ML15154A512

Sequoyah, Unit 1 - Cycle 21 Core Operating Limits Report, Revision 0

ML15154A512
Person / Time
Site:	Sequoyah
Issue date:	05/27/2015
From:	Carlin J T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L36 150506 800
Download: ML15154A512 (18)

Text

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000May 27, 201510 CFR 50.4ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001Sequoyah Nuclear Plant, Unit 1Facility Operating License No. DPR-77NRC Docket No. 50-327

Subject:

Sequoyah Unit I Cycle 21 Core Operating Limits ReportIn accordance with Sequoyah Nuclear Plant (SQN) Unit 1 TechnicalSpecification (TS) 6.9.1.14.c, enclosed is the Unit 1 Cycle 21 Core Operating LimitsReport (COLR), Revision 0. In accordance with TS 6.9.1.14.c, the COLR is requiredto be provided to the Nuclear Regulatory Commission within 30 days after the cyclestart-up (Mode 2) for each reload cycle. Sequoyah Unit 1 entered Mode 2 on May15, 2015, for the current reload cycle.There are no new regulatory commitments in this letter. If you have any questions,please contact Erin Henderson, SQN Site Licensing Manager at (423) 843-7170.T. C n /' ,Site Vice PresidentSequoyah Nuclear PlantEnclosureSequoyah Unit 1 Cycle 21 Core Operating Limits Reportcc (Enclosure):NRC Regional Administrator- Region IINRC Senior Resident Inspector -SQN01 ENCLOSURESEQUOYAH UNIT 1 CYCLE 21CORE OPERATING LIMITS REPORT QA RecordL36 150506 800SEQUOYAH UNIT I CYCLE 21CORE OPERATING LIMITS REPORTREVISION 0May 2015Prepared by:W. Andrew Whitener, Nulear Fuels Program & OversightPrepared by:DateMark D. Porter, PWR Fuel EngineeringVerified by:Christine A. Setter, PWR Fuel EngineeringReviewed by:Kithlee ;A. Cunningham, PWR Fuel Engineering ManagerBrandon S. Catalanotto, Reactor SupervisorApproved by:DateDateDateD a- zo/teDateDateS-7/'20--DateDtePO aiPlant ManagerRevision 0Pages affected AllReason for Revision: Initial IssueSEQUOYAH-UNIT 1Page 1 of 16Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 211.0 CORE OPERATING LIMITS REPORTThis Core Operating Limits Report (COLR) for Sequoyah Unit 1 Cycle 21 hasbeen prepared in accordance with the requirements of Technical Specification(TS) 6.9.1.14.The TSs affected by this Report are listed below:TABLE 2.2-1 fl(Al) trip reset function for OTAT Trip (QTNL, QTPL) andrates of trip setpoint decrease per percent Al (QTNS, QTPS)TABLE 2.2-1 f2(AI) trip reset function for OPAT Trip (QPNL, QPPL) andrates of trip setpoint decrease per percent Al (QPNS, QPPS)3/4.1.1.3 Moderator Temperature Coefficient (MTC)3/4.1.3.5 Shutdown Rod Insertion Limit3/4.1.3.6 Control Rod Insertion Limits3/4.2.1 Axial Flux Difference (AFD)3/4.2.2 Heat Flux Hot Channel Factor (FQ(X,Y,Z))3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor (FAH(X,Y))2.0 OPERATING LIMITSThe cycle-specific parameter limits for the specifications listed in section 1.0are presented in the following subsections. These limits have been developedusing the NRC approved methodologies specified in TS 6.9.1.14. Theversions of the topical reports which describe the methodologies used for thiscycle are listed in Table 1.The following abbreviations are used in this section:BOL stands for Beginning of Cycle LifeARO stands for All Rods OutHZP stands for Hot Zero THERMAL POWEREOL stands for End of Cycle LifeRTP stands for RATED THERMAL POWERSEQUOYAH-UNIT 1Page 2 of 16Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.1 Moderator Temperature Coefficient -MTC (Specification 3/4.1.1.3)2.1.1 The MTC limits are:The BOL/ARO/HZP MTC shall be less positive than 0 Ak/k/°F (BOLlimit). With the measured value more positive than-0.05 x 105 Ak/k/OF, establish control rod withdrawal limits to ensurethe MTC remains less positive than 0 Ak/k/°F for all times in core life.The EOL/ARO/RTP MTC shall be less negative than or equalto -4.5 x 10-4 Ak/k/IF.2.1.2 The 300 ppm surveillance limit is:The measured 300 ppm/ARO/RTP MTC shall be less negative thanor equal to -3.74 x 10-4 Ak/k/°F.2.2 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5)2.2.1 The shutdown rods shall be withdrawn to a position as defined below:Cycle Burnup Steps Withdrawn(MWd/mtU)> 0 > 225 to < 2312.3 Control Rod Insertion Limits (Specification 3/4.1.3.6)2.3.1 The control rod banks shall be limited in physical insertion as shownin Figure 1.2.4 Axial Flux Difference -AFD (Specification 3/4.2.1)2.4.1 The axial flux difference (AFD) limits (AFDLimit) are provided inFigure 2.SEQUOYAH-UNIT 1Page 3 of 16Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.5 Heat Flux Hot Channel Factor -FQ(X, YZ) (Specification 3/4.2.2)FQ(X,Y,Z) shall be limited by the following relationships:RTPFQ (X.Y.Z)<

• K(Z) for P > 0.5RTPFQ (XY,Z) 0< .* K(Z) for P5 0.5THERMAL POWERwhere P -RATED THERMAL POWER2.5.1 FoRTP = 2.622.5.2 K(Z) is provided in Figure 3.The following parameters are required for core monitoring per the SurveillanceRequirements of Specification 3/4.2.2:2.5.3 NSLOPEAFD = 1.21where NSLOPEAFD =Negative AFD limit adjustment required tocompensate for each 1 % that FQ (X,Y,Z)exceeds BQDES.2.5.4 PSLOPEAFD = 1.55where PSLOPEAFD =Positive AFD limit adjustment required tocompensate for each 1 % that FQ(X,Y,Z)exceeds BQDES.2.5.5 NSLOPEf2(AI) = 1.48where NSLOPEf2(AI) =Adjustment to negative OPAT f2(AI) limitrequired to compensate for each 1 % thatFQ(X,Y,Z) exceeds BCDES.2.5.6 PSLOPEf2(Al) = 2.00where PSLOPEf2(AI) =Adjustment to positive OPAT f2(Al) limitrequired to compensate for each 1 % thatFQ(X,Y,Z) exceeds BCDES.SEQUOYAH-UNIT 1Page 4 of 16Revision 0 COLR FOR SEQUOYAH UNIT I CYCLE 212.5.7 BQNOM(X,YZ) =2.5.8 BQDES(X,YZ) =2.5.9 BCDES(X,YZ) =Nominal design peaking factor, increased by anallowance for the expected deviation betweenthe nominal design power distribution and themeasurement.Maximum allowable design peaking factor whichensures that the F0 (X,YZ) limit will be preservedfor operation within the LCO limits, includingallowances for calculational and measurementuncertainties.Maximum allowable design peaking factor whichensures that the centerline fuel melt limit will bepreserved for operation within the LCO limits,including allowances for calculational andmeasurement uncertainties.BQNOM(X,Y,Z), BQDES(X,Y,Z), and BCDES(X,Y,Z) databases areprovided for input to the plant power distribution analysis codes on acycle-specific basis and are determined using the methodology forcore limit generation described in the references inSpecification 6.9.1.14.2.5.10 The increase in FQM(X,YZ) for compliance with the4.2.2.2.e Surveillance Requirements is defined as follows.For all cycle burnups, use 2.0%SEQUOYAH-UNIT 1Page 5 of 16Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 212.6Nuclear Enthalpy Rise Hot Channel Factor -FdH(X, V)(Specification 3/4.2.3)FAH(X,Y) shall be limited by the following relationship:FAH(X,Y) -MAP(X,Y,Z) / AXIAL(X,Y)2.6.1 MAP(X,YZ) is provided in Table 2.AXIAL(X,Y) is the axial peak from the normalized axial power shape.The following parameters are required for core monitoring per theSurveillance Requirements of Specification 3/4.2.3:FAHRM(X,Y) _ BHNOM(X,Y)where FAHRM(X,Y) = FAHM (X,Y) / [MAPM / AXIAL(X,Y)]FAHM (X,Y) is' the measured radial peak at location X,Y.MAPM is the value of MAP(X,Y,Z) obtained from Table 2 for themeasured peak.2.6.2 BHNOM(X,Y) =2.6.3 BHDES(X,Y) =2.6.4 BRDES(X,Y) =Nominal design radial peaking factor, increasedby an allowance for the expected deviationbetween the nominal design power distributionand the measurement.Maximum allowable design radial peaking factorwhich ensures that the FAH (X,Y) limit will bepreserved for operation within the LCO limits,including allowances for calculational andmeasurement uncertainties.Maximum allowable design radial peaking factorwhich ensures that the steady state DNBR limitwill be preserved for operation within the LCOlimits, including allowances for calculational andmeasurement uncertainties.BHNOM(X,Y), BHDES(X,Y) and BRDES(X,Y) databases areprovided for input to the plant power distribution analysis computercodes on a cycle-specific basis and are determined using themethodology for core limit generation described in the references inSpecification 6.9.1.14.SEQUOYAH-UNIT 1Page 6 of 16Revision 0 COLR FOR SEQUOYAH UNIT I CYCLE 212.6.5 RRH = 3.34 when 0.8 < P < 1.0RRH = 1.67 when P < 0.8where RRH = Thermal power reduction required to compensatefor each 1 % that FAH(X,Y) exceeds its limit.P = Thermal Power / Rated Thermal Power2.6.6 TRH = 0.0334 when 0.8 < P < 1.0TRH = 0.0167 when P < 0.8Where TRH= Reduction in OTAT K1 setpoint required tocompensate for each 1 % that FAH(X,Y) exceeds itslimit.P = Thermal Power / Rated Thermal Power2.6.7 All cycle burnups shall use a 2% increase in FAHM (X,Y) forcompliance with the 4.2.3.2.d.1 Surveillance Requirement.SEQUOYAH-UNIT 1Page 7 of 16Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 213.03.1REACTOR CORE PROTECTIVE LIMITSTrip Reset Term [fF(AI)] for Overtemperature Delta-T Trip(Specification 2.2.1)The following parameters are required to specify the power level-dependentfl(AI) trip reset term limits for the Overtemperature Delta-T trip function:3.1.1 QTNL = -20%where QTNL =the maximum negative Al setpoint at rated thermalpower at which the trip setpoint is not reduced bythe axial power distribution.3.1.2 QTPL = +5%where QTPL =the maximum positive Al setpoint at rated thermalpower at which the trip setpoint is not reduced bythe axial power distribution.3.1.3 QTNS = 2.50%where QTNS =3.1.4 QTPS = 1.40%the percent reduction in Overtemperature Delta-Ttrip setpoint for each percent that the magnitude ofAl exceeds its negative limit at rated thermal power(QTNL).the percent reduction in Overtemperature Delta-Ttrip setpoint for each percent that the magnitude ofAl exceeds its positive limit at rated thermal power(QTPL).where QTPS =SEQUOYAH-UNIT 1Page 8 of 16Revision 0 COLR FOR SEQUOYAH UNIT I CYCLE 213.2Trip Reset Term ff2(AI)] for Overpower Delta-T Trip (Specification 2.2.1)The following parameters are required to specify the power level-dependentf2(AI) trip reset term limits for the Overpower Delta-T trip function:3.2.1 QPNL = -25%where QPNL =the maximum negative Al setpoint at rated thermalpower at which the trip setpoint is not reduced bythe axial power distribution.3.2.2 QPPL = +25%where QPPL =the maximum positive Al setpoint at rated thermalpower at which the trip setpoint is not reduced bythe axial power distribution.3.2.3 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 thermal power(QPNL).3.2.4 QPPS = 1.70%where QPPS =the percent reduction in Overpower Delta-T tripsetpoint for each percent that the magnitude of Alexceeds its positive limit at rated thermal power(QPPL).SEQUOYAH-UNIT 1Page 9 of 16Revision 0 COLR FOR SEQUOYAH UNIT I CYCLE 21Table 1COLR Methodology Topical Reports1. BAW-10180-A, Revision 1, "NEMO-Nodal Expansion Method Optimized," March 1993.(Methodology for Specification 3/4.1.1.3-Moderator Temperature Coefficient)2. BAW-10169P-A, Revision 0, "RSG Plant Safety Analysis-B&W Safety AnalysisMethodology for Recirculating Steam Generator Plants," October 1989.(Methodology for Specification 3/4.1.1.3-Moderator Temperature Coefficient)3. BAW-10163P-A, Revision 0, "Core Operating Limit Methodology for Westinghouse-Designed PWRs," June 1989.(Methodology for Specifications 2.2.1-Reactor Trip Instrumentation Setpoints [f1(AI),f2(AI) limits], 3/4.1.3.5-Shutdown Rod Insertion Limit, 3/4.1.3.6-Control Rod InsertionLimits, 3/4.2.1-Axial Flux Difference, 3/4.2.2-Heat Flux Hot Channel Factor, 3/4.2.3-Nuclear Enthalpy Rise Hot Channel Factor)4. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model," March 2001.(Methodology for Specification 3/4.2.2-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 Specification 3/4.2.2-Heat Flux Hot Channel Factor)6. BAW-10186P-A, Revision 2, "Extended Burnup Evaluation," June 2003.(Methodology for Specification 3/4.2.2-Heat Flux Hot Channel Factor)7. EMF-2103P-A, Revision 0, "Realistic Large Break LOCA Methodology for PressurizedWater Reactors," April 2003.(Methodology for Specification 3/4.2.2-Heat Flux Hot Channel Factor)8. BAW-1 0241 P-A, Revision 1, "BHTP DNB Correlation Applied with LYNXT," July 2005.(Methodology for Specification 3/4.2.3-Enthalpy Rise Hot Channel Factor)9. BAW-10199P-A, Revision 0, "The BWU Critical Heat Flux Correlations," August 1996.(Methodology for Specification 3/4.2.3-Enthalpy Rise Hot Channel Factor)10. BAW-10189P-A, "CHF Testing and Analysis of the Mark-BW Fuel Assembly Design,"January 1996.(Methodology for Specification 3/4.2.3-Enthalpy Rise Hot Channel Factor)11. BAW-1 01 59P-A, "BWCMV Correlation of Critical Heat Flux in Mixing Vane Grid FuelAssemblies," August 1990.(Methodology for Specification 3/4.2.3-Enthalpy Rise Hot Channel Factor)12. BAW-1 0231 P-A, Revision 1, "COPERNIC Fuel Rod Design Computer Code," January2004.(Methodology for Specification 2.2.1-Reactor Trip Instrumentation Setpoints)SEQUOYAH-UNIT 1Page 10 of 16Revision 0 COLR FOR SEQUOYAH UNIT I CYCLE 21Table 2Maximum Allowable Peaking Limits MAP(X,Y,Z) for OperationAXIAL(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 1.809211 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' 2.064311 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 1Page 11 of 16Revision 0 COLR FOR SEQUOYAH UNIT I CYCLE 21Table 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 2.638411 2.3482AXIAL(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 2.148311 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 2.421511 2.1250SEQUOYAH-UNIT 1Page 12 of 16Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 21Table 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 2.697411 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 2.911711 2.0862SEQUOYAH-UNIT 1Page 13 of 16Revision 0 COLR FOR SEQUOYAH UNIT I CYCLE 21231(Fully Withdrawn Region)*220 -1375,225)200 -7~(1.0,182)18016010 ----BANI C C0140-;P90120MIO,110)WIN -'- BAIPIK D~~,oo80o-60402 0 -o , )0 0.2 0.4 0.6 0.8(Fully Inserted)Fraction of Rated Thermal PowerFIGURE 1Rod Bank Insertion Limits Versus Thermal Power, Four Loop Operation* Fully withdrawn region shall be the condition where shutdown and control banks areat a position within the interval of >225 and <231steps withdrawn, inclusive.Fully withdrawn shall be the position as defined below,Cycle Burnup (MWd/mtU) Steps Withdrawn> 0 > 225 to 5 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 level must bereduced by 1.3% in power, and the rod insertion limit lines must be increased by 3 steps withdrawn until the LEFM isreturned to operation.SEQUOYAH-UNIT 1Page 14 of 16Revision 0 COLR FOR SEQUOYAH UNIT I CYCLE 21120110_______ _100 43~1c ~,(7,1\00)loo -----I "A --- ( -- o--t---1 -- --U ccept ble ___ _ -- _- Unac ceptable9 peratiqn Op'ationgo8 80 Accqptableo Op4rationI-7050 _ _ _ _ _ _¶jý150) __ _ ___o 40 -_ ___ ___ 8 L-10 __ _ _20 --50 30 10 0 10 20 30 40 50Flux Difference (AI) %FIGURE 2Axial Flux Difference Limits As AFunction of Rated Thermal PowerFor Burnup Range 0 EFPD to EOLThis 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 level must bereduced by 1.3% in power, and the AFD limit lines must be made more restrictive by 1% in AFD until the LEFM isreturned to operation.SEQUOYAH-UNIT 1Page 15 of 16Revision 0 COLR FOR SEQUOYAH UNIT I CYCLE 211.21.00.8N0.60.40.20.0---- ---- ------- ------ L -------V -----V -------I-----Elevation K(z)0.000 1.0000-- ---------- ---6.285 1.0000 -;- ------ ----------7.995 1.00009.705 1.000012.000 1.0000----------------------------------------0246Core Height (Feet)FIGURE 381012K(Z) -Normalized FQ(X,Y,Z) as a Function of Core HeightSEQUOYAH-UNIT 1Page 16 of 16Revision 0