ML15328A052

Sequoyah, Unit 1 Cycle 21 and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 1

ML15328A052
Person / Time
Site:	Sequoyah
Issue date:	11/16/2015
From:	Carlin J T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML15328A052 (38)

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Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000November 16, 201510 CFR 50.4ATTN: Document Controi DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001Sequoyah Nuclear Plant, Units 1 and 2Renewed Facility Operating License Nos. DPR-77 and DPR-79NRC Docket Nos. 50-327 and 50-328

References:

Sequoyah Unit I Cycle 21, and Unit 2 Cycle 20 Core OperatingLimits Reports, Revision No. 11. Letter from NRC to TVA, "Sequoyah Nuclear Plant, Units 1 and 2-Issuance of Amendments for the Conversion to the ImprovedTechnical Specifications with Beyond Scope Issues (TAC Nos.MF3128 and MF3129)," dated September 30, 20015(ML1 5238B460)In accordance with Sequoyah Nuclear Plant (SQN) Units 1 and 2 TechnicalSpecifications (TSs) 5.6.3.d, enclosed is the Unit 1 Cycle 21 Core Operating LimitsReport (COLR), Revision 1, and Unit 2 Cycle 20OCOLR, Revision 1. In accordancewith TSs 5.6.3.d, the COLRs are required to be provided to the Nuclear RegulatoryCommission (NRC) within 30 days of issuance for each reload cycle. SequoyahUnits 1 and 2 were issued license amendment Nos. 334 and 327, respectively forimproved standard TSs (Reference 1). These license amendments resulted in therevisions to each of the COLRs as discussed in Enclosure 1. The revised COLRsbecame effective on October 21, 2016.There are no new regulatory commitments in this letter. If you have any questions,please contact Jonathan Johnson, SQN Site Licensing Manager at (423) 843-8129.Soso U.S. Nuclear Regulatory CommissionPage 2November 16, 2015Sequoyah Nuclear PlantEnclosures1.2.3.Units 1 and 2 Core Operating Limits Report ChangesSequoyah Unit I Cycle 21 Core Operating Limits Report, Revision 1Sequoyah Unit 2 Cycle 20 Core Operating Limits Report, Revision 1ZTK: DVGEnclosurescc (Enclosures):NRC Regional Administrator -Region IINRC Senior Resident Inspector -SQN ENCLOSURE1ISEQUOYAH UNITS 1 AND 2CORE OPERATING LIMITS REPORT CHANGESThe following describes the changes made to each Units' Core Operating Limits Report(COLR), as result of the NRC review and approval of License Amendment Request for theconversion of the Sequoyah Technical Specification (TS) to Improved Standard TechnicalSpecification, NUREG-1 431, Revision 4.1. Acronyms for All Rods Out (ARO) and Hot Zero THERMAL POWER (HZP) wereremoved from the COLRs.2. In Section 1.0, a table was added to assist user of the COLRs.3. Section 2.0 was updated to align the new TSs Reporting Requirements Section, 5.6.3,"Core Operating Limits Report".4. In Section 2.1 the Cycle-Specific Parameter Limits were relocated from the TSs to theCOLRs. These parameters involve the Shutdown Margin requirements with referencesto the associated Limiting Condition for Operation (LCO).5. 60 ppm Moderator Temperature Coefficient limits were added in "Section 2.2 consistentwith the NOTE in TSs LCO 3.1.3, "Moderator Temperature Coefficient," SurveillanceRequirement 3.1.3.2.6. Control Bank Insertion Limits requirement were added in Section 2.4 as necessary forTSs LCO 3.1.6, "Control Bank Insertion Limits," Surveillance Requirements.7. Section 2.5 was revised to add information relocated from previous TSs for consistencywith approved TSs LCO 3.2.1, "Heat Flux Hot Channel Factor (Fq(X, Y, Z))".8. Section 2.6 was revised to add information relocated from previous TSs for consistencywith approved TSs LCO 3.2.2, 'Nuclear Enthalpy Rise Hot Channel Factor F&H(X, Y)".9. Power Distribution Limits coefficient definitions, such as BQNOM and BHDES, wereeliminated as these are defined in the TS Bases.10. The boron concentration limit for TSs LCO 3.9.1, 'Boron Concentration," were added tothe COLRs consistent with the approved TVA License Amendment Request.

ENCLOSURE 2SEQUOYAH UNIT 1 CYCLE 21CORE OPERATING LIMITS REPORT REVISION 1 QA RecordQA RcordL36 151009 802SEQUOYAH UNIT 1 CYCLE 21CORE OPERATING LIMITS REPORTREVISION 1October 2015Prepared by:Christine A. Setter, PWR Fuel EngineeringVerified by:John E. Strange, P R Fuel EngineeringReviewed by:unningham, PW Fue ngneig ManagerLradnS. Catalanotto, Reactor Engineering ManagerApproved by:DateDateDate/ '&,/SDateRevisionPages affected AllReason for Revision: *Update for Improved Technical Specifications ('ITS) ImplementationSEQUOYAH-UNIT 1Pae1o16Rvsn1Page 1 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 211.0 CORE OPERATING LIMITS REPORTThis CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit I Cycle 21has been prepared in accordance with the requirements of Technical Specification(TS) 5.6.3.The TSs affected by this Report are listed below:TS COLR COLRSection Technical Specification COLR Parameter Section Page3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.1 3BOL MTC Limit 2.2.1 43.3 Moderator Temperature EOL MTC Limit "2.2.2 4313 Coefficient (MTC) 300 ppm Surveillance Limit 2.2.3 4________________60 ppm Surveillance Limit 2.2.4 43.1.4 Rod Group Alignment Limits SDM 2.1.3 3Shutdown Bank Insertion Limits 2.3 43.1.5 Shutdown Bank Insertion LimitsSD2.4 3CotoS BnDnsrinMiit 2.14 53.1.6rConrolnBanknnsertion imitstSD 2.1. 33.1.8 PHYSICS TESTS Exceptions- SDM 2.1.6 3MODE 2 -___________ __FQ 2.5.1 6K(Z) 2.5.2 6NSLOPEAFD 2.5.3 6321 H eat Flux Hot Channel Factor PSLOPEAFD 2.5.4 6321 (F0(X,Y,Z)) NSLOPEf2(Al) 2.5.5 6PSLOPEf2(AI) 2.5.6 6FQ(X,YZ) Appropriate Factor 2.5.7 6ITS LCO 3.2.1 Required Action A.3 2.5.8 6MAP(X,Y,Z) 2.6.1 6RRH 2.6.2 6Nuclear Enthalpy Rise Hot TRH2.3 63.2.2263 6Channel Factor (FAH(XY)) FAH(X,Y) Appropriate Factor 2.6.4 7ITS 3.2.2 Required Action A.4 2.6.5 7ITS 3.2.2 Required Action B.1 2.6.6 73.2.3 AXIAL FLUX DIFFERENCE AFD Limits 2.7 7(AFD)___3.3.1 Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS 2.8.1 8Instrumentation QPNL, QPPL, QPNS, and QPPS 2.8.2 93.9.1 Boron Concentration Refueling Boron Concentration 2.9 9CORE OPERATING LIMITS Aayia ehd5.6.3 REOT(OR nltclMtos2.0 3SEQUOYAH-UNIT 1Pae2o16Rvsn1Page 2 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.0 .OPERATING LIMITSThe cycle-specific parameter limits for the TS listed in section 1 .0 are presented inthe following subsections. These limits have been developed using the NRCapproved methodologies specified in TS 5.6.3. The versions of the topical reportswhich describe the methodologies used for this cycle are listed in Table 1.The following abbreviations are used in this section:BOL stands for Beginning of Cycle LifeEOL stands for End of Cycle LifeRTP stands for RATED THERMAL POWER2.1 SHUTDOWN MARGIN -SDM (TS 3.1 .1, 3.1.4, 3.1.5, 3.1.6, 3.1.8)2.1.1 For TS 3.1.1, SDM shall be ->1.6 %Ak/kin MODE 2 with keff < 1.0, MODE 3 and MODE 4*2.1.2 For TS 3.1.1, SDM shall be > 1.0 %Ak/kin MODE 5.2.1.3 For TS 3.1.4, SDM shall be > 1.6 %Ak/kin MODE 1 and MODE 2.2.1.4 For TS 3.1.5, SDM shall be >-1.6 %Ak/kin MODE 1 and MODE 2.2.1.5 For TS 3.1.6, SDM shall be --.1.6 %Alk/in MODE 1 and MODE 2 with keff> 1.0.2.1.6 For TS 3.1.8, SDM shall be _> 1.6 %Ak/kin MODE 2.SEQUOYAH-UNIT 1 ae3o 6RvsoPage 3 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.2Moderator Temperature Coefficient -MTC (TS 3.1.3)2.2.1 The BOL MTC limit is: less positive than2.2.2 The EOL MTC limit is:less negative than or equal to2.2.3 The 300 ppm Surveillance limit is:less negative than or equal to2.2.4 The 60 ppm Surveillance limit is:less negative than or equal to-0.05 x10-5 Ak/k/0F.-4.50 x 10.4 Ak/k/°F.-3.74 x 10-4 Ak/k/°F.-4.15 xl10 Ak/k/0F.2.3Shutdown Bank Insertion Limits (TS 3.1.5)2.3.1 Each shutdown bank shall be withdrawn to a position as definedbelow:SEQUOYAH-UNIT 1 ae4o 6Rvsopage 4 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.4Control Bank Insertion Limits (TS 3.1.6)2.4.1 The control banks shall be limited in physical insertion as shown inFigure 1.2.4.2 Each cOntrol bank shall be considered fully withdrawn from the coreat>__225 steps.2.4.3 The control banks shall be operated in sequence by withdrawal ofBank A, Bank B, Bank C, and Bank D. The control banks shall besequenced in reverse order upon insertion.2.4.4 Each control bank not fully withdrawn from the core shall be operatedwith the following overlap as a function of full out position.Full Out Position (steps) Bank Overlap (steps) Bank Difference (steps)225 97 128226 98 128227 99 128228 100 128229 101 128230 102 128231 103 128SEQUOYAH-UNIT 1 ae f16RvsoPage 5 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.5 Heat Flux Hot Channel Factor -FQ(X,Y,Z) (TS 3.2.1)2.5.1 FQRT- 2.622.5.2 K(Z) is provided in Figure 22.5.3 NSLOPEAFD = 1.212.5.4 PSLOPEAFD = 1.552.5.5 NSLOPEf2(AI) = 1.482.5.6 PSLOPEf2(AI) = 2.002.5.7 The appropriate factor for increase in FQM(X,Y,Z) for compliancewith SR 3.2.1.2 and SR 3.2.1.3 is specified as follows:For all cycle burn ups, use 2.0%2.5.8 ITS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta TTrip setpoints (value of K<4) at least 1 % (in AT span) for each 1 % thatFQC(x,Y,Z) exceeds its limit.2.6 Nuclear Enthalpy Rise Hot Channel Factor -FAH(X,Y) (TS 3.2.2)2.6.1 MAP(X,Y,Z) is provided in Table 2.2.6.2 RRH=3.34 when 0.8 <P<1.0RRH=1.67 whenP<0.8P = THERMAL POWER / RATED THERMAL POWERRRH = Thermal power reduction required to compensate for each1% that FAH(X,Y) exceeds its limit.2.6.3 TRH = 0.0334 when 0.8 < P < 1.0TRH = 0.0167 when P < 0.8P = THERMAL POWER / RATED THERMAL POWERTRH = Reduction in Overtemperature Delta T K1 setpoint required tocompensate for each 1% that FAH(X,Y) exceeds its limit.SEQUOYAH-UNIT 1Pae6o16RvsnIPage 6 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.6.4 The appropriate factor for increase in FAHM (X,Y) for compliance with-SR 3.2.2.1 and SR 3.2.2.2 is specified as follows:For all cycle burnups, use 2.0%2.6.5 ITS 3.2.2 Required Action A.4 reduces the Overtemperature Delta Tsetpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the FAH minmargin.*2.6.6 ITS 3.2.2 Required Action B.1 reduces the Overtemperature Delta Tsetpoint (K1 term in Table 3.3.1-1) by >- TRH multiplied by the f1(Al)min margin.2.7 AXIAL FLUX DIFFERENCE -AFD (TS 3.2.3)2.7.1 The AFD limits are specified in Figure 3SEQUOYAH-UNIT 1Pae7o16RvsnIPage 7 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.8 Reactor Trip System Instrumentation (TS *3.3.1)2.8.1 Trip Reset Term [f1(Al)] for Overtemperature Delta-T Trip*The following parameters are required to specify the power level-dependentf1(AI) trip reset term limits for Table 3.3.1-1 (function 6), OvertemperatureDelta-T trip function:2.8.1.1 QTNL = -20%where QTNL = the maximum negative Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.1.2 QTPL = +5%where QTPL = the maximum positive Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.1.3 QTNS = 2.50%where QTNS = the percent reduction in Overtemperature Delta-Ttrip setpoint for each percent that the magnitudeof Al exceeds its negative limit at RATEDTHERMAL POWER (QTNL).2.8.1.4 QTPS = 1.40%where QTPS = the percent reduction in Overtemperature Delta-Ttrip setpoint for each percent that the magnitudeof Al exceeds its positive limit at RATEDTHERMAL POWER (QTPL).SEQUOYAH-UNIT 1 ae8o 6RvsoPage 8 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.8.2 Trip Reset Term [f2(AI)] for Overpower Delta-T TripThe following parameters are required to specify the power level-dependent f2(AI) trip reset term limits for Table 3.3.1-1 (function 7),Overpower Delta-T trip function:*2.8.2.1 QPNL = -25%where QPNL = the maximum negative Al setpoint at RATEDTHERMAL *POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.2.2 QPPL = +25%where QPPL = the maximum positive Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.2.3 QPNS = 1.70%where QPNS = the percent reduction in Overpower Delta-T tripsetpoint for each percent that the magnitude of Alexceeds its negative limit at RATED THERMALPOWER (QPNL).2.8.2.4 QPPS = 1.70%where QPPS = the percent reduction in Overpower Delta-T tripsetpoint for each percent that the magnitude of Al> exceeds its positive limit at RATED.THERMALPOWER (QPPL).2.9 Boron Concentration (TS 3.9.1)2.9.1 The refueling boron concentration shall be z 2080 ppm.SEQUOYAH-UNIT 1 ae9o 6RvsoPage 9 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21Table 1COLR Methodology Topical Reports1. BAW-10180-A, Revision 1, "NEMO-Nodal Expansion Method Optimized," March 1993.(Methodology for TS 3.1 .1-SHUTDOWN MARGIN, 3.1 .3-Moderator TemperatureCoefficient, 3.9.1-Boron Concentration)2. BAW-10169P-A, Revision 0, "RSG Plant Safety Analysis-B&W Safety AnalysisMethodology for Recirculating Steam Generator Plants," October 1989.(Methodology for TS 3.1 .3-Moderator Temperature Coefficient)3. BAW-10163P-A, Revision 0, ."Core Operating Limit Methodology for Westinghouse-Designed PWRs," June 1989.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f1(AI), f2(AI) limits],3.1.5-Shutdown Bank Insertion Limits, 3.1.6-Control Bank Insertion Limits, 3.2.1-HeatF~lux Hot Channel Factor, 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.2.3-AXIALFLUX DIFFERENCE)4. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model,"' March 2001.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)5. BAW-10227P-A, Revision 1, "Evaluation of Advanced Cladding and Structural Material(M5) in PWR Reactor Fuel," June 2003.(Methodology for TS 3.2.1-Hleat Flux Hot Channel Factor)6. BAW-10186P-A, Revision 2, "Extended Burnup Evaluation," June 2003.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)7. EMF-2103P-A, Revision 0, "Realistic Large Break LOCA Methodology for PressurizedWater Reactors,". April 2003.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)8. BAW-1 0241 P-A, Revision 1, "BHTP DNB Correlation Applied with LYNXT," July 2005.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])9. BAW-10199P-A, Revision 0, "The BWU Critical Heat Flux Correlations," August 1996.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])10. BAW-10189P-A, "CHF Testing and Analysis of the Mark-BW Fuel Assembly Design,"January 1996.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])1 1. BAW-10159P-A, "BWCMV Correlation of Critical Heat Fluxin Mixing Vane Grid FuelAssemblies," August .1990.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])12. BAW-10231P-A, Revision 1, "COPERNIC Fuel Rod Design Computer Code," January2004.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f2(AI) limits])-SEQUOYAH-UNIT 1 ae1 f16RvsoPage 10 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21Table 2Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation(TS 3.2.2)AXlAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 1.81282 1.81253 1.8122.4 1.81195 1.81151.1 6 1.81097 1.81068 1.81049 1.809810 1.809211 1.75991 2.06712 2.06643 2.06564 2.06495 2.06421.2 6 2.06367 2.06248 2.06159 2.045710 1.949211 -1.85891 2.34332 2.34193 2.34124 2.33975 2.33891.3 6 2.33817 2.33578 2.31309 2.188610 2.0643______11 1.9439AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.59692 2.53803 2.48274 2.44115 2.43151.4 6 2.48007 2.53568 2.44479 2.355510 2.173811 2.02381 2.67232 2.60613 2.54174 2.49135 2.48011.5 6 2.53807 2.62738 2.53119 2.444710 2.277211 2.09751 2.73082 2.66053 2.59474 2.53715 2.52341.6 6 2.59067 2.70778 2.61179 2.524010 2.375811 2.1662SEQUOYAH-UNIT 1 ae1 f16RvsoPage 11 of 16Revision 1 TableFO 2EU A Uont in CYCEd 2Table 2 (continued)AXIAL(X,Y) ELEVATION(ft) MAP(X,Y,Z)1 2.76642 2.70833 2.63804 2.57915 2.56391.7 6 2.63597 2.77958 2.68709 " 2.579810 2.472611 2.23041 2.79632 2.74663 2.67754 2.61725 2.60101.8 6 2.68027 2.84568 2.75529 2.664810 2.565511 2.29311 2.82352 2.77393 2.71254 2.65235 2.63281.9 6 2.72007 2.90658 2.81939 2.728810 2.6384______11 2.3482AXIAL(X,Y) ELEVATION (if) MAP(X,Y,Z)1 2.43392 2.40603 2.38564 2.34235 2.3114>1.9 6 2.60067 2.50038 2.40049 2.298910 2.148311 .1.96301 2.50572 2.47543 2.44494 2.35915 2.42052.1 6 2.76437 2.64748 2.53609 2.440010 2.327711 2.05491 2.53802 2.52163 2.46194 2.42945 2.42902.3 6 2.82227 2.73348 2.62349 2.518610 2.4215_____11 2.1250SEQUOYAH-UNIT I1ae1 f16RvsoPage 12 of 16Revision 1 TableFO 2EU A UcnItin CYCEd 2Table 2 (continued)AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.64402 2.51603 2.50454 2.44885 2.58032.5 6 2.94817 2.85448 2.72869 2.645010 2.552711 2.17311 2.55542 2.55293 2.51974 2.43755 2.56432.7 6 2.98397 2.88378 2.79399 2.704010 2.599711 2.19951 2.42232 2.56533 2.50754 2.39555 2.72952.9 6 3.09217 3.00708 2.88969 2.805810 2.6974_____11 2.2039AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.24482 2.55353 2.46784 2.32295 2.89133.1 6 3.15157 3.01818 2.96999 2.894110 2.781911 2.18661 2.02282 2.51723 2.40074 2.21955 3.04963.3 6 3.22267 3.14468 3.03509 2.968810 2.853311 2.14731 1.75632 2.45663 2.30624 2.08545 3.20453.5 6 3.29297 3.26278 3.08469 3.0299* 10 2.9117_____11 2.0862SEQUOYAH-UNIT 1 Pg 3o 6RvsoPage 13 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21231220(FuI~y Withdn~wn Regior~ (575~225)p --'Inn I0-Cl)rm0/ ABANK D82040020 __ _ _ _ _40(Fully Inserted)0.20.40.60_8IFraction of RATED THERMAL POWERFIGURE 1Rod Bank Insertion Limits Versus THERMAL POWER, Four Loop Operation(TS 3.1.6)* Fully withdrawn region shall be the condition where shutdown and control banks areat a position within the interval of 225 and <231 steps withdrawn, inclusive.Fully withdrawn shall be the position as defined belowCycle Burnup (MWd/mtU)>0Steps Withdrawn-> 225 to < 231This figure is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in operation.If the LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power levelmust be reduced by 1 .3% in power, and the rod insertion limit lines must be increased by 3 steps withdrawn untilthe LEFM is returned to operation.SEQUOYAH-UNIT 1 ae1 f16RvsoPage 14 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 211.21.00.80.60.40.20.0Eeaio K Iz)( )0.00 10006,25 1000\ IIiIElvaio K!z0246-Core Height (Feet)81012FIGURE 2K(Z) -Normalized FQ(X,Y,Z) as a Function of Core Height(TS 3.2.1)SEQUOYAH-UNIT 1Page 15 of 16 RvsoRevision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21a.000.'II-a'UII-01201101009080706050403020100III I I(710) UnaccieptableI_--hOpe rationI-_ -. I_S I I 1COLR FOR SEQUOYAH UNIT 1 CYCLE 21I q]IILIII' ! i '-50-40 20 -10 0 10 20 30Flux Difference (Al) %FIGURE 3AXIAL FLUX DIFFERENCE Limits As AFunction of RATED THERMAL POWERFor Burnup Range 0 EFPD to EOL(TS 3.2.3)4050This figure is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in operation.If the LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power levelmust be reduced by 1.3% in power, and the AFD limit lines must be made more restrictive by 1% in AFD untilthe LEFM is returned to operation.SEQUOYAH-UNIT 1 Pg 6o 6RvsoPage 16 of 16Revision 1 ENCLOSURE 3SEQUOYAH UNIT 2 CYCLE 20CORE OPERATING LIMITS REPORT REVISION 1 QA RecordQA RcordL36 151009 803SEQUOYAH UNIT 2 CYCLE 20CORE OPERATING LIMITS REPORTREVISION IOctober 2015Prepared by:Christine A. Setter, PWR Fuel Engineering DateVerified by:/P,5R Fuel Engineering DatO! eReviewed by:K PWR Fuel Engineering Manager DateBrandon S. Catalanotto, Reactor Engineering Manager Date/ /Approved by:PORC Chairman DatePlant Manager 'DateRevision .._1Pages affected AllReason for Revision: Update for Improved Technical Specifications (ITS) ImplementationSEQUOYAH-UNJT 2Pae1o17Rvsn1Page 1 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 201.0 CORE OPERATING LIMITS REPORTThis CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 2 Cycle 20has been prepared in accordance with the requirements of Technical Specification(TS) 5.6.3.The TSs affected by this Report are listed below:TS COLR COLRSection Technical Specification COLR Parameter Section Page3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.1 3BOL MTC Limit 2.2.1 4313 Moderator Temperature EOL MTC Limit 2.2.2 4Coefficient (MTC) 300Oppm Surveillance Limit 2.2.3 460 ppm Surveillance Limit 2.2.4 43.1.4 Rod Group Alignment Limits SDM 2.1.3 3Shutdown Bank Insertion Limits 2.3 43.1.5 Shutdown Bank Insertion LimitsSD214 3CotoS anDnetinLmt 2..4 53.1.6rCntrolnBnkIInsetionnLiitsiSs 2.14 33.1.8 PHYSICS TESTS Exceptions -SDM 2.1.6 3MODE 2FTP 2.5.1 6K(Z) 2.5.2 6NSLOPEAFD 2.5.3 6321 Heat Flux Hot ChanneiFactor PSLOPEAFD 2.5.4 6(F0(X,Y,Z)) NSLOPEf2(AI) 2.5.5 6PSLOPEf2(AI) 2.5.6 6FQ(X,Y,Z) Appropriate Factor 2.5.7 6___________________ITS LCO 3.2.1 Required Action A.3 2.5.8 6MAP(X,Y,Z) 2.6.1 6RRH 2.6.2 6322 Nuclear Enthalpy Rise Hot TRH 2.6.3 6Channel Factor (FAH(X,Y)) FAH(X,Y) Appropriate Factor 2.6.4 7ITS 3.2.2 Required Action A.4 2.6.5 7ITS 3.2.2 Required Action B.1 2.6.6 7323 AXIAL FLUX DIFFERENCE AOLmt .(AFD) _ _ _ _ _ _ _ _ _ _ _331 Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS 2.8.1 8Instrumentation QPNL, QPPL, QPNS, and QPPS 2.8.2 93.9.1 Boron Concentration Refueling Boron Concentration 2.9 9CORE OPERATING LlMITS Aayia ehd5.6.3 REOT(OR nltclMtos2.0 3SEQUOYAH-UNIT 2Pae2o17Risn1Page 2 of 17Revision 1 COLR FoR SEQUOYAH UNIT 2 CYCLE 202.0 OPERATING LIMITSThe cycle-specific parameter limits for the TS listed in section 1 .0 are presented inthe following subsections. These limits have been developed using the NRCapproved methodologies specified in TS 5.6.3. The versions of the topical reportswhich describe the methodologies used for this cycle are listed in Table 1.The following abbreviations are used in this section:,BOL stands for Beginning of Cycle LifeEOL stands for End of Cycle LifeRTP stands for RATED THERMAL POWER2.1 SHUTDOWN MARGIN -SOM (TS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8)2.1.1 For TS 3.1.1, SOM shall be >_1.6 %Ak/kin MODE 2 with keff < 1.0, MODE 3 and MODE 42.1.2 For TS 3.1.1, SDM shall be >_1.0 %Ak/kin MODE 5.2.1.3 For TS 3.1.4, SDM shall be >1.6 %Ak/kin MODE 1 and MODE 2.2.1.4 For TS 3.1.5, SDM shall be >_1.6 %Ak/kin MODE 1 and MODE 2.2.1.5 For TS 3.1.6, SDM shall be >__1.6 %Ak/kin MODE 1 and MODE 2 with keff> 1.0.2.1.6 For TS 3.1.8, SDM shall, be >_.1.6 %Ak/kin MODE 2.SEQUOYAH-UNIT 2Pae3o17RvsnIPage 3 of 17.Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.2Moderator Temperature Coefficient -MTC (TS 3.1.3)2.2.1 The BOL MTC limit is:less positive than2.2.2 The EOL MTC limit is:less negative than or equal to2.2.3 The 300 ppm Surveillance limit is:less negative than or equal to2.2.4 The 60 ppm Surveillance limit is:less negative than or equal to-0.16 x10-5 Ak/k/°F.-4.50 x 1 0A Ak/k/°F.-3.75 x 1 04 Ak/k/°F.-4.20 x10A Ak/k/°F.2.3Shutdown Bank Insertion Limits (TS 3.1.5)2.3.1 Each shutdown bank shall be withdrawn to a position as definedbelow:SEQUOYAH-UNIT 2Pae4o17RvsnI* Page 4 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.4Control Bank Insertion Limits (TS 3.1.6)2.4.1 The control banks Shall be limited in physical insertion as shown inFigure 1.2.4.2 Each control bank shall be considered fully withdrawn from the coreat>__225 steps.2.4.3 The control banks shall be operated in sequence by withdrawal ofBank A, Bank B, Bank C, and Bank 0. The control banks shall besequenced in reverse order upon insertion.2.4.4 Each control bank not fully withdrawn from the core shall be operatedwith the following overlap as a function of full out position.Full Out Position Bank Overlap Bank Difference(ts) (steps) (steps)225 9712226 9812227 99 128__________228 100 128229 101 128230 102 128231 103 "128SEQUOYAH-UNIT 2Pae5o17RvsnIPage 5 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.5 Heat Flux Hot Channel Factor- FQ(X,Y,Z) (TS 3.2.1)RTP2.5.1 FQ = 2.622.5.2 K(Z) is provided in Figure 22.5.3 NsLoPEAFD = 1.442.5.4 PSLOPEAFD = 1.76-2.5.5 NSLOPEf2(/I) = 1.482.5.6 PSLOPEf2(AI) = 2.98M2.5.7 The appropriate factor for increase in FQ (X,Y,Z) for compliancewith SR 3.2.1.2 and SR 3.2.1.3 is specified as follows:For cycle burnups: 0 to 3312 MWd/mtU, use 2.0%For cycle burnups: > 3312 to 3864 MWd/mtU, use 2.12%For cycle* burnups: > 386,4 MWd/mtU, use 2.0%2.5.8 ITS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta TTrip setpoints (value of K4) at least 1% (in AT span) for each 1% thatFQC(X,Y,Z) exceeds its limit.2.6 Nuclear Enthalpy Rise Hot Channel Factor -FAH(X,Y) (TS 3.2.2)2.6.1 MAP(X,Y,Z) is provided in Tables 2a and 2b.2.6.2 RRH = 3.34 when 0.8 < P_ 1.0RRHIl.67 whenP<0.8P = THERMAL POWER / RATED THERMAL POWERRRH = Thermal power reduction required to compensate for each*1% that FAH(X,Y) exceeds its limit.2.6.3 TRH = 0.0334 when 0.8 < P < 1.0TRH = 0.01 67 when P < 0.8P = THERMAL POWER I RATED THERMAL POWERTRH = Reduction in Overtemperature Delta T K1 setpoint required tocompensate for each 1 % that FAH(X,Y) exceeds its limit.SEQUOYAH-UNIT 2 Pg f1Page 6 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.6.4 The appropriate factor for increase in FAHM (X,Y) for compliance withSR 3.2.2.1 and SR 3.2.2.2 is specified as follows:For all cycle burnups, use 2.0%:2.6.5 ITS 3.2.2 Required Action A.4 reduces the overtemperature Delta Tsetpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the FAN minmargin.2.6.6 ITS 3.2.2 Required Action 8.1 reduces the Overtemperature Delta Tsetpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the f1 (Al)min margin.2.7 AXIAL FLUX DIFFERENCE -AFD (TS 3.2.3)2.7.1 The AFD limits are specified in Figure 3SEQUOYAH-UNIT 2Pae7o17RvsnIPage 7 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.8 Reactor Trip System Instrumentation (TS 3.3.1)2.8.1 Trip Reset Term [f1(AI)] for Overtemperature Delta-T TripThe following parameters are required to specify the power level-dependentf1(AI) trip reset term limits for Table 3.3.1-1 (function 6), OvertemperatureDelta-T trip function:2.8.1 .1 QTNL = -20%where QTNL = the maximum negative Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.1.2 QTPL = +5%where QTPL = the maximum positive AlI setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.1.3 QTNS = 2.50%where QTNS = the percent reduction in Overtemperature Delta-Ttrip setpoint for each percent that the magnitudeof Al exceeds its negative limit at RATEDTHERMAL POWER (QTNL).2.8.1.4 QTPS = 1.40%where QTPS = the percent reduction in Overtemperature Delta-Ttrip setpoint for each percent that the magnitudeof Al exceeds its positive limit at RATEDTHERMAL POWER (QTPL).SEQUOYAH-UNIT 2Pae8o17Rvsn1Page 8 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.8.2 Trip Reset Term [fz(AI)] for Overpower Delta-T TripThe following parameters are required to specify the power level-dependent f2(AI)trip reset term limits for Table 3.3.1-1 (function 7), Overpower Delta-T trip function:.2.8.2.1 QPNL =-25%Where QPNL = the maximum negative Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.2.2 QPPL = +25%where QPPL = the maximum positive Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.2.3 QPNS = 1.70%where QPNS = the percent reduction in Overpower Delta-Ttrip setpoint for each percent that themagnitude of Al exceeds its negative limit atRATED THERMAL POWER (QPNL).2.8.2.4 QPPS = 1.70%where QPPS = the percent reduction in Overpower Delta-Ttrip setpoint for each percent that themagnitude of Al exceeds its positive limit atRATED THERMAL POWER (QPPL).2.9 Boron Concentration (TS 3.9.1)2.9.1 The refueling boron concentration shall be > 2000 ppm.SEQUOYAH-UNIT 2Pae9o17Rvsn1Page 9 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20Table 1COLR Methodology Topical Reports1. BAW-1 0180-A, Revision 1, "NEMO-Nodal Expansion Method Optimized," March 1993.(Methodology for TS 3.1.1-SHUTDOWN MARGIN, 3.1.3-Moderator TemperatureCoefficient, 3.9.1-Boron Concentration)-2. BAW-10169P-A, Revision 0, "RSG Plant Safety Analysis-B&W Safety AnalysisMethodology for Recirculating Steam Generator Plants," October 1989.(Methodology for TS 3.1 .3-Moderator Temperature Coefficient)3. BAW-1 01 63P-A, Revision 0, "Core Operating Limit Methodology for Westinghouse-Designed PWRs," June 1989.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f1(AI), f2(AI) limits],3.1.5-Shutdown Bank Insertion Limits, 3.1.6-Control Bank Insertion Limits, 3.2.1-HeatFlux Hot Channel Factor, 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.2.3-AXIALFLUX DIFFERENCE)4. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model," March 2001.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)5. BAW-1 0227P-A, Revision 1, "Evaluation of Advanced Cladding and Structural Material(M5) in PWR Reactor Fuel,"' June 2003.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)6. BAW-10186P-A, Revision 2, "Extended Burnup Evaluation," June 2003.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)7. EMF-2103P-A, Revision 0, "Realistic Large Break LOCA Methodology for PressurizedWater Reactors," April 2003.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)8. BAW-1 0241 P-A, Revision 1, "BHTP DNB Correlation Applied with LYNXT," July 2005.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])9. BAW-10199P-A, Revision 0, "The BWU Critical Heat Flux Correlations," August 1996.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])10. BAW-10189P-A, "CHF Testing and Analysis of the Mark-BW Fuel Assembly Design,"January 1996.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(Al) limits])11. BAW-1 01 59P-A, "BWCMV Correlation of Critical Heat Flux in Mixing Vane Grid FuelAssemblies," August 1990.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])12. BAW-10231 P-A, Revision .1, "COPERNIC Fuel Rod Design Computer Code," January2004.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f2(Al) limits])SEQUOYAH-UNIT 2 Pg 0o 7RvsoPage 10 of 17Revision 1 CQLR FOR SEQUOYAH UNIT 2 CYCLE 20Table 2aMaximum Allowable Peaking Limits MAP(X,Y,Z) for OperationAdvanced W17 HTPTMFuel (TS 3.2.2)AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 1.81282 1.81253 1.81224 1.81195 1.81151.1 6 1.81097 1.81068 1.81049 1.809810 1.8092______11 1.75991 2.06712 2.06643 2.06564 2.06495 2.06421.2 6 2.06367 2.06248 2.06159 2.045710 1.9492_____11 1.85891 2.34332 2.34193 2.34124 2.33975 2.33891.3 6 2.3381-7 2.33578 2.31309 2.188610 2.0643______11 1.9439AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.59692 2.53803 2.48274 2.44115 2.43151.4 6 2.48007 2.53568 2.44479 2.355510 2.173811 2.02381 2.67232 2.60613 2.54174 2.49135 2.48011.5 6 2.53807 2.62738 2.53119 2.444710 2.277211 2.09751 2.73082 2.66053. 2.59474 2.53715 2.52341.6 6 2.59067 2.70778 2.61179 2.524010 2.3758_ _ _ _ _11 2.1662SEQUOYAH-UNIT 2Pae1of7eisnIPage 11 of 17Revision 1 CO ablFO 2OaH UcnIti2n YCed 20Table 2a (continued)AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 ,2.76642 2.70833 2.63804 2.57915 2.56391.7 6 2.6359,7 2.77958 2.68709 2.579810 2.472611 2.23041 2.79632 2.74663 2.67754 2.61725 2.60101.8 6 2.68027 2.84568 2.75529 2.664810 2.565511 2.29311 2.82352 2.77393 2.71254 2.65235 2.63281.9 6 2.72007 2.90658 2.81939 2.728810 2.6384_____11 2.3482AXlAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.43392 2.40603 2.38564 2.34235 2.3114>1.9 6 2.60067 2.50038 2.40049 2.298910 2.1483_____11 1.96301 2.50572 2.47543 2.44494 2.35915 2.42052.1 6 2.76437 2.64748 2.53609 2.440010 2.3277_____11 2.05491 2.53802 2.52163 2.46194 2.42945 2.42902.3 6 2.82227 2.73348 2.62349 2.518610 2.4215_____11 2.1250SEQUOYAH-UNIT 2Pae1of7Page 12 of 17Revision 1 TableFO 2OaH UcnIti2nCYLEd 2Table 2a (continued)AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.64402 2.5160' 3 2.50454 2.44885 2.58032.5. 6 2.94817 2.85448 2.72869 2.645010 2.5527_____11 2.17311 2.55542 2.55293 2.51974 2.43755 2.56432.7 6 2.98397 2.88378 2.79399 2.704010 .2.599711 2.19951 2.42232 2.56533 2.50754 2.39555 2.72952.9 6 3.09217 3.00708 2.88969 2.805810 2.6974_____11 2.2039AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.24482 2.55353 2.46784 2.32295 2.89133.1 6 3.15157 3.01818 2.96999 2.894110 2.781911 2.18661 2.02282 2.51723 2.40074 2.21955 3.04963.3 6 3.22267 3.14468 3.03509 2.968810 2.853311 2.14731. 1.75632 2.45663 2.30624 2.08545 3.20453.5 6 3.29297 3.26278 3.08469 .3.029910. 2.9117_____11 2.0862SEQUOYAH-UNIT 2 Pg 3f7RvsoPage 13 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20Table 2bMaximum Allowable Peaking Limits MAP(X,Y,Z) for OperationMark-BW Fuel (TS 3.2.2)AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)2 1.93434 1.93001.1 6 1.92348 1.911510 1.88942 2.16634 2.15581.2 6 2.14108 2.1153'10 2,05822 *2.40234 2.38251.3 6 2.35998 2.3100_______10 2.17602 2.64534 2.61361.4 6 2.56108 2.419910 2.27872 2.71894 2.81811.5 6 2.67358 2.528010 2.37492 2.77204 2.92191.7 6 2.86418 2.706410 2.5539AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)2 2.81434 2.98561.9 6 3.00738 2.850910 2.70482 2.44054 2.4405>1.9 6 2.73768 2.590610 2.34562 2.58814 2.58812.2 6 2.98998 2.780010 2.53672 2.61114 2.61112.6 6 3.29478 3.205510 2.80492 2.91424 2.914236 4.02168 3.652710 3.17112 2.96184 2.96183.5 6 4.23518 3.745210 3.3214SEQUOYAH-UNIT 2 Pg 4o 7RvsoPage 14 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20r- /~- BA K C/* 140& (u120 8w100 _______BANK 0DZ8040 /20,0 {.09,o) ________ ________ _______ _______0 0.2 0.A 0.6 0_8(Fully Inserted)Fraction of RATED THERMAL POWERFIGURE 1Rod Bank Insertion Limits Versus THERMAL POWER, Four Loop Operation(TS 3.1.6)* Fully withdrawn region shall be the condition where shutdown and control banks areat a position within the interval of >225 and <231 steps withdrawn, inclusive.Fully withdrawn shall be the position as defined below,Cycle Burnup (MWd/mtU) Steps Withdrawn0 225 to -231This figure is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in operation.If the LEEM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power levelmust be reduced by 1.3% in power, and the rod insertion limit lines must be increased by 3 steps withdrawnuntil the LEFM is returned to operation.SEQUOYAH-UNIT 2 Pg 5o 7RvsoPage 15 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 201.21.00.80.60.40.20.0I 2 2 II 2 I I-2 I I II I I2 I4-----22 2 2I 2 2 I2 2Elevation K(z)(ft)0.000 1.00006.285 1.0000 -~----------2 7.995 1.0000 2 2 22 9.705 1.0000 2 2 212.000 1.0000 2 2-2 2 I2 2 2 22 2 2 2I. 2 2 22 I I 2 II I I0246Core Height (Feet)1012FIGURE 2K(Z) -Normalized FQ(X,Y,Z) as a Function of Core Height(TS 3.2.1 )SEQUOYAH-UNIT 2 Pg 6o 7RvsoPage 16 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20I-1-S1*6='U1201101009080706050403020100I I II---K- ---LU accept be_/--tperatD- 7 -n---I----/ .--°PecirainI* -- I--/ t- --- I(-4b,5o) I IIII I I-- -V- -- -K-I [-.II i I _-- -- i28,o -I 2-----1--K* l--I-II.v-50 30 10 0 10Flux Difference (hl) %20 30 4050FIGURE 3AXIAL FLUX DIFFERENCE Limits As AFunction of RATED THERMAL. POWER.For Burnup Range 0 EFPD to EOL(TS 3.2.3)This figure is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in oPeration.If the LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable *power levelmust be reduced by 1.3% in power, and the AFD limit lines must be made more restrictive by 1% in AFO untilthe LEFM is returned to operation.SEQUOYAH-UNIT 2 Pg 7o 7RvsoPage 17 of 17Revision 1 Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000November 16, 201510 CFR 50.4ATTN: Document Controi DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001Sequoyah Nuclear Plant, Units 1 and 2Renewed Facility Operating License Nos. DPR-77 and DPR-79NRC Docket Nos. 50-327 and 50-328

References:

Sequoyah Unit I Cycle 21, and Unit 2 Cycle 20 Core OperatingLimits Reports, Revision No. 11. Letter from NRC to TVA, "Sequoyah Nuclear Plant, Units 1 and 2-Issuance of Amendments for the Conversion to the ImprovedTechnical Specifications with Beyond Scope Issues (TAC Nos.MF3128 and MF3129)," dated September 30, 20015(ML1 5238B460)In accordance with Sequoyah Nuclear Plant (SQN) Units 1 and 2 TechnicalSpecifications (TSs) 5.6.3.d, enclosed is the Unit 1 Cycle 21 Core Operating LimitsReport (COLR), Revision 1, and Unit 2 Cycle 20OCOLR, Revision 1. In accordancewith TSs 5.6.3.d, the COLRs are required to be provided to the Nuclear RegulatoryCommission (NRC) within 30 days of issuance for each reload cycle. SequoyahUnits 1 and 2 were issued license amendment Nos. 334 and 327, respectively forimproved standard TSs (Reference 1). These license amendments resulted in therevisions to each of the COLRs as discussed in Enclosure 1. The revised COLRsbecame effective on October 21, 2016.There are no new regulatory commitments in this letter. If you have any questions,please contact Jonathan Johnson, SQN Site Licensing Manager at (423) 843-8129.Soso U.S. Nuclear Regulatory CommissionPage 2November 16, 2015Sequoyah Nuclear PlantEnclosures1.2.3.Units 1 and 2 Core Operating Limits Report ChangesSequoyah Unit I Cycle 21 Core Operating Limits Report, Revision 1Sequoyah Unit 2 Cycle 20 Core Operating Limits Report, Revision 1ZTK: DVGEnclosurescc (Enclosures):NRC Regional Administrator -Region IINRC Senior Resident Inspector -SQN ENCLOSURE1ISEQUOYAH UNITS 1 AND 2CORE OPERATING LIMITS REPORT CHANGESThe following describes the changes made to each Units' Core Operating Limits Report(COLR), as result of the NRC review and approval of License Amendment Request for theconversion of the Sequoyah Technical Specification (TS) to Improved Standard TechnicalSpecification, NUREG-1 431, Revision 4.1. Acronyms for All Rods Out (ARO) and Hot Zero THERMAL POWER (HZP) wereremoved from the COLRs.2. In Section 1.0, a table was added to assist user of the COLRs.3. Section 2.0 was updated to align the new TSs Reporting Requirements Section, 5.6.3,"Core Operating Limits Report".4. In Section 2.1 the Cycle-Specific Parameter Limits were relocated from the TSs to theCOLRs. These parameters involve the Shutdown Margin requirements with referencesto the associated Limiting Condition for Operation (LCO).5. 60 ppm Moderator Temperature Coefficient limits were added in "Section 2.2 consistentwith the NOTE in TSs LCO 3.1.3, "Moderator Temperature Coefficient," SurveillanceRequirement 3.1.3.2.6. Control Bank Insertion Limits requirement were added in Section 2.4 as necessary forTSs LCO 3.1.6, "Control Bank Insertion Limits," Surveillance Requirements.7. Section 2.5 was revised to add information relocated from previous TSs for consistencywith approved TSs LCO 3.2.1, "Heat Flux Hot Channel Factor (Fq(X, Y, Z))".8. Section 2.6 was revised to add information relocated from previous TSs for consistencywith approved TSs LCO 3.2.2, 'Nuclear Enthalpy Rise Hot Channel Factor F&H(X, Y)".9. Power Distribution Limits coefficient definitions, such as BQNOM and BHDES, wereeliminated as these are defined in the TS Bases.10. The boron concentration limit for TSs LCO 3.9.1, 'Boron Concentration," were added tothe COLRs consistent with the approved TVA License Amendment Request.

ENCLOSURE 2SEQUOYAH UNIT 1 CYCLE 21CORE OPERATING LIMITS REPORT REVISION 1 QA RecordQA RcordL36 151009 802SEQUOYAH UNIT 1 CYCLE 21CORE OPERATING LIMITS REPORTREVISION 1October 2015Prepared by:Christine A. Setter, PWR Fuel EngineeringVerified by:John E. Strange, P R Fuel EngineeringReviewed by:unningham, PW Fue ngneig ManagerLradnS. Catalanotto, Reactor Engineering ManagerApproved by:DateDateDate/ '&,/SDateRevisionPages affected AllReason for Revision: *Update for Improved Technical Specifications ('ITS) ImplementationSEQUOYAH-UNIT 1Pae1o16Rvsn1Page 1 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 211.0 CORE OPERATING LIMITS REPORTThis CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit I Cycle 21has been prepared in accordance with the requirements of Technical Specification(TS) 5.6.3.The TSs affected by this Report are listed below:TS COLR COLRSection Technical Specification COLR Parameter Section Page3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.1 3BOL MTC Limit 2.2.1 43.3 Moderator Temperature EOL MTC Limit "2.2.2 4313 Coefficient (MTC) 300 ppm Surveillance Limit 2.2.3 4________________60 ppm Surveillance Limit 2.2.4 43.1.4 Rod Group Alignment Limits SDM 2.1.3 3Shutdown Bank Insertion Limits 2.3 43.1.5 Shutdown Bank Insertion LimitsSD2.4 3CotoS BnDnsrinMiit 2.14 53.1.6rConrolnBanknnsertion imitstSD 2.1. 33.1.8 PHYSICS TESTS Exceptions- SDM 2.1.6 3MODE 2 -___________ __FQ 2.5.1 6K(Z) 2.5.2 6NSLOPEAFD 2.5.3 6321 H eat Flux Hot Channel Factor PSLOPEAFD 2.5.4 6321 (F0(X,Y,Z)) NSLOPEf2(Al) 2.5.5 6PSLOPEf2(AI) 2.5.6 6FQ(X,YZ) Appropriate Factor 2.5.7 6ITS LCO 3.2.1 Required Action A.3 2.5.8 6MAP(X,Y,Z) 2.6.1 6RRH 2.6.2 6Nuclear Enthalpy Rise Hot TRH2.3 63.2.2263 6Channel Factor (FAH(XY)) FAH(X,Y) Appropriate Factor 2.6.4 7ITS 3.2.2 Required Action A.4 2.6.5 7ITS 3.2.2 Required Action B.1 2.6.6 73.2.3 AXIAL FLUX DIFFERENCE AFD Limits 2.7 7(AFD)___3.3.1 Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS 2.8.1 8Instrumentation QPNL, QPPL, QPNS, and QPPS 2.8.2 93.9.1 Boron Concentration Refueling Boron Concentration 2.9 9CORE OPERATING LIMITS Aayia ehd5.6.3 REOT(OR nltclMtos2.0 3SEQUOYAH-UNIT 1Pae2o16Rvsn1Page 2 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.0 .OPERATING LIMITSThe cycle-specific parameter limits for the TS listed in section 1 .0 are presented inthe following subsections. These limits have been developed using the NRCapproved methodologies specified in TS 5.6.3. The versions of the topical reportswhich describe the methodologies used for this cycle are listed in Table 1.The following abbreviations are used in this section:BOL stands for Beginning of Cycle LifeEOL stands for End of Cycle LifeRTP stands for RATED THERMAL POWER2.1 SHUTDOWN MARGIN -SDM (TS 3.1 .1, 3.1.4, 3.1.5, 3.1.6, 3.1.8)2.1.1 For TS 3.1.1, SDM shall be ->1.6 %Ak/kin MODE 2 with keff < 1.0, MODE 3 and MODE 4*2.1.2 For TS 3.1.1, SDM shall be > 1.0 %Ak/kin MODE 5.2.1.3 For TS 3.1.4, SDM shall be > 1.6 %Ak/kin MODE 1 and MODE 2.2.1.4 For TS 3.1.5, SDM shall be >-1.6 %Ak/kin MODE 1 and MODE 2.2.1.5 For TS 3.1.6, SDM shall be --.1.6 %Alk/in MODE 1 and MODE 2 with keff> 1.0.2.1.6 For TS 3.1.8, SDM shall be _> 1.6 %Ak/kin MODE 2.SEQUOYAH-UNIT 1 ae3o 6RvsoPage 3 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.2Moderator Temperature Coefficient -MTC (TS 3.1.3)2.2.1 The BOL MTC limit is: less positive than2.2.2 The EOL MTC limit is:less negative than or equal to2.2.3 The 300 ppm Surveillance limit is:less negative than or equal to2.2.4 The 60 ppm Surveillance limit is:less negative than or equal to-0.05 x10-5 Ak/k/0F.-4.50 x 10.4 Ak/k/°F.-3.74 x 10-4 Ak/k/°F.-4.15 xl10 Ak/k/0F.2.3Shutdown Bank Insertion Limits (TS 3.1.5)2.3.1 Each shutdown bank shall be withdrawn to a position as definedbelow:SEQUOYAH-UNIT 1 ae4o 6Rvsopage 4 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.4Control Bank Insertion Limits (TS 3.1.6)2.4.1 The control banks shall be limited in physical insertion as shown inFigure 1.2.4.2 Each cOntrol bank shall be considered fully withdrawn from the coreat>__225 steps.2.4.3 The control banks shall be operated in sequence by withdrawal ofBank A, Bank B, Bank C, and Bank D. The control banks shall besequenced in reverse order upon insertion.2.4.4 Each control bank not fully withdrawn from the core shall be operatedwith the following overlap as a function of full out position.Full Out Position (steps) Bank Overlap (steps) Bank Difference (steps)225 97 128226 98 128227 99 128228 100 128229 101 128230 102 128231 103 128SEQUOYAH-UNIT 1 ae f16RvsoPage 5 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.5 Heat Flux Hot Channel Factor -FQ(X,Y,Z) (TS 3.2.1)2.5.1 FQRT- 2.622.5.2 K(Z) is provided in Figure 22.5.3 NSLOPEAFD = 1.212.5.4 PSLOPEAFD = 1.552.5.5 NSLOPEf2(AI) = 1.482.5.6 PSLOPEf2(AI) = 2.002.5.7 The appropriate factor for increase in FQM(X,Y,Z) for compliancewith SR 3.2.1.2 and SR 3.2.1.3 is specified as follows:For all cycle burn ups, use 2.0%2.5.8 ITS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta TTrip setpoints (value of K<4) at least 1 % (in AT span) for each 1 % thatFQC(x,Y,Z) exceeds its limit.2.6 Nuclear Enthalpy Rise Hot Channel Factor -FAH(X,Y) (TS 3.2.2)2.6.1 MAP(X,Y,Z) is provided in Table 2.2.6.2 RRH=3.34 when 0.8 <P<1.0RRH=1.67 whenP<0.8P = THERMAL POWER / RATED THERMAL POWERRRH = Thermal power reduction required to compensate for each1% that FAH(X,Y) exceeds its limit.2.6.3 TRH = 0.0334 when 0.8 < P < 1.0TRH = 0.0167 when P < 0.8P = THERMAL POWER / RATED THERMAL POWERTRH = Reduction in Overtemperature Delta T K1 setpoint required tocompensate for each 1% that FAH(X,Y) exceeds its limit.SEQUOYAH-UNIT 1Pae6o16RvsnIPage 6 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.6.4 The appropriate factor for increase in FAHM (X,Y) for compliance with-SR 3.2.2.1 and SR 3.2.2.2 is specified as follows:For all cycle burnups, use 2.0%2.6.5 ITS 3.2.2 Required Action A.4 reduces the Overtemperature Delta Tsetpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the FAH minmargin.*2.6.6 ITS 3.2.2 Required Action B.1 reduces the Overtemperature Delta Tsetpoint (K1 term in Table 3.3.1-1) by >- TRH multiplied by the f1(Al)min margin.2.7 AXIAL FLUX DIFFERENCE -AFD (TS 3.2.3)2.7.1 The AFD limits are specified in Figure 3SEQUOYAH-UNIT 1Pae7o16RvsnIPage 7 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.8 Reactor Trip System Instrumentation (TS *3.3.1)2.8.1 Trip Reset Term [f1(Al)] for Overtemperature Delta-T Trip*The following parameters are required to specify the power level-dependentf1(AI) trip reset term limits for Table 3.3.1-1 (function 6), OvertemperatureDelta-T trip function:2.8.1.1 QTNL = -20%where QTNL = the maximum negative Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.1.2 QTPL = +5%where QTPL = the maximum positive Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.1.3 QTNS = 2.50%where QTNS = the percent reduction in Overtemperature Delta-Ttrip setpoint for each percent that the magnitudeof Al exceeds its negative limit at RATEDTHERMAL POWER (QTNL).2.8.1.4 QTPS = 1.40%where QTPS = the percent reduction in Overtemperature Delta-Ttrip setpoint for each percent that the magnitudeof Al exceeds its positive limit at RATEDTHERMAL POWER (QTPL).SEQUOYAH-UNIT 1 ae8o 6RvsoPage 8 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.8.2 Trip Reset Term [f2(AI)] for Overpower Delta-T TripThe following parameters are required to specify the power level-dependent f2(AI) trip reset term limits for Table 3.3.1-1 (function 7),Overpower Delta-T trip function:*2.8.2.1 QPNL = -25%where QPNL = the maximum negative Al setpoint at RATEDTHERMAL *POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.2.2 QPPL = +25%where QPPL = the maximum positive Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.2.3 QPNS = 1.70%where QPNS = the percent reduction in Overpower Delta-T tripsetpoint for each percent that the magnitude of Alexceeds its negative limit at RATED THERMALPOWER (QPNL).2.8.2.4 QPPS = 1.70%where QPPS = the percent reduction in Overpower Delta-T tripsetpoint for each percent that the magnitude of Al> exceeds its positive limit at RATED.THERMALPOWER (QPPL).2.9 Boron Concentration (TS 3.9.1)2.9.1 The refueling boron concentration shall be z 2080 ppm.SEQUOYAH-UNIT 1 ae9o 6RvsoPage 9 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21Table 1COLR Methodology Topical Reports1. BAW-10180-A, Revision 1, "NEMO-Nodal Expansion Method Optimized," March 1993.(Methodology for TS 3.1 .1-SHUTDOWN MARGIN, 3.1 .3-Moderator TemperatureCoefficient, 3.9.1-Boron Concentration)2. BAW-10169P-A, Revision 0, "RSG Plant Safety Analysis-B&W Safety AnalysisMethodology for Recirculating Steam Generator Plants," October 1989.(Methodology for TS 3.1 .3-Moderator Temperature Coefficient)3. BAW-10163P-A, Revision 0, ."Core Operating Limit Methodology for Westinghouse-Designed PWRs," June 1989.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f1(AI), f2(AI) limits],3.1.5-Shutdown Bank Insertion Limits, 3.1.6-Control Bank Insertion Limits, 3.2.1-HeatF~lux Hot Channel Factor, 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.2.3-AXIALFLUX DIFFERENCE)4. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model,"' March 2001.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)5. BAW-10227P-A, Revision 1, "Evaluation of Advanced Cladding and Structural Material(M5) in PWR Reactor Fuel," June 2003.(Methodology for TS 3.2.1-Hleat Flux Hot Channel Factor)6. BAW-10186P-A, Revision 2, "Extended Burnup Evaluation," June 2003.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)7. EMF-2103P-A, Revision 0, "Realistic Large Break LOCA Methodology for PressurizedWater Reactors,". April 2003.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)8. BAW-1 0241 P-A, Revision 1, "BHTP DNB Correlation Applied with LYNXT," July 2005.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])9. BAW-10199P-A, Revision 0, "The BWU Critical Heat Flux Correlations," August 1996.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])10. BAW-10189P-A, "CHF Testing and Analysis of the Mark-BW Fuel Assembly Design,"January 1996.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])1 1. BAW-10159P-A, "BWCMV Correlation of Critical Heat Fluxin Mixing Vane Grid FuelAssemblies," August .1990.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])12. BAW-10231P-A, Revision 1, "COPERNIC Fuel Rod Design Computer Code," January2004.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f2(AI) limits])-SEQUOYAH-UNIT 1 ae1 f16RvsoPage 10 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21Table 2Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation(TS 3.2.2)AXlAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 1.81282 1.81253 1.8122.4 1.81195 1.81151.1 6 1.81097 1.81068 1.81049 1.809810 1.809211 1.75991 2.06712 2.06643 2.06564 2.06495 2.06421.2 6 2.06367 2.06248 2.06159 2.045710 1.949211 -1.85891 2.34332 2.34193 2.34124 2.33975 2.33891.3 6 2.33817 2.33578 2.31309 2.188610 2.0643______11 1.9439AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.59692 2.53803 2.48274 2.44115 2.43151.4 6 2.48007 2.53568 2.44479 2.355510 2.173811 2.02381 2.67232 2.60613 2.54174 2.49135 2.48011.5 6 2.53807 2.62738 2.53119 2.444710 2.277211 2.09751 2.73082 2.66053 2.59474 2.53715 2.52341.6 6 2.59067 2.70778 2.61179 2.524010 2.375811 2.1662SEQUOYAH-UNIT 1 ae1 f16RvsoPage 11 of 16Revision 1 TableFO 2EU A Uont in CYCEd 2Table 2 (continued)AXIAL(X,Y) ELEVATION(ft) MAP(X,Y,Z)1 2.76642 2.70833 2.63804 2.57915 2.56391.7 6 2.63597 2.77958 2.68709 " 2.579810 2.472611 2.23041 2.79632 2.74663 2.67754 2.61725 2.60101.8 6 2.68027 2.84568 2.75529 2.664810 2.565511 2.29311 2.82352 2.77393 2.71254 2.65235 2.63281.9 6 2.72007 2.90658 2.81939 2.728810 2.6384______11 2.3482AXIAL(X,Y) ELEVATION (if) MAP(X,Y,Z)1 2.43392 2.40603 2.38564 2.34235 2.3114>1.9 6 2.60067 2.50038 2.40049 2.298910 2.148311 .1.96301 2.50572 2.47543 2.44494 2.35915 2.42052.1 6 2.76437 2.64748 2.53609 2.440010 2.327711 2.05491 2.53802 2.52163 2.46194 2.42945 2.42902.3 6 2.82227 2.73348 2.62349 2.518610 2.4215_____11 2.1250SEQUOYAH-UNIT I1ae1 f16RvsoPage 12 of 16Revision 1 TableFO 2EU A UcnItin CYCEd 2Table 2 (continued)AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.64402 2.51603 2.50454 2.44885 2.58032.5 6 2.94817 2.85448 2.72869 2.645010 2.552711 2.17311 2.55542 2.55293 2.51974 2.43755 2.56432.7 6 2.98397 2.88378 2.79399 2.704010 2.599711 2.19951 2.42232 2.56533 2.50754 2.39555 2.72952.9 6 3.09217 3.00708 2.88969 2.805810 2.6974_____11 2.2039AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.24482 2.55353 2.46784 2.32295 2.89133.1 6 3.15157 3.01818 2.96999 2.894110 2.781911 2.18661 2.02282 2.51723 2.40074 2.21955 3.04963.3 6 3.22267 3.14468 3.03509 2.968810 2.853311 2.14731 1.75632 2.45663 2.30624 2.08545 3.20453.5 6 3.29297 3.26278 3.08469 3.0299* 10 2.9117_____11 2.0862SEQUOYAH-UNIT 1 Pg 3o 6RvsoPage 13 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21231220(FuI~y Withdn~wn Regior~ (575~225)p --'Inn I0-Cl)rm0/ ABANK D82040020 __ _ _ _ _40(Fully Inserted)0.20.40.60_8IFraction of RATED THERMAL POWERFIGURE 1Rod Bank Insertion Limits Versus THERMAL POWER, Four Loop Operation(TS 3.1.6)* Fully withdrawn region shall be the condition where shutdown and control banks areat a position within the interval of 225 and <231 steps withdrawn, inclusive.Fully withdrawn shall be the position as defined belowCycle Burnup (MWd/mtU)>0Steps Withdrawn-> 225 to < 231This figure is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in operation.If the LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power levelmust be reduced by 1 .3% in power, and the rod insertion limit lines must be increased by 3 steps withdrawn untilthe LEFM is returned to operation.SEQUOYAH-UNIT 1 ae1 f16RvsoPage 14 of 16Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 211.21.00.80.60.40.20.0Eeaio K Iz)( )0.00 10006,25 1000\ IIiIElvaio K!z0246-Core Height (Feet)81012FIGURE 2K(Z) -Normalized FQ(X,Y,Z) as a Function of Core Height(TS 3.2.1)SEQUOYAH-UNIT 1Page 15 of 16 RvsoRevision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21a.000.'II-a'UII-01201101009080706050403020100III I I(710) UnaccieptableI_--hOpe rationI-_ -. I_S I I 1COLR FOR SEQUOYAH UNIT 1 CYCLE 21I q]IILIII' ! i '-50-40 20 -10 0 10 20 30Flux Difference (Al) %FIGURE 3AXIAL FLUX DIFFERENCE Limits As AFunction of RATED THERMAL POWERFor Burnup Range 0 EFPD to EOL(TS 3.2.3)4050This figure is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in operation.If the LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power levelmust be reduced by 1.3% in power, and the AFD limit lines must be made more restrictive by 1% in AFD untilthe LEFM is returned to operation.SEQUOYAH-UNIT 1 Pg 6o 6RvsoPage 16 of 16Revision 1 ENCLOSURE 3SEQUOYAH UNIT 2 CYCLE 20CORE OPERATING LIMITS REPORT REVISION 1 QA RecordQA RcordL36 151009 803SEQUOYAH UNIT 2 CYCLE 20CORE OPERATING LIMITS REPORTREVISION IOctober 2015Prepared by:Christine A. Setter, PWR Fuel Engineering DateVerified by:/P,5R Fuel Engineering DatO! eReviewed by:K PWR Fuel Engineering Manager DateBrandon S. Catalanotto, Reactor Engineering Manager Date/ /Approved by:PORC Chairman DatePlant Manager 'DateRevision .._1Pages affected AllReason for Revision: Update for Improved Technical Specifications (ITS) ImplementationSEQUOYAH-UNJT 2Pae1o17Rvsn1Page 1 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 201.0 CORE OPERATING LIMITS REPORTThis CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 2 Cycle 20has been prepared in accordance with the requirements of Technical Specification(TS) 5.6.3.The TSs affected by this Report are listed below:TS COLR COLRSection Technical Specification COLR Parameter Section Page3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.1 3BOL MTC Limit 2.2.1 4313 Moderator Temperature EOL MTC Limit 2.2.2 4Coefficient (MTC) 300Oppm Surveillance Limit 2.2.3 460 ppm Surveillance Limit 2.2.4 43.1.4 Rod Group Alignment Limits SDM 2.1.3 3Shutdown Bank Insertion Limits 2.3 43.1.5 Shutdown Bank Insertion LimitsSD214 3CotoS anDnetinLmt 2..4 53.1.6rCntrolnBnkIInsetionnLiitsiSs 2.14 33.1.8 PHYSICS TESTS Exceptions -SDM 2.1.6 3MODE 2FTP 2.5.1 6K(Z) 2.5.2 6NSLOPEAFD 2.5.3 6321 Heat Flux Hot ChanneiFactor PSLOPEAFD 2.5.4 6(F0(X,Y,Z)) NSLOPEf2(AI) 2.5.5 6PSLOPEf2(AI) 2.5.6 6FQ(X,Y,Z) Appropriate Factor 2.5.7 6___________________ITS LCO 3.2.1 Required Action A.3 2.5.8 6MAP(X,Y,Z) 2.6.1 6RRH 2.6.2 6322 Nuclear Enthalpy Rise Hot TRH 2.6.3 6Channel Factor (FAH(X,Y)) FAH(X,Y) Appropriate Factor 2.6.4 7ITS 3.2.2 Required Action A.4 2.6.5 7ITS 3.2.2 Required Action B.1 2.6.6 7323 AXIAL FLUX DIFFERENCE AOLmt .(AFD) _ _ _ _ _ _ _ _ _ _ _331 Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS 2.8.1 8Instrumentation QPNL, QPPL, QPNS, and QPPS 2.8.2 93.9.1 Boron Concentration Refueling Boron Concentration 2.9 9CORE OPERATING LlMITS Aayia ehd5.6.3 REOT(OR nltclMtos2.0 3SEQUOYAH-UNIT 2Pae2o17Risn1Page 2 of 17Revision 1 COLR FoR SEQUOYAH UNIT 2 CYCLE 202.0 OPERATING LIMITSThe cycle-specific parameter limits for the TS listed in section 1 .0 are presented inthe following subsections. These limits have been developed using the NRCapproved methodologies specified in TS 5.6.3. The versions of the topical reportswhich describe the methodologies used for this cycle are listed in Table 1.The following abbreviations are used in this section:,BOL stands for Beginning of Cycle LifeEOL stands for End of Cycle LifeRTP stands for RATED THERMAL POWER2.1 SHUTDOWN MARGIN -SOM (TS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8)2.1.1 For TS 3.1.1, SOM shall be >_1.6 %Ak/kin MODE 2 with keff < 1.0, MODE 3 and MODE 42.1.2 For TS 3.1.1, SDM shall be >_1.0 %Ak/kin MODE 5.2.1.3 For TS 3.1.4, SDM shall be >1.6 %Ak/kin MODE 1 and MODE 2.2.1.4 For TS 3.1.5, SDM shall be >_1.6 %Ak/kin MODE 1 and MODE 2.2.1.5 For TS 3.1.6, SDM shall be >__1.6 %Ak/kin MODE 1 and MODE 2 with keff> 1.0.2.1.6 For TS 3.1.8, SDM shall, be >_.1.6 %Ak/kin MODE 2.SEQUOYAH-UNIT 2Pae3o17RvsnIPage 3 of 17.Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.2Moderator Temperature Coefficient -MTC (TS 3.1.3)2.2.1 The BOL MTC limit is:less positive than2.2.2 The EOL MTC limit is:less negative than or equal to2.2.3 The 300 ppm Surveillance limit is:less negative than or equal to2.2.4 The 60 ppm Surveillance limit is:less negative than or equal to-0.16 x10-5 Ak/k/°F.-4.50 x 1 0A Ak/k/°F.-3.75 x 1 04 Ak/k/°F.-4.20 x10A Ak/k/°F.2.3Shutdown Bank Insertion Limits (TS 3.1.5)2.3.1 Each shutdown bank shall be withdrawn to a position as definedbelow:SEQUOYAH-UNIT 2Pae4o17RvsnI* Page 4 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.4Control Bank Insertion Limits (TS 3.1.6)2.4.1 The control banks Shall be limited in physical insertion as shown inFigure 1.2.4.2 Each control bank shall be considered fully withdrawn from the coreat>__225 steps.2.4.3 The control banks shall be operated in sequence by withdrawal ofBank A, Bank B, Bank C, and Bank 0. The control banks shall besequenced in reverse order upon insertion.2.4.4 Each control bank not fully withdrawn from the core shall be operatedwith the following overlap as a function of full out position.Full Out Position Bank Overlap Bank Difference(ts) (steps) (steps)225 9712226 9812227 99 128__________228 100 128229 101 128230 102 128231 103 "128SEQUOYAH-UNIT 2Pae5o17RvsnIPage 5 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.5 Heat Flux Hot Channel Factor- FQ(X,Y,Z) (TS 3.2.1)RTP2.5.1 FQ = 2.622.5.2 K(Z) is provided in Figure 22.5.3 NsLoPEAFD = 1.442.5.4 PSLOPEAFD = 1.76-2.5.5 NSLOPEf2(/I) = 1.482.5.6 PSLOPEf2(AI) = 2.98M2.5.7 The appropriate factor for increase in FQ (X,Y,Z) for compliancewith SR 3.2.1.2 and SR 3.2.1.3 is specified as follows:For cycle burnups: 0 to 3312 MWd/mtU, use 2.0%For cycle burnups: > 3312 to 3864 MWd/mtU, use 2.12%For cycle* burnups: > 386,4 MWd/mtU, use 2.0%2.5.8 ITS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta TTrip setpoints (value of K4) at least 1% (in AT span) for each 1% thatFQC(X,Y,Z) exceeds its limit.2.6 Nuclear Enthalpy Rise Hot Channel Factor -FAH(X,Y) (TS 3.2.2)2.6.1 MAP(X,Y,Z) is provided in Tables 2a and 2b.2.6.2 RRH = 3.34 when 0.8 < P_ 1.0RRHIl.67 whenP<0.8P = THERMAL POWER / RATED THERMAL POWERRRH = Thermal power reduction required to compensate for each*1% that FAH(X,Y) exceeds its limit.2.6.3 TRH = 0.0334 when 0.8 < P < 1.0TRH = 0.01 67 when P < 0.8P = THERMAL POWER I RATED THERMAL POWERTRH = Reduction in Overtemperature Delta T K1 setpoint required tocompensate for each 1 % that FAH(X,Y) exceeds its limit.SEQUOYAH-UNIT 2 Pg f1Page 6 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.6.4 The appropriate factor for increase in FAHM (X,Y) for compliance withSR 3.2.2.1 and SR 3.2.2.2 is specified as follows:For all cycle burnups, use 2.0%:2.6.5 ITS 3.2.2 Required Action A.4 reduces the overtemperature Delta Tsetpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the FAN minmargin.2.6.6 ITS 3.2.2 Required Action 8.1 reduces the Overtemperature Delta Tsetpoint (K1 term in Table 3.3.1-1) by > TRH multiplied by the f1 (Al)min margin.2.7 AXIAL FLUX DIFFERENCE -AFD (TS 3.2.3)2.7.1 The AFD limits are specified in Figure 3SEQUOYAH-UNIT 2Pae7o17RvsnIPage 7 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.8 Reactor Trip System Instrumentation (TS 3.3.1)2.8.1 Trip Reset Term [f1(AI)] for Overtemperature Delta-T TripThe following parameters are required to specify the power level-dependentf1(AI) trip reset term limits for Table 3.3.1-1 (function 6), OvertemperatureDelta-T trip function:2.8.1 .1 QTNL = -20%where QTNL = the maximum negative Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.1.2 QTPL = +5%where QTPL = the maximum positive AlI setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.1.3 QTNS = 2.50%where QTNS = the percent reduction in Overtemperature Delta-Ttrip setpoint for each percent that the magnitudeof Al exceeds its negative limit at RATEDTHERMAL POWER (QTNL).2.8.1.4 QTPS = 1.40%where QTPS = the percent reduction in Overtemperature Delta-Ttrip setpoint for each percent that the magnitudeof Al exceeds its positive limit at RATEDTHERMAL POWER (QTPL).SEQUOYAH-UNIT 2Pae8o17Rvsn1Page 8 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 202.8.2 Trip Reset Term [fz(AI)] for Overpower Delta-T TripThe following parameters are required to specify the power level-dependent f2(AI)trip reset term limits for Table 3.3.1-1 (function 7), Overpower Delta-T trip function:.2.8.2.1 QPNL =-25%Where QPNL = the maximum negative Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.2.2 QPPL = +25%where QPPL = the maximum positive Al setpoint at RATEDTHERMAL POWER at which the trip setpoint isnot reduced by the axial power distribution.2.8.2.3 QPNS = 1.70%where QPNS = the percent reduction in Overpower Delta-Ttrip setpoint for each percent that themagnitude of Al exceeds its negative limit atRATED THERMAL POWER (QPNL).2.8.2.4 QPPS = 1.70%where QPPS = the percent reduction in Overpower Delta-Ttrip setpoint for each percent that themagnitude of Al exceeds its positive limit atRATED THERMAL POWER (QPPL).2.9 Boron Concentration (TS 3.9.1)2.9.1 The refueling boron concentration shall be > 2000 ppm.SEQUOYAH-UNIT 2Pae9o17Rvsn1Page 9 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20Table 1COLR Methodology Topical Reports1. BAW-1 0180-A, Revision 1, "NEMO-Nodal Expansion Method Optimized," March 1993.(Methodology for TS 3.1.1-SHUTDOWN MARGIN, 3.1.3-Moderator TemperatureCoefficient, 3.9.1-Boron Concentration)-2. BAW-10169P-A, Revision 0, "RSG Plant Safety Analysis-B&W Safety AnalysisMethodology for Recirculating Steam Generator Plants," October 1989.(Methodology for TS 3.1 .3-Moderator Temperature Coefficient)3. BAW-1 01 63P-A, Revision 0, "Core Operating Limit Methodology for Westinghouse-Designed PWRs," June 1989.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f1(AI), f2(AI) limits],3.1.5-Shutdown Bank Insertion Limits, 3.1.6-Control Bank Insertion Limits, 3.2.1-HeatFlux Hot Channel Factor, 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.2.3-AXIALFLUX DIFFERENCE)4. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model," March 2001.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)5. BAW-1 0227P-A, Revision 1, "Evaluation of Advanced Cladding and Structural Material(M5) in PWR Reactor Fuel,"' June 2003.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)6. BAW-10186P-A, Revision 2, "Extended Burnup Evaluation," June 2003.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)7. EMF-2103P-A, Revision 0, "Realistic Large Break LOCA Methodology for PressurizedWater Reactors," April 2003.(Methodology for TS 3.2.1-Heat Flux Hot Channel Factor)8. BAW-1 0241 P-A, Revision 1, "BHTP DNB Correlation Applied with LYNXT," July 2005.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])9. BAW-10199P-A, Revision 0, "The BWU Critical Heat Flux Correlations," August 1996.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])10. BAW-10189P-A, "CHF Testing and Analysis of the Mark-BW Fuel Assembly Design,"January 1996.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(Al) limits])11. BAW-1 01 59P-A, "BWCMV Correlation of Critical Heat Flux in Mixing Vane Grid FuelAssemblies," August 1990.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-ReactorTrip System Instrumentation [f1(AI) limits])12. BAW-10231 P-A, Revision .1, "COPERNIC Fuel Rod Design Computer Code," January2004.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f2(Al) limits])SEQUOYAH-UNIT 2 Pg 0o 7RvsoPage 10 of 17Revision 1 CQLR FOR SEQUOYAH UNIT 2 CYCLE 20Table 2aMaximum Allowable Peaking Limits MAP(X,Y,Z) for OperationAdvanced W17 HTPTMFuel (TS 3.2.2)AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 1.81282 1.81253 1.81224 1.81195 1.81151.1 6 1.81097 1.81068 1.81049 1.809810 1.8092______11 1.75991 2.06712 2.06643 2.06564 2.06495 2.06421.2 6 2.06367 2.06248 2.06159 2.045710 1.9492_____11 1.85891 2.34332 2.34193 2.34124 2.33975 2.33891.3 6 2.3381-7 2.33578 2.31309 2.188610 2.0643______11 1.9439AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.59692 2.53803 2.48274 2.44115 2.43151.4 6 2.48007 2.53568 2.44479 2.355510 2.173811 2.02381 2.67232 2.60613 2.54174 2.49135 2.48011.5 6 2.53807 2.62738 2.53119 2.444710 2.277211 2.09751 2.73082 2.66053. 2.59474 2.53715 2.52341.6 6 2.59067 2.70778 2.61179 2.524010 2.3758_ _ _ _ _11 2.1662SEQUOYAH-UNIT 2Pae1of7eisnIPage 11 of 17Revision 1 CO ablFO 2OaH UcnIti2n YCed 20Table 2a (continued)AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 ,2.76642 2.70833 2.63804 2.57915 2.56391.7 6 2.6359,7 2.77958 2.68709 2.579810 2.472611 2.23041 2.79632 2.74663 2.67754 2.61725 2.60101.8 6 2.68027 2.84568 2.75529 2.664810 2.565511 2.29311 2.82352 2.77393 2.71254 2.65235 2.63281.9 6 2.72007 2.90658 2.81939 2.728810 2.6384_____11 2.3482AXlAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.43392 2.40603 2.38564 2.34235 2.3114>1.9 6 2.60067 2.50038 2.40049 2.298910 2.1483_____11 1.96301 2.50572 2.47543 2.44494 2.35915 2.42052.1 6 2.76437 2.64748 2.53609 2.440010 2.3277_____11 2.05491 2.53802 2.52163 2.46194 2.42945 2.42902.3 6 2.82227 2.73348 2.62349 2.518610 2.4215_____11 2.1250SEQUOYAH-UNIT 2Pae1of7Page 12 of 17Revision 1 TableFO 2OaH UcnIti2nCYLEd 2Table 2a (continued)AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.64402 2.5160' 3 2.50454 2.44885 2.58032.5. 6 2.94817 2.85448 2.72869 2.645010 2.5527_____11 2.17311 2.55542 2.55293 2.51974 2.43755 2.56432.7 6 2.98397 2.88378 2.79399 2.704010 .2.599711 2.19951 2.42232 2.56533 2.50754 2.39555 2.72952.9 6 3.09217 3.00708 2.88969 2.805810 2.6974_____11 2.2039AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)1 2.24482 2.55353 2.46784 2.32295 2.89133.1 6 3.15157 3.01818 2.96999 2.894110 2.781911 2.18661 2.02282 2.51723 2.40074 2.21955 3.04963.3 6 3.22267 3.14468 3.03509 2.968810 2.853311 2.14731. 1.75632 2.45663 2.30624 2.08545 3.20453.5 6 3.29297 3.26278 3.08469 .3.029910. 2.9117_____11 2.0862SEQUOYAH-UNIT 2 Pg 3f7RvsoPage 13 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20Table 2bMaximum Allowable Peaking Limits MAP(X,Y,Z) for OperationMark-BW Fuel (TS 3.2.2)AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)2 1.93434 1.93001.1 6 1.92348 1.911510 1.88942 2.16634 2.15581.2 6 2.14108 2.1153'10 2,05822 *2.40234 2.38251.3 6 2.35998 2.3100_______10 2.17602 2.64534 2.61361.4 6 2.56108 2.419910 2.27872 2.71894 2.81811.5 6 2.67358 2.528010 2.37492 2.77204 2.92191.7 6 2.86418 2.706410 2.5539AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z)2 2.81434 2.98561.9 6 3.00738 2.850910 2.70482 2.44054 2.4405>1.9 6 2.73768 2.590610 2.34562 2.58814 2.58812.2 6 2.98998 2.780010 2.53672 2.61114 2.61112.6 6 3.29478 3.205510 2.80492 2.91424 2.914236 4.02168 3.652710 3.17112 2.96184 2.96183.5 6 4.23518 3.745210 3.3214SEQUOYAH-UNIT 2 Pg 4o 7RvsoPage 14 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20r- /~- BA K C/* 140& (u120 8w100 _______BANK 0DZ8040 /20,0 {.09,o) ________ ________ _______ _______0 0.2 0.A 0.6 0_8(Fully Inserted)Fraction of RATED THERMAL POWERFIGURE 1Rod Bank Insertion Limits Versus THERMAL POWER, Four Loop Operation(TS 3.1.6)* Fully withdrawn region shall be the condition where shutdown and control banks areat a position within the interval of >225 and <231 steps withdrawn, inclusive.Fully withdrawn shall be the position as defined below,Cycle Burnup (MWd/mtU) Steps Withdrawn0 225 to -231This figure is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in operation.If the LEEM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power levelmust be reduced by 1.3% in power, and the rod insertion limit lines must be increased by 3 steps withdrawnuntil the LEFM is returned to operation.SEQUOYAH-UNIT 2 Pg 5o 7RvsoPage 15 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 201.21.00.80.60.40.20.0I 2 2 II 2 I I-2 I I II I I2 I4-----22 2 2I 2 2 I2 2Elevation K(z)(ft)0.000 1.00006.285 1.0000 -~----------2 7.995 1.0000 2 2 22 9.705 1.0000 2 2 212.000 1.0000 2 2-2 2 I2 2 2 22 2 2 2I. 2 2 22 I I 2 II I I0246Core Height (Feet)1012FIGURE 2K(Z) -Normalized FQ(X,Y,Z) as a Function of Core Height(TS 3.2.1 )SEQUOYAH-UNIT 2 Pg 6o 7RvsoPage 16 of 17Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20I-1-S1*6='U1201101009080706050403020100I I II---K- ---LU accept be_/--tperatD- 7 -n---I----/ .--°PecirainI* -- I--/ t- --- I(-4b,5o) I IIII I I-- -V- -- -K-I [-.II i I _-- -- i28,o -I 2-----1--K* l--I-II.v-50 30 10 0 10Flux Difference (hl) %20 30 4050FIGURE 3AXIAL FLUX DIFFERENCE Limits As AFunction of RATED THERMAL. POWER.For Burnup Range 0 EFPD to EOL(TS 3.2.3)This figure is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in oPeration.If the LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable *power levelmust be reduced by 1.3% in power, and the AFD limit lines must be made more restrictive by 1% in AFO untilthe LEFM is returned to operation.SEQUOYAH-UNIT 2 Pg 7o 7RvsoPage 17 of 17Revision 1