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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)
	v • d • e

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 November 16, 2015 10 CFR 50.4 ATTN: Document Controi Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

References:

Sequoyah Unit I Cycle 21, and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 1 1. Letter from NRC to TVA, "Sequoyah Nuclear Plant, Units 1 and 2-Issuance of Amendments for the Conversion to the Improved Technical 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 Technical Specifications (TSs) 5.6.3.d, enclosed is the Unit 1 Cycle 21 Core Operating Limits Report (COLR), Revision 1, and Unit 2 Cycle 20OCOLR, Revision 1. In accordance with TSs 5.6.3.d, the COLRs are required to be provided to the Nuclear Regulatory Commission (NRC) within 30 days of issuance for each reload cycle. Sequoyah Units 1 and 2 were issued license amendment Nos. 334 and 327, respectively for improved standard TSs (Reference 1). These license amendments resulted in the revisions to each of the COLRs as discussed in Enclosure

1. The revised COLRs became 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 Commission Page 2 November 16, 2015 Sequoyah Nuclear Plant Enclosures 1.2.3.Units 1 and 2 Core Operating Limits Report Changes Sequoyah Unit I Cycle 21 Core Operating Limits Report, Revision 1 Sequoyah Unit 2 Cycle 20 Core Operating Limits Report, Revision 1 ZTK: DVG Enclosures cc (Enclosures):

NRC Regional Administrator

-Region II NRC Senior Resident Inspector

-SQN ENCLOSURE1I SEQUOYAH UNITS 1 AND 2 CORE OPERATING LIMITS REPORT CHANGES The 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 the conversion of the Sequoyah Technical Specification (TS) to Improved Standard Technical Specification, NUREG-1 431, Revision 4.1. Acronyms for All Rods Out (ARO) and Hot Zero THERMAL POWER (HZP) were removed 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 the COLRs. These parameters involve the Shutdown Margin requirements with references to the associated Limiting Condition for Operation (LCO).5. 60 ppm Moderator Temperature Coefficient limits were added in "Section 2.2 consistent with the NOTE in TSs LCO 3.1.3, "Moderator Temperature Coefficient," Surveillance Requirement 3.1.3.2.6. Control Bank Insertion Limits requirement were added in Section 2.4 as necessary for TSs LCO 3.1.6, "Control Bank Insertion Limits," Surveillance Requirements.

7. Section 2.5 was revised to add information relocated from previous TSs for consistency with 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 consistency with 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, were eliminated as these are defined in the TS Bases.10. The boron concentration limit for TSs LCO 3.9.1, 'Boron Concentration," were added to the COLRs consistent with the approved TVA License Amendment Request.

ENCLOSURE 2 SEQUOYAH UNIT 1 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 1 QA Record QA RcordL36 151009 802 SEQUOYAH UNIT 1 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 1 October 2015 Prepared by: Christine A. Setter, PWR Fuel Engineering Verified by: John E. Strange, P R Fuel Engineering Reviewed by:

unningham, PW Fue ngneig ManagerL radnS. Catalanotto, Reactor Engineering Manager Approved by: Date Date Date/ '&,/S Date Revision Pages affected All Reason for Revision:

Update for Improved Technical Specifications

('ITS) Implementation SEQUOYAH-UNIT 1Pae1o16Rvsn1 Page 1 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit I Cycle 21 has 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 COLR Section Technical Specification COLR Parameter Section Page 3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.1 3 BOL MTC Limit 2.2.1 4 3.3 Moderator Temperature EOL MTC Limit "2.2.2 4 313 Coefficient (MTC) 300 ppm Surveillance Limit 2.2.3 4________________60 ppm Surveillance Limit 2.2.4 4 3.1.4 Rod Group Alignment Limits SDM 2.1.3 3 Shutdown Bank Insertion Limits 2.3 4 3.1.5 Shutdown Bank Insertion LimitsSD2.4 3 CotoS BnDnsrinMiit 2.14 5 3.1.6rConrolnBanknnsertion imitstSD 2.1. 3 3.1.8 PHYSICS TESTS Exceptions-SDM 2.1.6 3 MODE 2 -___________

__FQ 2.5.1 6 K(Z) 2.5.2 6 NSLOPEAFD 2.5.3 6 321 H eat Flux Hot Channel Factor PSLOPEAFD 2.5.4 6 321 (F 0 (X,Y,Z)) NSLOPEf 2 (Al) 2.5.5 6 PSLOPEf 2 (AI) 2.5.6 6 FQ(X,YZ) Appropriate Factor 2.5.7 6 ITS LCO 3.2.1 Required Action A.3 2.5.8 6 MAP(X,Y,Z) 2.6.1 6 RRH 2.6.2 6 Nuclear Enthalpy Rise Hot TRH2.3 6 3.2.2263 6 Channel Factor (FAH(XY))

FAH(X,Y) Appropriate Factor 2.6.4 7 ITS 3.2.2 Required Action A.4 2.6.5 7 ITS 3.2.2 Required Action B.1 2.6.6 7 3.2.3 AXIAL FLUX DIFFERENCE AFD Limits 2.7 7 (AFD)___3.3.1 Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS 2.8.1 8 Instrumentation QPNL, QPPL, QPNS, and QPPS 2.8.2 9 3.9.1 Boron Concentration Refueling Boron Concentration 2.9 9 CORE OPERATING LIMITS Aayia ehd 5.6.3 REOT(OR nltclMtos2.0 3 SEQUOYAH-UNIT 1Pae2o16Rvsn1 Page 2 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.0 .OPERATING LIMITS The cycle-specific parameter limits for the TS listed in section 1 .0 are presented in the following subsections.

These limits have been developed using the NRC approved methodologies specified in TS 5.6.3. The versions of the topical reports which 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 Life EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.1 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/k in 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/k in MODE 5.2.1.3 For TS 3.1.4, SDM shall be > 1.6 %Ak/k in MODE 1 and MODE 2.2.1.4 For TS 3.1.5, SDM shall be >-1.6 %Ak/k in 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/k in MODE 2.SEQUOYAH-UNIT 1 ae3o 6Rvso Page 3 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.2 Moderator Temperature Coefficient

-MTC (TS 3.1.3)2.2.1 The BOL MTC limit is: less positive than 2.2.2 The EOL MTC limit is: less negative than or equal to 2.2.3 The 300 ppm Surveillance limit is: less negative than or equal to 2.2.4 The 60 ppm Surveillance limit is: less negative than or equal to-0.05 x10-5 Ak/k/0 F.-4.50 x 10.4 Ak/k/°F.-3.74 x 10-4 Ak/k/°F.-4.15 xl10 Ak/k/0 F.2.3 Shutdown Bank Insertion Limits (TS 3.1.5)2.3.1 Each shutdown bank shall be withdrawn to a position as defined below: SEQUOYAH-UNIT 1 ae4o 6Rvso page 4 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.4 Control Bank Insertion Limits (TS 3.1.6)2.4.1 The control banks shall be limited in physical insertion as shown in Figure 1.2.4.2 Each cOntrol bank shall be considered fully withdrawn from the core at>__225 steps.2.4.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The control banks shall be sequenced in reverse order upon insertion.

2.4.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap as a function of full out position.Full Out Position (steps) Bank Overlap (steps) Bank Difference (steps)225 97 128 226 98 128 227 99 128 228 100 128 229 101 128 230 102 128 231 103 128 SEQUOYAH-UNIT 1 ae f16Rvso Page 5 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.5 Heat Flux Hot Channel Factor -FQ(X,Y,Z) (TS 3.2.1)2.5.1 FQRT- 2.62 2.5.2 K(Z) is provided in Figure 2 2.5.3 NSLOPEAFD

= 1.21 2.5.4 PSLOPEAFD

= 1.55 2.5.5 NSLOPEf 2 (AI) = 1.48 2.5.6 PSLOPEf 2 (AI) = 2.00 2.5.7 The appropriate factor for increase in FQM(X,Y,Z) for compliance with 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 T Trip setpoints (value of K<4) at least 1 % (in AT span) for each 1 % that FQC(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<1.0 RRH=1.67 whenP<0.8 P = THERMAL POWER / RATED THERMAL POWER RRH = 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 < 1.0 TRH = 0.0167 when P < 0.8 P = THERMAL POWER / RATED THERMAL POWER TRH = Reduction in Overtemperature Delta T K 1 setpoint required to compensate for each 1% that FAH(X,Y) exceeds its limit.SEQUOYAH-UNIT 1Pae6o16RvsnI Page 6 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.6.4 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 T setpoint (K 1 term in Table 3.3.1-1) by > TRH multiplied by the FAH min margin.*2.6.6 ITS 3.2.2 Required Action B.1 reduces the Overtemperature Delta T setpoint (K 1 term in Table 3.3.1-1) by >- TRH multiplied by the f 1 (Al)min margin.2.7 AXIAL FLUX DIFFERENCE

-AFD (TS 3.2.3)2.7.1 The AFD limits are specified in Figure 3 SEQUOYAH-UNIT 1Pae7o16RvsnI Page 7 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.8 Reactor Trip System Instrumentation (TS *3.3.1)2.8.1 Trip Reset Term [f 1 (Al)] for Overtemperature Delta-T Trip*The following parameters are required to specify the power level-dependent f 1 (AI) trip reset term limits for Table 3.3.1-1 (function 6), Overtemperature Delta-T trip function: 2.8.1.1 QTNL = -20%where QTNL = the maximum negative Al setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.

2.8.1.2 QTPL = +5%where QTPL = the maximum positive Al setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.

2.8.1.3 QTNS = 2.50%where QTNS = the percent reduction in Overtemperature Delta-T trip setpoint for each percent that the magnitude of Al exceeds its negative limit at RATED THERMAL POWER (QTNL).2.8.1.4 QTPS = 1.40%where QTPS = the percent reduction in Overtemperature Delta-T trip setpoint for each percent that the magnitude of Al exceeds its positive limit at RATED THERMAL POWER (QTPL).SEQUOYAH-UNIT 1 ae8o 6Rvso Page 8 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 2.8.2 Trip Reset Term [f 2 (AI)] for Overpower Delta-T Trip The following parameters are required to specify the power level-dependent f 2 (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 RATED THERMAL *POWER at which the trip setpoint is not reduced by the axial power distribution.

2.8.2.2 QPPL = +25%where QPPL = the maximum positive Al setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.

2.8.2.3 QPNS = 1.70%where QPNS = the percent reduction in Overpower Delta-T trip setpoint for each percent that the magnitude of Al exceeds its negative limit at RATED THERMAL POWER (QPNL).2.8.2.4 QPPS = 1.70%where QPPS = the percent reduction in Overpower Delta-T trip setpoint for each percent that the magnitude of Al> exceeds its positive limit at RATED.THERMAL POWER (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 6Rvso Page 9 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 Table 1 COLR Methodology Topical Reports 1. BAW-10180-A, Revision 1, "NEMO-Nodal Expansion Method Optimized," March 1993.(Methodology for TS 3.1 .1-SHUTDOWN MARGIN, 3.1 .3-Moderator Temperature Coefficient, 3.9.1-Boron Concentration)

2. BAW-10169P-A, Revision 0, "RSG Plant Safety Analysis-B&W Safety Analysis Methodology 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

[f 1 (AI), f 2 (AI) limits], 3.1.5-Shutdown Bank Insertion Limits, 3.1.6-Control Bank Insertion Limits, 3.2.1-Heat F~lux Hot Channel Factor, 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.2.3-AXIAL FLUX 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 Pressurized Water 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-Reactor Trip System Instrumentation

[f 1 (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-Reactor Trip System Instrumentation

[f 1 (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-Reactor Trip System Instrumentation

[f 1 (AI) limits])1 1. BAW-10159P-A, "BWCMV Correlation of Critical Heat Fluxin Mixing Vane Grid Fuel Assemblies," August .1990.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor Trip System Instrumentation

[f 1 (AI) limits])12. BAW-10231P-A, Revision 1, "COPERNIC Fuel Rod Design Computer Code," January 2004.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation

[f 2 (AI) limits])-SEQUOYAH-UNIT 1 ae1 f16Rvso Page 10 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 Table 2 Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation (TS 3.2.2)AXlAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 1 1.8128 2 1.8125 3 1.8122.4 1.8119 5 1.8115 1.1 6 1.8109 7 1.8106 8 1.8104 9 1.8098 10 1.8092 11 1.7599 1 2.0671 2 2.0664 3 2.0656 4 2.0649 5 2.0642 1.2 6 2.0636 7 2.0624 8 2.0615 9 2.0457 10 1.9492 11 -1.8589 1 2.3433 2 2.3419 3 2.3412 4 2.3397 5 2.3389 1.3 6 2.3381 7 2.3357 8 2.3130 9 2.1886 10 2.0643______11 1.9439 AXIAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 1 2.5969 2 2.5380 3 2.4827 4 2.4411 5 2.4315 1.4 6 2.4800 7 2.5356 8 2.4447 9 2.3555 10 2.1738 11 2.0238 1 2.6723 2 2.6061 3 2.5417 4 2.4913 5 2.4801 1.5 6 2.5380 7 2.6273 8 2.5311 9 2.4447 10 2.2772 11 2.0975 1 2.7308 2 2.6605 3 2.5947 4 2.5371 5 2.5234 1.6 6 2.5906 7 2.7077 8 2.6117 9 2.5240 10 2.3758 11 2.1662 SEQUOYAH-UNIT 1 ae1 f16Rvso Page 11 of 16 Revision 1 TableFO 2EU A Uont in CYCEd 2 Table 2 (continued)

AXIAL(X,Y)

ELEVATION(ft)

MAP(X,Y,Z) 1 2.7664 2 2.7083 3 2.6380 4 2.5791 5 2.5639 1.7 6 2.6359 7 2.7795 8 2.6870 9 " 2.5798 10 2.4726 11 2.2304 1 2.7963 2 2.7466 3 2.6775 4 2.6172 5 2.6010 1.8 6 2.6802 7 2.8456 8 2.7552 9 2.6648 10 2.5655 11 2.2931 1 2.8235 2 2.7739 3 2.7125 4 2.6523 5 2.6328 1.9 6 2.7200 7 2.9065 8 2.8193 9 2.7288 10 2.6384______11 2.3482 AXIAL(X,Y)

ELEVATION (if) MAP(X,Y,Z) 1 2.4339 2 2.4060 3 2.3856 4 2.3423 5 2.3114>1.9 6 2.6006 7 2.5003 8 2.4004 9 2.2989 10 2.1483 11 .1.9630 1 2.5057 2 2.4754 3 2.4449 4 2.3591 5 2.4205 2.1 6 2.7643 7 2.6474 8 2.5360 9 2.4400 10 2.3277 11 2.0549 1 2.5380 2 2.5216 3 2.4619 4 2.4294 5 2.4290 2.3 6 2.8222 7 2.7334 8 2.6234 9 2.5186 10 2.4215_____11 2.1250 SEQUOYAH-UNIT I1ae1 f16Rvso Page 12 of 16 Revision 1 TableFO 2EU A UcnItin CYCEd 2 Table 2 (continued)

AXIAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 1 2.6440 2 2.5160 3 2.5045 4 2.4488 5 2.5803 2.5 6 2.9481 7 2.8544 8 2.7286 9 2.6450 10 2.5527 11 2.1731 1 2.5554 2 2.5529 3 2.5197 4 2.4375 5 2.5643 2.7 6 2.9839 7 2.8837 8 2.7939 9 2.7040 10 2.5997 11 2.1995 1 2.4223 2 2.5653 3 2.5075 4 2.3955 5 2.7295 2.9 6 3.0921 7 3.0070 8 2.8896 9 2.8058 10 2.6974_____11 2.2039 AXIAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 1 2.2448 2 2.5535 3 2.4678 4 2.3229 5 2.8913 3.1 6 3.1515 7 3.0181 8 2.9699 9 2.8941 10 2.7819 11 2.1866 1 2.0228 2 2.5172 3 2.4007 4 2.2195 5 3.0496 3.3 6 3.2226 7 3.1446 8 3.0350 9 2.9688 10 2.8533 11 2.1473 1 1.7563 2 2.4566 3 2.3062 4 2.0854 5 3.2045 3.5 6 3.2929 7 3.2627 8 3.0846 9 3.0299* 10 2.9117_____11 2.0862 SEQUOYAH-UNIT 1 Pg 3o 6Rvso Page 13 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 231 220(FuI~y Withdn~wn Regior~ (575~225)p --'Inn I 0-Cl)rm 0/ ABANK D 820 400 20 __ _ _ _ _40 (Fully Inserted)0.2 0.4 0.6 0_8 I Fraction of RATED THERMAL POWER FIGURE 1 Rod 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 are at 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)>0 Steps Withdrawn-> 225 to < 231 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 level must be reduced by 1 .3% in power, and the rod insertion limit lines must be increased by 3 steps withdrawn until the LEFM is returned to operation.

SEQUOYAH-UNIT 1 ae1 f16Rvso Page 14 of 16 Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 1.2 1.0 0.8 0.6 0.4 0.2 0.0 Eeaio K Iz)( )0.00 1000 6,25 1000\ I I i I Elvaio K!z 0 2 4 6-Core Height (Feet)8 10 12 FIGURE 2 K(Z) -Normalized FQ(X,Y,Z) as a Function of Core Height (TS 3.2.1)SEQUOYAH-UNIT 1 Page 15 of 16 Rvso Revision 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 a.0 0 0.'I I-a'U II-0 120 110 100 90 80 70 60 50 40 30 20 10 0 I II I I (710) UnaccieptableI_

--hOpe rationI-_ -. I_S I I 1 COLR FOR SEQUOYAH UNIT 1 CYCLE 21 I q]I I L I I I' ! i '-50-40 20 -10 0 10 20 30 Flux Difference (Al) %FIGURE 3 AXIAL FLUX DIFFERENCE Limits As A Function of RATED THERMAL POWER For Burnup Range 0 EFPD to EOL (TS 3.2.3)40 50 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 level must be reduced by 1.3% in power, and the AFD limit lines must be made more restrictive by 1% in AFD until the LEFM is returned to operation.

SEQUOYAH-UNIT 1 Pg 6o 6Rvso Page 16 of 16 Revision 1 ENCLOSURE 3 SEQUOYAH UNIT 2 CYCLE 20 CORE OPERATING LIMITS REPORT REVISION 1 QA Record QA RcordL36 151009 803 SEQUOYAH UNIT 2 CYCLE 20 CORE OPERATING LIMITS REPORT REVISION I October 2015 Prepared by: Christine A. Setter, PWR Fuel Engineering Date Verified by:/P,5R Fuel Engineering DatO! e Reviewed by: K PWR Fuel Engineering Manager Date Brandon S. Catalanotto, Reactor Engineering Manager Date/ /Approved by: PORC Chairman Date Plant Manager 'Date Revision .._1 Pages affected All Reason for Revision:

Update for Improved Technical Specifications (ITS) Implementation SEQUOYAH-UNJT 2Pae1o17Rvsn1 Page 1 of 17 Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 2 Cycle 20 has 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 COLR Section Technical Specification COLR Parameter Section Page 3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.1 3 BOL MTC Limit 2.2.1 4 313 Moderator Temperature EOL MTC Limit 2.2.2 4 Coefficient (MTC) 300Oppm Surveillance Limit 2.2.3 4 60 ppm Surveillance Limit 2.2.4 4 3.1.4 Rod Group Alignment Limits SDM 2.1.3 3 Shutdown Bank Insertion Limits 2.3 4 3.1.5 Shutdown Bank Insertion LimitsSD214 3 CotoS anDnetinLmt 2..4 5 3.1.6rCntrolnBnkIInsetionnLiitsiSs 2.14 3 3.1.8 PHYSICS TESTS Exceptions

-SDM 2.1.6 3 MODE 2 FTP 2.5.1 6 K(Z) 2.5.2 6 NSLOPEAFD 2.5.3 6 321 Heat Flux Hot ChanneiFactor PSLOPEAFD 2.5.4 6 (F 0 (X,Y,Z)) NSLOPEf 2 (AI) 2.5.5 6 PSLOPEf 2 (AI) 2.5.6 6 FQ(X,Y,Z)

Appropriate Factor 2.5.7 6___________________ITS LCO 3.2.1 Required Action A.3 2.5.8 6 MAP(X,Y,Z) 2.6.1 6 RRH 2.6.2 6 322 Nuclear Enthalpy Rise Hot TRH 2.6.3 6 Channel Factor (FAH(X,Y))

FAH(X,Y) Appropriate Factor 2.6.4 7 ITS 3.2.2 Required Action A.4 2.6.5 7 ITS 3.2.2 Required Action B.1 2.6.6 7 323 AXIAL FLUX DIFFERENCE AOLmt .(AFD) _ _ _ _ _ _ _ _ _ _ _331 Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS 2.8.1 8 Instrumentation QPNL, QPPL, QPNS, and QPPS 2.8.2 9 3.9.1 Boron Concentration Refueling Boron Concentration 2.9 9 CORE OPERATING LlMITS Aayia ehd 5.6.3 REOT(OR nltclMtos2.0 3 SEQUOYAH-UNIT 2Pae2o17Risn1 Page 2 of 17 Revision 1 COLR FoR SEQUOYAH UNIT 2 CYCLE 20 2.0 OPERATING LIMITS The cycle-specific parameter limits for the TS listed in section 1 .0 are presented in the following subsections.

These limits have been developed using the NRC approved methodologies specified in TS 5.6.3. The versions of the topical reports which 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 Life EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.1 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/k in 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/k in MODE 5.2.1.3 For TS 3.1.4, SDM shall be >1.6 %Ak/k in MODE 1 and MODE 2.2.1.4 For TS 3.1.5, SDM shall be >_1.6 %Ak/k in MODE 1 and MODE 2.2.1.5 For TS 3.1.6, SDM shall be >__1.6 %Ak/k in MODE 1 and MODE 2 with keff> 1.0.2.1.6 For TS 3.1.8, SDM shall, be >_.1.6 %Ak/k in MODE 2.SEQUOYAH-UNIT 2Pae3o17RvsnI Page 3 of 17.Revision 1

COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.2 Moderator Temperature Coefficient

-MTC (TS 3.1.3)2.2.1 The BOL MTC limit is: less positive than 2.2.2 The EOL MTC limit is: less negative than or equal to 2.2.3 The 300 ppm Surveillance limit is: less negative than or equal to 2.2.4 The 60 ppm Surveillance limit is: less negative than or equal to-0.16 x10-5 Ak/k/°F.-4.50 x 1 0 A Ak/k/°F.-3.75 x 1 04 Ak/k/°F.-4.20 x10A Ak/k/°F.2.3 Shutdown Bank Insertion Limits (TS 3.1.5)2.3.1 Each shutdown bank shall be withdrawn to a position as defined below: SEQUOYAH-UNIT 2Pae4o17RvsnI

Page 4 of 17 Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.4 Control Bank Insertion Limits (TS 3.1.6)2.4.1 The control banks Shall be limited in physical insertion as shown in Figure 1.2.4.2 Each control bank shall be considered fully withdrawn from the core at>__225 steps.2.4.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank 0. The control banks shall be sequenced in reverse order upon insertion.

2.4.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap as a function of full out position.Full Out Position Bank Overlap Bank Difference (ts) (steps) (steps)225 9712 226 9812 227 99 128__________

228 100 128 229 101 128 230 102 128 231 103 "128 SEQUOYAH-UNIT 2Pae5o17RvsnI Page 5 of 17 Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.5 Heat Flux Hot Channel Factor- FQ(X,Y,Z) (TS 3.2.1)RTP 2.5.1 FQ = 2.62 2.5.2 K(Z) is provided in Figure 2 2.5.3 NsLoPEAFD

= 1.44 2.5.4 PSLOPEAFD

= 1.76-2.5.5 NSLOPEf 2 (/I) = 1.48 2.5.6 PSLOPEf 2 (AI) = 2.98 M 2.5.7 The appropriate factor for increase in FQ (X,Y,Z) for compliance with 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 T Trip setpoints (value of K 4) at least 1% (in AT span) for each 1% that FQC(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_ 1.0 RRHIl.67 whenP<0.8 P = THERMAL POWER / RATED THERMAL POWER RRH = 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 < 1.0 TRH = 0.01 67 when P < 0.8 P = THERMAL POWER I RATED THERMAL POWER TRH = Reduction in Overtemperature Delta T K 1 setpoint required to compensate for each 1 % that FAH(X,Y) exceeds its limit.SEQUOYAH-UNIT 2 Pg f1 Page 6 of 17 Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.6.4 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 T setpoint (K 1 term in Table 3.3.1-1) by > TRH multiplied by the FAN min margin.2.6.6 ITS 3.2.2 Required Action 8.1 reduces the Overtemperature Delta T setpoint (K 1 term in Table 3.3.1-1) by > TRH multiplied by the f 1 (Al)min margin.2.7 AXIAL FLUX DIFFERENCE

-AFD (TS 3.2.3)2.7.1 The AFD limits are specified in Figure 3 SEQUOYAH-UNIT 2Pae7o17RvsnI Page 7 of 17 Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.8 Reactor Trip System Instrumentation (TS 3.3.1)2.8.1 Trip Reset Term [f 1 (AI)] for Overtemperature Delta-T Trip The following parameters are required to specify the power level-dependent f 1 (AI) trip reset term limits for Table 3.3.1-1 (function 6), Overtemperature Delta-T trip function: 2.8.1 .1 QTNL = -20%where QTNL = the maximum negative Al setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.

2.8.1.2 QTPL = +5%where QTPL = the maximum positive AlI setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.

2.8.1.3 QTNS = 2.50%where QTNS = the percent reduction in Overtemperature Delta-T trip setpoint for each percent that the magnitude of Al exceeds its negative limit at RATED THERMAL POWER (QTNL).2.8.1.4 QTPS = 1.40%where QTPS = the percent reduction in Overtemperature Delta-T trip setpoint for each percent that the magnitude of Al exceeds its positive limit at RATED THERMAL POWER (QTPL).SEQUOYAH-UNIT 2Pae8o17Rvsn1 Page 8 of 17 Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20 2.8.2 Trip Reset Term [fz(AI)] for Overpower Delta-T Trip The following parameters are required to specify the power level-dependent f 2 (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 RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.

2.8.2.2 QPPL = +25%where QPPL = the maximum positive Al setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.

2.8.2.3 QPNS = 1.70%where QPNS = the percent reduction in Overpower Delta-T trip setpoint for each percent that the magnitude of Al exceeds its negative limit at RATED THERMAL POWER (QPNL).2.8.2.4 QPPS = 1.70%where QPPS = the percent reduction in Overpower Delta-T trip setpoint for each percent that the magnitude of Al exceeds its positive limit at RATED THERMAL POWER (QPPL).2.9 Boron Concentration (TS 3.9.1)2.9.1 The refueling boron concentration shall be > 2000 ppm.SEQUOYAH-UNIT 2Pae9o17Rvsn1 Page 9 of 17 Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 1 COLR Methodology Topical Reports 1. 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 Temperature Coefficient, 3.9.1-Boron Concentration)-

2. BAW-10169P-A, Revision 0, "RSG Plant Safety Analysis-B&W Safety Analysis Methodology 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

[f 1 (AI), f 2 (AI) limits], 3.1.5-Shutdown Bank Insertion Limits, 3.1.6-Control Bank Insertion Limits, 3.2.1-Heat Flux Hot Channel Factor, 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.2.3-AXIAL FLUX 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 Pressurized Water 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-Reactor Trip System Instrumentation

[f 1 (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-Reactor Trip System Instrumentation

[f 1 (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-Reactor Trip System Instrumentation

[f 1 (Al) limits])11. BAW-1 01 59P-A, "BWCMV Correlation of Critical Heat Flux in Mixing Vane Grid Fuel Assemblies," August 1990.(Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor Trip System Instrumentation

[f 1 (AI) limits])12. BAW-10231 P-A, Revision .1, "COPERNIC Fuel Rod Design Computer Code," January 2004.(Methodology for TS 3.3.1-Reactor Trip System Instrumentation

[f 2 (Al) limits])SEQUOYAH-UNIT 2 Pg 0o 7Rvso Page 10 of 17 Revision 1 CQLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 2a Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Advanced W17 HTP T M Fuel (TS 3.2.2)AXIAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 1 1.8128 2 1.8125 3 1.8122 4 1.8119 5 1.8115 1.1 6 1.8109 7 1.8106 8 1.8104 9 1.8098 10 1.8092______11 1.7599 1 2.0671 2 2.0664 3 2.0656 4 2.0649 5 2.0642 1.2 6 2.0636 7 2.0624 8 2.0615 9 2.0457 10 1.9492_____11 1.8589 1 2.3433 2 2.3419 3 2.3412 4 2.3397 5 2.3389 1.3 6 2.3381-7 2.3357 8 2.3130 9 2.1886 10 2.0643______11 1.9439 AXIAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 1 2.5969 2 2.5380 3 2.4827 4 2.4411 5 2.4315 1.4 6 2.4800 7 2.5356 8 2.4447 9 2.3555 10 2.1738 11 2.0238 1 2.6723 2 2.6061 3 2.5417 4 2.4913 5 2.4801 1.5 6 2.5380 7 2.6273 8 2.5311 9 2.4447 10 2.2772 11 2.0975 1 2.7308 2 2.6605 3. 2.5947 4 2.5371 5 2.5234 1.6 6 2.5906 7 2.7077 8 2.6117 9 2.5240 10 2.3758_ _ _ _ _11 2.1662 SEQUOYAH-UNIT 2Pae1of7eisnI Page 11 of 17 Revision 1 CO ablFO 2OaH UcnIti2n YCed 20 Table 2a (continued)

AXIAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 1 ,2.7664 2 2.7083 3 2.6380 4 2.5791 5 2.5639 1.7 6 2.6359, 7 2.7795 8 2.6870 9 2.5798 10 2.4726 11 2.2304 1 2.7963 2 2.7466 3 2.6775 4 2.6172 5 2.6010 1.8 6 2.6802 7 2.8456 8 2.7552 9 2.6648 10 2.5655 11 2.2931 1 2.8235 2 2.7739 3 2.7125 4 2.6523 5 2.6328 1.9 6 2.7200 7 2.9065 8 2.8193 9 2.7288 10 2.6384_____11 2.3482 AXlAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 1 2.4339 2 2.4060 3 2.3856 4 2.3423 5 2.3114>1.9 6 2.6006 7 2.5003 8 2.4004 9 2.2989 10 2.1483_____11 1.9630 1 2.5057 2 2.4754 3 2.4449 4 2.3591 5 2.4205 2.1 6 2.7643 7 2.6474 8 2.5360 9 2.4400 10 2.3277_____11 2.0549 1 2.5380 2 2.5216 3 2.4619 4 2.4294 5 2.4290 2.3 6 2.8222 7 2.7334 8 2.6234 9 2.5186 10 2.4215_____11 2.1250 SEQUOYAH-UNIT 2Pae1of7 Page 12 of 17 Revision 1 TableFO 2OaH UcnIti2nCYLEd 2 Table 2a (continued)

AXIAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 1 2.6440 2 2.5160' 3 2.5045 4 2.4488 5 2.5803 2.5. 6 2.9481 7 2.8544 8 2.7286 9 2.6450 10 2.5527_____11 2.1731 1 2.5554 2 2.5529 3 2.5197 4 2.4375 5 2.5643 2.7 6 2.9839 7 2.8837 8 2.7939 9 2.7040 10 .2.5997 11 2.1995 1 2.4223 2 2.5653 3 2.5075 4 2.3955 5 2.7295 2.9 6 3.0921 7 3.0070 8 2.8896 9 2.8058 10 2.6974_____11 2.2039 AXIAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 1 2.2448 2 2.5535 3 2.4678 4 2.3229 5 2.8913 3.1 6 3.1515 7 3.0181 8 2.9699 9 2.8941 10 2.7819 11 2.1866 1 2.0228 2 2.5172 3 2.4007 4 2.2195 5 3.0496 3.3 6 3.2226 7 3.1446 8 3.0350 9 2.9688 10 2.8533 11 2.1473 1. 1.7563 2 2.4566 3 2.3062 4 2.0854 5 3.2045 3.5 6 3.2929 7 3.2627 8 3.0846 9 .3.0299 10. 2.9117_____11 2.0862 SEQUOYAH-UNIT 2 Pg 3f7Rvso Page 13 of 17 Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20 Table 2b Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Mark-BW Fuel (TS 3.2.2)AXIAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 2 1.9343 4 1.9300 1.1 6 1.9234 8 1.9115 10 1.8894 2 2.1663 4 2.1558 1.2 6 2.1410 8 2.1153'10 2,0582 2 *2.4023 4 2.3825 1.3 6 2.3599 8 2.3100_______10 2.1760 2 2.6453 4 2.6136 1.4 6 2.5610 8 2.4199 10 2.2787 2 2.7189 4 2.8181 1.5 6 2.6735 8 2.5280 10 2.3749 2 2.7720 4 2.9219 1.7 6 2.8641 8 2.7064 10 2.5539 AXIAL(X,Y)

ELEVATION (ft) MAP(X,Y,Z) 2 2.8143 4 2.9856 1.9 6 3.0073 8 2.8509 10 2.7048 2 2.4405 4 2.4405>1.9 6 2.7376 8 2.5906 10 2.3456 2 2.5881 4 2.5881 2.2 6 2.9899 8 2.7800 10 2.5367 2 2.6111 4 2.6111 2.6 6 3.2947 8 3.2055 10 2.8049 2 2.9142 4 2.9142 36 4.0216 8 3.6527 10 3.1711 2 2.9618 4 2.9618 3.5 6 4.2351 8 3.7452 10 3.3214 SEQUOYAH-UNIT 2 Pg 4o 7Rvso Page 14 of 17 Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20 r- /~- BA K C/* 140& (u120 8 w100 _______BANK 0D Z80 40 /20, 0 {.09,o) ________ ________ _______ _______0 0.2 0.A 0.6 0_8 (Fully Inserted)Fraction of RATED THERMAL POWER FIGURE 1 Rod 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 are at 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 -231 This 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 level must be reduced by 1.3% in power, and the rod insertion limit lines must be increased by 3 steps withdrawn until the LEFM is returned to operation.

SEQUOYAH-UNIT 2 Pg 5o 7Rvso Page 15 of 17 Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20 1.2 1.0 0.8 0.6 0.4 0.2 0.0 I 2 2 I I 2 I I-2 I I I I I I 2 I 4-----2 2 2 2 I 2 2 I 2 2 Elevation K(z)(ft)0.000 1.0000 6.285 1.0000 -~----------

2 7.995 1.0000 2 2 2 2 9.705 1.0000 2 2 2 12.000 1.0000 2 2-2 2 I 2 2 2 2 2 2 2 2 I. 2 2 2 2 I I 2 I I I I 0 2 4 6 Core Height (Feet)10 12 FIGURE 2 K(Z) -Normalized FQ(X,Y,Z) as a Function of Core Height (TS 3.2.1 )SEQUOYAH-UNIT 2 Pg 6o 7Rvso Page 16 of 17 Revision 1 COLR FOR SEQUOYAH UNIT 2 CYCLE 20 I-1-S1*6='U 120 110 100 90 80 70 60 50 40 30 20 10 0 I I II---K- ---L U accept be_/--tperatD-7 -n---I----/ .--°PecirainI

-- I--/ t- --- I (-4b,5o) I I I II I I-- -V- -- -K-I [-.II i I _-- -- i28,o -I 2-----1--K* l--I-I I.v-50 30 10 0 10 Flux Difference (hl) %20 30 40 50 FIGURE 3 AXIAL FLUX DIFFERENCE Limits As A Function 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 level must be reduced by 1.3% in power, and the AFD limit lines must be made more restrictive by 1% in AFO until the LEFM is returned to operation.

SEQUOYAH-UNIT 2 Pg 7o 7Rvso Page 17 of 17 Revision 1 Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 November 16, 2015 10 CFR 50.4 ATTN: Document Controi Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

References:

Sequoyah Unit I Cycle 21, and Unit 2 Cycle 20 Core Operating Limits Reports, Revision No. 1 1. Letter from NRC to TVA, "Sequoyah Nuclear Plant, Units 1 and 2-Issuance of Amendments for the Conversion to the Improved Technical 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 Technical Specifications (TSs) 5.6.3.d, enclosed is the Unit 1 Cycle 21 Core Operating Limits Report (COLR), Revision 1, and Unit 2 Cycle 20OCOLR, Revision 1. In accordance with TSs 5.6.3.d, the COLRs are required to be provided to the Nuclear Regulatory Commission (NRC) within 30 days of issuance for each reload cycle. Sequoyah Units 1 and 2 were issued license amendment Nos. 334 and 327, respectively for improved standard TSs (Reference 1). These license amendments resulted in the revisions to each of the COLRs as discussed in Enclosure

1. The revised COLRs became 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 Commission Page 2 November 16, 2015 Sequoyah Nuclear Plant Enclosures 1.2.3.Units 1 and 2 Core Operating Limits Report Changes Sequoyah Unit I Cycle 21 Core Operating Limits Report, Revision 1 Sequoyah Unit 2 Cycle 20 Core Operating Limits Report, Revision 1 ZTK: DVG Enclosures cc (Enclosures):

NRC Regional Administrator

-Region II NRC Senior Resident Inspector

-SQN ENCLOSURE1I SEQUOYAH UNITS 1 AND 2 CORE OPERATING LIMITS REPORT CHANGES The 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 the conversion of the Sequoyah Technical Specification (TS) to Improved Standard Technical Specification, NUREG-1 431, Revision 4.1. Acronyms for All Rods Out (ARO) and Hot Zero THERMAL POWER (HZP) were removed 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 the COLRs. These parameters involve the Shutdown Margin requirements with references to the associated Limiting Condition for Operation (LCO).5. 60 ppm Moderator Temperature Coefficient limits were added in "Section 2.2 consistent with the NOTE in TSs LCO 3.1.3, "Moderator Temperature Coefficient," Surveillance Requirement 3.1.3.2.6. Control Bank Insertion Limits requirement were added in Section 2.4 as necessary for TSs LCO 3.1.6, "Control Bank Insertion Limits," Surveillance Requirements.

7. Section 2.5 was revised to add information relocated from previous TSs for consistency with 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 consistency with 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, were eliminated as these are defined in the TS Bases.10. The boron concentration limit for TSs LCO 3.9.1, 'Boron Concentration," were added to the COLRs consistent with the approved TVA License Amendment Request.

ENCLOSURE 2 SEQUOYAH UNIT 1 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 1 QA Record QA RcordL36 151009 802 SEQUOYAH UNIT 1 CYCLE 21 CORE OPERATING LIMITS REPORT REVISION 1 October 2015 Prepared by: Christine A. Setter, PWR Fuel Engineering Verified by: John E. Strange, P R Fuel Engineering Reviewed by:

unningham, PW Fue ngneig ManagerL radnS. Catalanotto, Reactor Engineering Manager Approved by: Date Date Date/ '&,/S Date Revision Pages affected All Reason for Revision:

Update for Improved Technical Specifications