ThermalOverpowerMargin55.2%

MechanicalOverpowerMargin56.2%

LBDCR 16034 CORE OPERATING LIMITS REPORT 14 0.00,13.78 1312-11=-3:10--:.0::9-C>:I:...J8-a.<<:::i!:7-6-5--4-, 0 10 17.52,13.78 20 30 40 50 60 70 COLRPage12 Average Planar Exposure (GWd/ST)Figure 1-1 Maximum Average Planar Linear Heat Generation Rate Note: Actual Limits described in Sections5.1and5.5 LBDCR 16034 CORE OPERATING LIMITS REPORT 100.1.47 100 90 OptionB 80 70 Option A 60 I 50!40 35.4,1.92 35.4.2.10 I 30 35.4,1.67 20 21.8.2.26 21.8.2.13 I 10 Per Section 5.5, bundle GEQ830 uses these limitsw/10%setdown 2.3 T 2.2-r r 2.1 T 2.0 T 1.91.8 t c:: r1.7 T1.6+:Ie f 1.5 r r 1.4 1;: l 1.1 T 1.0+r-........

oCorePower (%Rated)FigureCycle21 Power-Dependent MCPR LimitseocreMoe 100.1.50Tau=0.2 I90100 Option B 80 I 70 , 60 50 40 Option A 40,1.67 SO,1.67 58.1.65 1 70.1.62 I 3035.4,1.67 35.4,1.66 I 20 21.8,2.13 21.8,2.2650%Core Flow I 10 Per Section 5.5, bundle GEQ830 uses these limits wit 0%setdown 2.3 T f 2.2 T 2.1**t**t 2.0+r 1.9+-t 1.8.....l i.0: it 1.7+a..t1.6 T 1.5 T 1.4+1.3+l'1.2-t--1.1 T r'1.0+1 o Core Power (%Rated)Figure 2-2 Cycle 21 Power-Dependent MCPR Limits BOC to MOe With EOC-RPT Inoperable COLRPage13 LBDCR 16034 CORE OPERATING LIMITS REPORT Per Section 5.5, bundle GEQ830 uses these limitsw/10%setdown 2.3..2.2 2.1 2.0*1.9 1.8 0.:1.7.ct a.u 1.6:E 1.5 1.4 1.31.2.1.1 21.8,2.26 21.8.2.15/>50%Core Flow 35.4.2.12 35.4.1.9740.1.74 40.1.66'50.1.62 58.1.58 Tau: 0.2 OptionS 100.1.52 100.1.44 100,1.42 1.0-***-..*---*..-t----"*-*--*t---

.....--r*-..*-**-..-l---"--t-

..*-*......-**t..--*...

__*+*..-......*........+**_..-........*****_*1 a102030405060708090100 Core Power (%Rated)Figure 2-3 Cycle 21 Power-Dependent MCPR Limits MOCto EOC....*-1 100 90 80 Option A I 70 70,1.69 50.1.74 58.1.72 50.1.63 I 40 40,1.74 35.4.1.97 40,1'.6650,1.6258.

1.58Tau=0.2/>50%Core Flow 35.4.2.12 I 30 21.8,2.15 21.8.2.26 Per Section 5.5, bundle GEQ830 uses these limits wit 0%setdown 1.4*f*1.3 t 1.2 t ,...---------------------------, 1.1+'------'t 1.0

-+--'---t----'--

..+I--.........--t o10205060 2.3 T 2.2+21 1 2.0 T 1.9'r l5 1.6 1-1.5 f Core Power (%Rated)Figure 24 Cycle 21 Power-Dependent MCPR Limits MOCtoEOC with EOC-RPT Inoperable COLRPage14 LBDCR 16034 CORE OPERATING LIMITS REPORT 1.4020.1.3930.1.39 1.35 T t C'I[1.30 J o:'IE90.1.28105.1.281.25...Per Section 5.5, bundle GEQ830 uses these limits wll 0%setdown 11D 100 90 80 70 60 50 40 30 20 10 1.20 f-,

...........

oCoreFlow (%Rated)Figure 2-5Cycle21 Flow-Dependent MCPR Limits COLRPage15 LBDCR 16034 CORE OPERATING LIMITS REPORT 100 100.1.00 I!80 70 I 60 50 Per Section 5.5, bundle GEQ830 uses these limits w/1 0%setdown 40 35.4,0.880 35.4,1.00 I 30 21.8,0.784 21.8,0.696 I I1020::.50%CoreFlow 1.05 T 1.00*f f 0.95 i t:§;0.90 f0.85 f C)t::I: I-..J 0.80 l r 0.75 1 f 0.70 1 0.65 o Power (%Rated)Figure 3-1a Cycle 21 Power-Dependent LHGR Factor BOC-MOeNote:These factorstobe appliedtothe exposure-dependent limits as descibed in Section 5.3 1.05 1 1.00 l: t: 0.95 t}.35.4.1.00 100.1.00 Per Section 5.5, bundle GEQ830 uses these limits w/1 0%setdown 35.4.0.709

">50%CoreFlow 110 100 90 80 70 60 50 40 35.4,0.8663020 21.8,0.696 21.8.0.77850%Core Flow Power (%Rated)Figure 3-1b Cycle 21 Power-Dependent LHGR, Factor MOC-EOCNote:These factorstobe appliedtothe exposure-dependent limits as descibed in Section 5.3 COLRPage16 LBDCR 16034 CORE OPERATING LIMITS REPORT 110 105.1.00 100 90 80 70 71.4.1.00 60 50 Per Section 5.5, bundle GEQ830 uses theselimitsw/10%

setdown 40 I2030 20.0.652 30.0.652 10 1.05 I 1.00{O.95*f f0.90 t C'1:-r'0.85 1 3 0.80 1 0.75 t 0.70 T r 0.65'f 0.60 orr...

oCoreFlow(%Rated)

Figure 3-2 Cycle 21 Flow-Dependent LHGR FactorNote:These factorstobe applied to the exposure-dependent limits as descibed in Section 5.3 COLRPage17 LBDCR 16034 CORE OPERATING LIMITS REPORT 110 100 90 80 70COREFLOW (%rated)5060 40 30 20 10 o 110 l iii I.i*.10 20 30 40 50 607080COREFLOW (MLB/HR)90 100 110 120 130 Figure 4 Backup Stability Protection Region Boundaries for Normal Feedwater Temperature (NFWT)COLRPage18 LBDCR 16034 CORE OPERATING LIMITS REPORT 130 110 120 100 110 90 100 80 90 70607080COREFLOW (MLB/HR)CORE FLOW (%rated)5060 50 40 40 30 30 20 20 10 10 o:::-t****..._.+..':='F'-._+--*_*F**-

--+..---t--

._..+__._....._--J.-._.-1....._._Implemented BSPBOUndary.l-

!;105%100:

-1

..-:-70r 1!I:;::!l-t*---*MELLLABoundary

-.+----+-A1."**-*+**_--t--**t--**

-+-..+"'-'-1"--;;60 i!!j 1 1_---1---_-....1.._.._._--t-------.--t----.---

!--*..-....-..:-..OPRMArmed Region: I50._.__i Scram

---*.j--.--+--*_-t-----1---t-----t**-*Q.40!: i: i---.-...-t-.-----1-**-**..--+_.---...:

--***-***t------

o i I::U30-L.-..-+-.-*-t-*-

--r-****-+-

+..-_..***1-*20__+..-.-t.---+--1----1----+---..--+.-10 I Iii: j!1 1!----*---i--**-----

-..-----1-------

..--------t-*

**-t-------*

  • -*---t------
  • -----T-------
      • -*---1------

..-.-1--.----

--.----y----.-.--

--.-.-j---------

o I*1 I*.*.*.o Figure 5 Backup Stability Protection Region Boundaries for Reduced Feedwater Temperature (RFWT)COLRPage19 LBDCR 16034

  • '"':P Entergy GNRO-2016/00017March24,2016 U.S.Nuclear Regulatory Commission Attn: DocumentControlDeskWashington,DC20555-0001 Entergy Operations, Inc.P.O.Box756PortGibson,MS39150 James NadeauManager,RegulatoryAssuranceGrandGulfNuclearStationTel.(601)437-2103

SUBJECT:

DearSirorMadam:

Core OperatingLimitsReportCycle21GrandGulf NuclearStation,Unit1DocketNo.50-416LicenseNo.NPF-29 Entergy OperationsInc.(Entergy),is submittingarevisedCore OperatingLimitsReport(COLR)forGrandGulf NuclearStation(GGNS)asrequiredbyGGNS Technical Specification (TS)5.6.5.d.TherevisedCOLRisforCycle21operation.Theanalyticalmethodsusedto determinetheCycle21CoreOperatingLimitswere previouslyapprovedbythe Nuclear Regulatory Commission(NRC)andarelistedinGGNSTS5.6.5.Thislettercontainsnonew commitments.Shouldyouhaveany questionsorrequireadditionalinformation,pleasecontactJamesNadeauat 601-437-2103.

Sincerely, JJN/tmc

Attachment:

CoreOperatingLimitsReport(COLR)Cycle21cc:(seenextpage)

GNRO-2016/00017Page2of2 cc: U.S.Nuclear Regulatory CommissionATTN:Mr.JimKim, NRR/DORL (w/2)MailStopOWFN881Rockville,MD 20852-2738 U.S.Nuclear Regulatory CommissionATTN:Mr.MarcDapas(w/2)

Regional Administrator,RegionIV1600EastLamarBoulevardArlington,TX76011-4511 NRC Senior Resident InspectorGrandGulf Nuclear StationPortGibson,MS39150 Attachment to GNRO-2016/00017 Core OperatingLimitsReport(COLR)Cycle21 Grand Gulf Nuclear Station Core Operating Limits Report COLRPage1 LBDCR 16034 CORE OPERATING LIMITS REPORT REASON FOR REVISION This reV1Slon provides the Cycle 21 core operating limits.These limits are basedona core power of 4408 MWt.TABLE OF CONTENTS 1.0 PURPOSE 3 2.0 SCOPE 3

3.0 REFERENCES

4-6 3.1 Background References 4 3.2 Current Cycle References 4 3.3 Methodology References 5-6 4.0 DEFINITIONS 7 5.0 GENERAL REQUIREMENTS 8-9 5.1 Averaqe Planar Linear Heat Generation Rates 8 5.2 Minimum Critical Power Ratio 8 5.3 Linear Heat Generation Rate 9 5.4 Stability 9 5.5 Applicability 9 5.6 Limitations and Conditions 10 Table 1 OPRM Upscale CDA Amplitude Discriminator 11 Setpoint Table 2 BSP Endpoints for Normal Feedwater Temperature 11 Table 3 BSP Endpoints for Reduced Feedwater 11 Temperature Table 4 ABSP Setpoints for theScramRegion 11 Table 5 Margin toThermalOverpowerand Mechanical 11 Overpower Limits Figure(s)1 APLHGR Operating Limits 12 Figure(s)2 MCPR Operating Limits 13-15 Figure(s)3 LHGR Operating Limits 16-17 Figure 4 Backup Stability Protection Region Boundaries 18 for Normal Feedwater Temperature Figure 5 Backup Stability Protection Region Boundaries 19 for Reduced Feedwater Temperature COLRPage2 LBDCR 16034 CORE OPERATING LIMITS REPORT 1.0 PURPOSE On October 4, 1988, the NRC issued Generic Letter 88-16[3.1.1]encouraging licensees to remove cycle-specific parameter limits from Technical Specifications and to place these limits in a formal report to be prepared by the licensee.Aslongas the parameter limits were developed with methodologies, the letter indicated that thiswouldremove unnecessary burdens on licensee and NRC resources.

On October29,1992, Entergy Operations submitted a Proposed Amendment to the Grand Gulf Operating License requesting changes to the GGNS Technical Specifications to remove certain reactor physics parameter limits thatchangeeach fuel cycle[3.1.2].This amendment committed to placing these operating limits in a separate Core Operating Limits Report (COLR)which is defined in Technical Specifications.

This PCOL was approved by the NRC by SER dated January21,1993[3.1.3].The COLR is controlledasa License Basis Document and revised accordingly for each fuel cycle or remaining portion of a fuel cycle.Any revisions to the COLRmustbe submitted to the NRC for information as requiredbyTechSpec 5.6.5 and tracked by Licensing Commitment 29132.This COLR reports the Cycle 21 core operating and stability setpoint confirmation and regions.2.0 SCOPE As defi ned in Techni cal Speci fi cati on 1.1, the COLR is the GGNS document that provides the core operating limits for the current fuel cycle.This document is prepared in accordance with Technical Specification 5.6.5 for each reload cycle using NRC-approved analytical methods.The Cycle 21 core operating and stability limits included in this report are:*the Average Planar Linear Heat Generation Rate (APLHGR),*the Minimum Critical Power Ratio (MCPR)(including EOC-RPT inoperable),*the Linear Heat Generation Rate (LHGR)limit, and*the DSS-CD stability setpoint confirmation and regions.COLR Page 3 LBDCR 16034 CORE OPERATING LIMITS REPORT

3.0 REFERENCES

This section contains the background, cycle-specific, and methodology references used in the safety analysis of Grand Gulf Cycle 21.3.1 Background References 3.1.1 MAEC-88/0313, Generic Letter 88-16,"Removal of Cycle-Specific Parameter Limits from Technical Specifications", October4,1988.3.1.2 GNRO-92-00093, Proposed Amendment to Grand Gulf Operating License,92/07, dated October 29, 1992.3.1.3 GNRI-93-0008, Amendment 106 to Grand Gulf Operating License, January 21, 1993.3.1.4 GEXI 2000-00116, K.V.Walters to J.B.Lee,"Technical Specification and COLR References for Grand Gulf Nuclear Station and River Bend Station," November3,2000.3.2 Current Cycle References 3.2.1 ECH-NE-16-00004 Revision 0, Supplemental Reload Licensing Report for Grand Gulf Nuclear StationReload20 Cycle 21, dated March 2016.3.2.2 ECH-NE-I0-00021 Revision 4, GNF2 Fuel Design Cycle-Independent Analyses for Entergy Grand Gulf Nuclear Station, dated November 2013.3.2.3 ECH-NE-16-00006 Revision0,FuelBundle Information Report for Grand Gulf Nuclear StationReload20 Cycle 21, dated October 2015.3.2.4 NEDC-32910P, Revision1,Grand Gulf Nuclear Station SAFER/GESTR-LOCA Accident Analysis With Relaxed ECCS Parameters, dated October 1999.3.2.5 GGNS-NE-I0-00022 Revision0,Grand Gulf Nuclear Station MELLLA+Task T0407.ECCS-LOCA Performance, dated September 2012.3.2.6 GGNS-SA-09-00002 Revision1,Grand Gulf Nuclear Station GNF2 ECCS-LOCA Evaluation, datedDecember2009.

3.2.7 NEDC-33173P-A, Rev.4, Application of GE Methods to Expanded Operating Domains, dated November 2012 3.2.8 NEDC-33006P-A, Rev.3, GE BWR Maximum ExtendedLoadLine Limit Analysis Plus, dated June2009 3.2.9 ECH-NE-16-00010, Revision 0, GGNS Cycle 21 GESTAR Assessment, dated March 2016.3.2.10 ECH-NE-14-00014 Revision 2, GGNS RF19 Bundle Reconstitution ReportBundle GEQ830, dated April 2015.COLRPage4 LBDCR 16034 CORE OPERATING LIMITS REPORT 3.3 Methodology References The Technical Specifications (TS)supported by each methodology reference are provided in brackets ({}).3.3.1 XN-NF-81-58(P)(A)

Revision2and Supplements1and2,"RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company,March1984{TS 3.2.1, TS 3.2.2, TS 3.2.3}.3.3.2 XN-NF-85-67(P)(A)

Revision 1,"Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, September 1986{TS 3.2.3}.3.3.3 EMF-85-74(P)

Revision 0 Supplement 1 (P)(A)and Supplement 2 (P)(A),"RODEX2A (BWR)Fuel Rod Thermal-Mechanical EvaluationModel,Siemens Power Corporation," February 1998{TS 3.2.3}.3.3.4 ANF-89-98(P)(A)

Revision1and Supplement 1,"Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995{TS 3.2.3}.3.3.5 Deleted 3.3.6 XN-NF-80-19(P)(A)

Volume1and Supplements1and2,"Exxon Nuclear Methodology for Boiling Water Reactors-Neutronic Methods forDesignand Analysis, Exxon NuclearCompany,"March1983

{TS 3.2.1, TS 3.2.2, TS 3.2.3}.3.3.7 XN-NF-80-19(P)(A)

Volume 4 Revision1,"Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon NuclearCompany,"June1986

{TS 3.2.1, TS 3.2.2, TS 3.2.3}.3.3.8 EMF-2158(P)(A)

Revision 0,"Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-MICROBURN-B2,SiemensPower Corporation," October 1999{TS 3.2.2, TS 3.2.3}.3.3.9 XN-NF-80-19(P)(A)

Volume 3 Revision2,"Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987{TS 3.2.2}.3.3.10XN-NF-84-105(P)(A), Volume1and Supplements1and2,"XCOBRA-T:

A Computer Code for BWR Transient Thermal Hydraulic Core Analysis," Exxon Nuclear Company, February 1987{TS 3.2.2}.3.3.11 ANF-524(P)(A)

Revision2and Supplements1and2,"ANF Critical Power Methodology for Boiling Water Reactors," Advanced Nuclear Fuels Corporation, November 1990{TS 3.2.2}.3.3.12 ANF-913 (P)(A), Volume 1, Revision1and Volume 1 Supplements2,3and4,"COTRANSA2:AComputerProgram for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation,August1990

{TS 3.2.2}.3.3.13 XN-NF-825(P)(A)

Supplement 2,"BWR/6 Generic Rod Withdrawal Error Analysis, MCPR p for Plant Operation Within the Extended Operating Domain," Exxon Nuclear Company, October 1986{TS 3.2.2}.3.3.14 ANF-1358(P)(A)

Revision3,"TheLoss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005{TS 3.2.2}.COLRPage5 LBDCR 16034 CORE OPERATING LIMITS REPORT 3.3 Methodology References (continued) 3.3.15 3.3.16 3.3.17 3.3.18 3.3.19 3.3.20 3.3.21 3.3.22 3.3.23 3.3.24EMF-1997(P)(A)

Revision 0,"ANFB-I0 Critical Power Correlation," Siemens Power Corporation, July 1998{TS 3.2.2}.EMF-1997(P), Supplement I(P)(A), Revision 0,"ANFB-I0 Critical Power Correlation:HighLocal Peaking Results,SiemensPower Corporation," July 1998{TS 3.2.2}.EMF-2209(P)(A)

Revision 2,"SPCB Critical Power Correlation, Siemens Power Corporation," September 2003{TS 3.2.2}.EMF-2245(P)(A)

Revision 0,"Application ofSiemensPower Corporation's Critical Power Correlations to Co-Resident Fuel," Siemens Power Corporation, August 2000{TS 3.2.2}.EMF-2361 (P)(A)Revision 0,"EXEM BWR-2000 ECCS Evaluation Model," Framatome ANP Richland, Inc., May 2001{TS 3.2.1}.Deleted Deleted NEDC-33383P, Revision 1,"GEXL97 Correlation Applicable to ATRIUM-I0 Fuel," June, 2008{TS 3.2.2}.EMF-2292(P)(A)

Revision 0,"ATRIUM-I0:AppendixK Spray Heat Transfer Coefficients,SiemensPower Corporation," September 2000{TS 3.2.1}.Deleted NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel (GESTAR-II)

{TS 3.2.1, TS 3.2.2, TS 3.2.3}.NEDO-33075-A, Revision 8, Licensing Topical Report, Boiling Water Reactor Detect and Suppress Solution-Confirmation Density, November 2013{TS 3.2.2, 3.3.1.1}NEDO-33612-A, Revision 0, Safety Analysis Report for GGNS Maximum Extended Load Line Limit Analysis Plus, September 2013{TS 3.2.2, 3.3.1.1}3.3.28*GGNS-NE-I0-00076 Revision 0 (GEH 0000-012101122-RO), GGNS EPU Option B Scram Times, dated September 2010.{TS 3.2.2}*Note: These references are applicable when GE fuel is in the reactor.COLRPage6 LBDCR 16034 4.0 CORE OPERATING LIMITS REPORT DEFINITIONS 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 4.10 4.11 4.12 4.13 4.14 4.15 Average Planar Linear Heat Generation Rate (APLHGR)-the APLHGR shall be applicable to a specific planar height and is equal to the sum of the linear heat generation rates for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the specified height.Average Planar Exposure-the Average Planar Exposure shall be applicable to a specific planar height and is equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the specified height.Critical Power Ratio (CPR)-the ratio of that power in the assembly, which is calculated by application of the fuel vendor's appropriate boiling correlation, to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating.

Core Operating Limits Report (COLR)-TheGrand Gulf Nuclear Station specific document that provides core operating limits for the current reload cycle in accordance with Technical Specification 5.6.5.Linear Heat Generation Rate (LHGR)-the LHGR shall be the heat generation per unit length of fuel rod.It is the integral of the heat flux over the heat transfer area associated with the unit length.Minimum Critical Power Ratio (MCPR)-the MCPR shall be the smallest CPR which exists in the core.MCPR Safety Limit-the minimum value of the CPR at which the fuel could be operated with the expected number of rods in boiling transition not exceeding 0.1%of the fuel rods in the core.OscillationPowerRange Monitor (OPRM)-Provides automatic detection and suppression of reactor core thermal-hydraulic instabilities through monitoring neutron flux changes.Backup Stability Protection (BSP)ScramRegion-The area of the core power and flow operatingdomainwhere the reactor is susceptible to reactor instabilities under conditions exceeding the licensing basis of the current reactor system.An immediatemanualscram is required upon entry.Backup Stability Protection (BSP)Controlled EntryRegion-The area of the corepowerand flow operatingdomainwhere the reactor is susceptible to reactor instabilities.

Compliance with at least one alternate stability control is required upon entry.AutomatedBackup Stability Protection (ABSP)ScramRegion-An automated reactor scram region that bounds the BSPScramRegionand is initiated by the APRM flow-biased scram setpoint upon entry.End of Rated (EOR)-The Cycle exposure corresponding to all rods out, 100%power, 100%flow,andnormal feedwater temperature

[3.2.1].Middle of Cycle (MOC)-The Cycle 21 MOC Core Average Exposure (CAE)is EOR-2,752 MWdjST[3.2.1].End of Cycle (EOC)-The Cycle 21 EOC CAE is 31,283 MWdjST[3.2.1].Maximum Extended Load Line Limit Analysis Plus (MELLLA+)-The GGNS MELLLA+operating domain is depicted in Figure 4.COLRPage7 LBDCR 16034 CORE OPERATING LIMITS REPORT 5.0 GENERAL REQUIREMENTS 5.1 Average Planar Linear Heat Generation Rates Consistent with Technical Specification 3.2.1, all APLHGRs shall not exceed the exposure-dependent limits reported in Figure 1-1[3.2.1].5.2 Minimum Critical Power Ratio Consistent with Technical Specification 3.2.2, the greater than the limits reported in Figure(s)2as exposure,andscram speed.[3.2.1, 3.2.2, 3.3.28].the power-dependent MCPR shall be determined based as follows.[3.3.28]MCPR shall be equal to or functions of power, flow, For operation at powersonscram time surveillance data 1)If the average scram time satisfies the following:

rAVh'::;rB'then the power dependent MCPR shall be equal to or greater than the Option B limits reported in Figure(s)2asa function of exposure.2)If the average scram time TAV/:'>r B and T::;0.2, then the power-dependent MCPR shall be equal to or greater than the Tau 0.2 limits reported in Figure(s)2asa function of exposure, 3)If the average scram time rAVE>t Ban d t>0.2, then the power-dependent MCPR shall be equal to or greater than the Option A limits reported in Figure(s)2asa function of exposure.In the above equations:=average scram time to the 20%insertion position as calculated by equation 1 of Reference 3.3.28, r B adjusted analysis mean scram time for 20%insertion as calculated by equation 3 of Reference 3.3.28 and t: A VI-'-r B r=-, r A-r B where r A the technical specification limit on core average scram time to the 20 percent insertion position (0.503 seconds).COLRPage8 LBDCR 16034 CORE OPERATING LIMITS REPORT The limits determined above support operation with Turbine Bypass Valves Out of Service as described in Technical Specification 3.7.7.Additional MCPR operating limits are provided to support operation with EOC-RPT inoperable as described in Technical Specification 3.3.4.1.5.3 Linear Heat Generation Rate Consistent with Technical Specification 3.2.3, the LHGRs for any GNF2 fuel rod at any axial location shall not exceed the nodal exposure-dependent limits reported in Reference 3.2.3 multiplied by the smaller of either the power-dependent ordependent LHGR factors reported in Figures3-1and 3-2, respectively

[3.2.1].The limits determined above support operation with Turbine Bypass Valves Out of Service as described in Technical Specification 3.7.7.5.4 Stability The OPRM Upscale Confirmation Density Algorithm (CDA)Amplitude Discriminator setpoint is reported in Table 1.TheBackup Stability Protection (BSP)regions boundaries are reported in Figures 4and5[3.2.1].BSP measures support operation with the OPRM upscale trip function inoperable as described in Technical Specification 3.3.1.1 Condition J.The endpoints for the BSP region boundaries are provided for normal (NFWT)and reduced (RFWT)feedwater temperature operations in Tables2and3, respectively.

Figures4and5 depict the BSP region boundaries for NFWT and RFWT operations.

Note that Figures 4and5 also depict the MELLLA+and MELLLA domains, consistent with feedwater temperature operating limitations.

The ABSP APRM SimulatedThermalPower(STP) setpoints associated with the ABSP Scram Region are provided in Table4.The ABSP setpoints are applicable to TLO and SLO, and to bothnormaland reduced feedwater temperature operations.

The BSPBoundaryand Manual BSP region boundaries for normal feedwater temperature operations are valid for reductions in normal feedwater temperature as muchas(and including)

-10.0 of.5.5 Applicability The following core operating limits are applicable for operation in the Maximum Extended Operting Domain (MEOD), with Feedwater Heaters Out of Service (FHOOS), TurbineBypassOut of Service (TBVOOS), and EOC-RPT inoperable.

For operation with EOC-RPT inoperable, the alternate MCPR limits described in Section 5.2abovemust be implemented.

For single-loop operation (SLO), the following additional requirementsmustbe satisfied.

1.THE APLHGRs shall not exceed the exposure-dependent limits determined in accordance with Section 5.1 reducedbya 0.83 SLO multiplier.

[3.2.1].2.THE LHGRs shall not exceed the smaller of the nodal exposure-dependent limits determined in accordance with Section 5.3 above or the nodal exposure-dependent limits reported in Reference 3.2.3 reducedbya 0.83 SLO multiplier

[3.2.1].3.The MCPR shall be equal to or greater than the limits determined in accordance with Section 5.2 above increased by 0.00 to account for the difference between the two-loop and single-loop MCPR safety limits for the allowable range of single-loop operation[3.2.1].COLRPage9 LBDCR 16034 CORE OPERATING LIMITS REPORT Note that the above described limits are applicable to all bundles in the core;however,a re-inserted bundle (GEQ830-reconstituted in RF19)requires a multiplier to account for uncertainties in its predicted neutronic response during operation.

After re-constitution, the vendor documented analyses to determine its performance in C21[3.2.10];which concluded that a 10%setdown was required for the TLs of GEQ830 (MFLCPR, MFLPD, MAPRAT).This additional factorhasbeen incorporated into the C21 core monitoring system.5.6 Limitations and Conditions As required by Limitation and Condition 9.10/9.11 of licensing topical report33173P-A[3.2.7], the limitingThermaland Mechanical Overpower results are reported in Table5.The results aresummarizedasa percent margin to both of these limits.The results are confirmed to meet the required 10%margin to the design limits[3.2.1].As required by Limitation and Condition 12.10.b of licensing topical report33006P-A[3.2.8], the off-rated limits assumed in the ECCS-LOCA analyses are confirmed to be consistent with the cycle-specific off-rated LHGR multipliers provided Figures3-1and 3-2.These off-rated LHGR multipliers provide adequate protection for MELLLA+operation.

As required by Limitation and Condition 12.5.c of licensing topical report33006P-A[3.2.8], the plant specific power/flow map specifying the GGNS licensed MELLLA+operating domain is included as Figure 4.As required by Limitation and Condition 12.5.b of licensing topical report33006P-A[3.2.8], operation with Feedwater Heaters Out of Service (FWHOOS)is prohibited while in the MELLLA+operating domain[3.2.1].In addition, as required by Limitation and Condition 12.5.a of licensing topical report NEDC-33006P-A

[3.2.8], and described in GGNS TS 3.4.1 LCO, SLO is prohibited in the MELLLA+operating domain[3.2.1].Therefore, operations with RFWT and/or SLO must adhere to the operating domain shown in Figure 5.Table 1 OPRM Upscale CDA Amplitude Discriminator Setpoint Amplitude Discriminator Trip 1.10 Table 2 BSP Endpoints for Normal Feedwater Temperature Endpoint Power(%)Flow(%)Definition Al 72.3 44.2ScramReaion Boundary, HFCL B1 37.5 25.5ScramReaion Boundary, NCL A2 67.3 50.0 Controlled Entrv Reaion Boundary.HFCL B2 26.4 24.4 Controlled Entry Reaion Boundary, NCL A3 100.0 85.5 BSP Boundary Intercept, HFCL B3 81.0 67.2 BSP Boundary Interceot, MELLLA Line COLRPage10 LBDCR 16034 CORE OPERATING LIMITS REPORT Table 3 BSP Endpoints for Reduced Feedwater Temperature Endpoint Power(%)Flow(%)Definition Al 63.0 44.8ScramRegion Boundary, HFCL Bl 30.0 24.8ScramReqion Boundary, NCL A2 67.3 50.0 Controlled Entry Region Boundary, HFCL B226.424.4 Controlled Entry Reqion Boundary, NCL Table 4 ABSP Setpoints for the Scram Region Parameter Symbol Value Slope of ABSP APRM flow-biased trip linear segment m,nTn 0.64 ABSP APRM flow-biased trip setpoint power intercept.

p 31.0%RTp 1 ConstantPowerLine for Trip from zero Drive Flow to BSP-TRIP Flow Breakpoint.

ABSP APRM flow-biased trip setpoint drive flow WBSP-TRIP 39.0%RDP intercept.

ConstantFlowLine for Trip.Flow Breakpoint value WBSP-BREAK 2.0%RDP 1.RTP-RatedThermalPower 2.RDF-Reclrculatlon Drlve Flow COLRPage11 Table 5 Margin to ThermalOverpowerandMechanicalOverpower Limits Criteria GNF2 ThermalOverpowerMargin55.2%

MechanicalOverpowerMargin56.2%

LBDCR 16034 CORE OPERATING LIMITS REPORT 14 0.00,13.78 1312-11=-3:10--:.0::9-C>:I:...J8-a.<<:::i!:7-6-5--4-, 0 10 17.52,13.78 20 30 40 50 60 70 COLRPage12 Average Planar Exposure (GWd/ST)Figure 1-1 Maximum Average Planar Linear Heat Generation Rate Note: Actual Limits described in Sections5.1and5.5 LBDCR 16034 CORE OPERATING LIMITS REPORT 100.1.47 100 90 OptionB 80 70 Option A 60 I 50!40 35.4,1.92 35.4.2.10 I 30 35.4,1.67 20 21.8.2.26 21.8.2.13 I 10 Per Section 5.5, bundle GEQ830 uses these limitsw/10%setdown 2.3 T 2.2-r r 2.1 T 2.0 T 1.91.8 t c:: r1.7 T1.6+:Ie f 1.5 r r 1.4 1;: l 1.1 T 1.0+r-........

oCorePower (%Rated)FigureCycle21 Power-Dependent MCPR LimitseocreMoe 100.1.50Tau=0.2 I90100 Option B 80 I 70 , 60 50 40 Option A 40,1.67 SO,1.67 58.1.65 1 70.1.62 I 3035.4,1.67 35.4,1.66 I 20 21.8,2.13 21.8,2.2650%Core Flow I 10 Per Section 5.5, bundle GEQ830 uses these limits wit 0%setdown 2.3 T f 2.2 T 2.1**t**t 2.0+r 1.9+-t 1.8.....l i.0: it 1.7+a..t1.6 T 1.5 T 1.4+1.3+l'1.2-t--1.1 T r'1.0+1 o Core Power (%Rated)Figure 2-2 Cycle 21 Power-Dependent MCPR Limits BOC to MOe With EOC-RPT Inoperable COLRPage13 LBDCR 16034 CORE OPERATING LIMITS REPORT Per Section 5.5, bundle GEQ830 uses these limitsw/10%setdown 2.3..2.2 2.1 2.0*1.9 1.8 0.:1.7.ct a.u 1.6:E 1.5 1.4 1.31.2.1.1 21.8,2.26 21.8.2.15/>50%Core Flow 35.4.2.12 35.4.1.9740.1.74 40.1.66'50.1.62 58.1.58 Tau: 0.2 OptionS 100.1.52 100.1.44 100,1.42 1.0-***-..*---*..-t----"*-*--*t---

.....--r*-..*-**-..-l---"--t-

..*-*......-**t..--*...

__*+*..-......*........+**_..-........*****_*1 a102030405060708090100 Core Power (%Rated)Figure 2-3 Cycle 21 Power-Dependent MCPR Limits MOCto EOC....*-1 100 90 80 Option A I 70 70,1.69 50.1.74 58.1.72 50.1.63 I 40 40,1.74 35.4.1.97 40,1'.6650,1.6258.

1.58Tau=0.2/>50%Core Flow 35.4.2.12 I 30 21.8,2.15 21.8.2.26 Per Section 5.5, bundle GEQ830 uses these limits wit 0%setdown 1.4*f*1.3 t 1.2 t ,...---------------------------, 1.1+'------'t 1.0

-+--'---t----'--

..+I--.........--t o10205060 2.3 T 2.2+21 1 2.0 T 1.9'r l5 1.6 1-1.5 f Core Power (%Rated)Figure 24 Cycle 21 Power-Dependent MCPR Limits MOCtoEOC with EOC-RPT Inoperable COLRPage14 LBDCR 16034 CORE OPERATING LIMITS REPORT 1.4020.1.3930.1.39 1.35 T t C'I[1.30 J o:'IE90.1.28105.1.281.25...Per Section 5.5, bundle GEQ830 uses these limits wll 0%setdown 11D 100 90 80 70 60 50 40 30 20 10 1.20 f-,

...........

oCoreFlow (%Rated)Figure 2-5Cycle21 Flow-Dependent MCPR Limits COLRPage15 LBDCR 16034 CORE OPERATING LIMITS REPORT 100 100.1.00 I!80 70 I 60 50 Per Section 5.5, bundle GEQ830 uses these limits w/1 0%setdown 40 35.4,0.880 35.4,1.00 I 30 21.8,0.784 21.8,0.696 I I1020::.50%CoreFlow 1.05 T 1.00*f f 0.95 i t:§;0.90 f0.85 f C)t::I: I-..J 0.80 l r 0.75 1 f 0.70 1 0.65 o Power (%Rated)Figure 3-1a Cycle 21 Power-Dependent LHGR Factor BOC-MOeNote:These factorstobe appliedtothe exposure-dependent limits as descibed in Section 5.3 1.05 1 1.00 l: t: 0.95 t}.35.4.1.00 100.1.00 Per Section 5.5, bundle GEQ830 uses these limits w/1 0%setdown 35.4.0.709

">50%CoreFlow 110 100 90 80 70 60 50 40 35.4,0.8663020 21.8,0.696 21.8.0.77850%Core Flow Power (%Rated)Figure 3-1b Cycle 21 Power-Dependent LHGR, Factor MOC-EOCNote:These factorstobe appliedtothe exposure-dependent limits as descibed in Section 5.3 COLRPage16 LBDCR 16034 CORE OPERATING LIMITS REPORT 110 105.1.00 100 90 80 70 71.4.1.00 60 50 Per Section 5.5, bundle GEQ830 uses theselimitsw/10%

setdown 40 I2030 20.0.652 30.0.652 10 1.05 I 1.00{O.95*f f0.90 t C'1:-r'0.85 1 3 0.80 1 0.75 t 0.70 T r 0.65'f 0.60 orr...

oCoreFlow(%Rated)

Figure 3-2 Cycle 21 Flow-Dependent LHGR FactorNote:These factorstobe applied to the exposure-dependent limits as descibed in Section 5.3 COLRPage17 LBDCR 16034 CORE OPERATING LIMITS REPORT 110 100 90 80 70COREFLOW (%rated)5060 40 30 20 10 o 110 l iii I.i*.10 20 30 40 50 607080COREFLOW (MLB/HR)90 100 110 120 130 Figure 4 Backup Stability Protection Region Boundaries for Normal Feedwater Temperature (NFWT)COLRPage18 LBDCR 16034 CORE OPERATING LIMITS REPORT 130 110 120 100 110 90 100 80 90 70607080COREFLOW (MLB/HR)CORE FLOW (%rated)5060 50 40 40 30 30 20 20 10 10 o:::-t****..._.+..':='F'-._+--*_*F**-

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o I*1 I*.*.*.o Figure 5 Backup Stability Protection Region Boundaries for Reduced Feedwater Temperature (RFWT)COLRPage19 LBDCR 16034

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