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=Text=
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{{#Wiki_filter:Tennessee Valley Authority
{{#Wiki_filter:Tennessee Valley Authority , P ost O ff ice B ox 2000, So d dy Da i sy , T e nn essee 37384-2000 December 21, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-77 NRC Docket No. 50-327 10 CFR 50.4  
, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 December 21, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington
, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-77 NRC Docket No. 50-327 10 CFR 50.4  


==Subject:==
==Subject:==
 
SEQUOYAH UNIT 1 CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 In accordance with Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specification (TS) 5.6.3.d, enclosed is the Unit 1 Cycle 22 Core Operating Limits Report (COLR), Revision 0 that was issued on December 7, 2016. SQN has completed the transition from the Mark-BW fuel design to the Advanced W17 HTP fuel design in Unit 1. Accordingly, the COLR only includes core operating limits associated with the use of Advanced W17 HTP fuel. There are no new regulatory commitments in this letter. If you have any questions, please contact Michael McBrearty , SQN Site Licensing Manager at (423) 843-7170.
SEQUOYAH UNIT 1 CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 In accordance with Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specification (TS) 5.6.3.d, enclosed is the Unit 1 Cycle 22 Core Operating Limits Report (COLR), Revision 0 that was issued on December 7, 2016. SQN has completed the transition from the Mark-BW fuel design to the Advanced W17 HTP fuel design in Unit 1. Accordingly, the COLR only includes core operating limits associated with the use of Advanced W17 HTP fuel. There are no new regulatory commitments in this letter. If you have any questions, please contact Michael McBrearty
Respectfully , Gregory A. Boerschig Site Vice President (interim)
, SQN Site Licensing Manager at (423) 843-7170.
Respectfully
, Gregory A. Boerschig Site Vice President (interim)
Sequoyah Nuclear Plant Enclosure Sequoyah Unit 1 Cycle 22 Core Operating Limits Report cc (Enclosure):
Sequoyah Nuclear Plant Enclosure Sequoyah Unit 1 Cycle 22 Core Operating Limits Report cc (Enclosure):
NRC Regional Administrator-Region II NRC Senior Resident Inspector-SQN ENCLOSURE SEQUOYAH UNIT 1 CYCLE 22 CORE OPERA TING LIMITS REPORT QA Record Prepared by: SEQUOYAH UNIT 1 CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 December 2016 Verified by: L36 161201 800 I 2 / o l / 2-o Date / 1zto\/L.o\(o fvt:JR. Fuel Engineering
NRC Regional Administrator-Region II NRC Senior Resident Inspector-SQN ENCLOSURE SEQUOYAH UNIT 1 CYCLE 22 CORE OPERA TING LIMITS REPORT QA Record Prepared by: SEQUOYAH UNIT 1 CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 December 2016 Verified by: L36 161201 800 I 2 / o l / 2-o Date / 1zto\/L.o\(o fvt:JR. Fuel Engineering
_
_
I 1z-2-2-01(p Date Manager /2 ;, h<. . Date Approved by:
I 1z-2-2-01(p Date Manager /2 ;, h<. . Date Approved by:
Date I Pl Date Date of PORC Affected Revision Approval Pages Reason for Revision 0 17 1-:i-/1111 All Initial issue. SEQUOYAH-UNIT 1 Page 1 of 16 Revision 0
Date I Pl Date Date of PORC Affected Revision Approval Pages Reason for Revision 0 17 1-:i-/1111 All Initial issue. SEQUOYAH-UNIT 1 Page 1 of 16 Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 2 of 16 Revision 0 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 1 Cycle 22 has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.3. The TSs affected by this Report are listed below:
COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 2 of 16 Revision 0 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 1 Cycle 22 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 Section Technical Specification COLR Parameter COLR SectionCOLR Page3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.1 3 3.1.3 Moderator Temperature Coefficient (MTC) BOL MTC Limit EOL MTC Limit 300 ppm Surveillance Limit 60 ppm Surveillance Limit 2.2.1 2.2.2 2.2.3 2.2.4 4 4 4 4 3.1.4 Rod Group Alignment Limits SDM 2.1.3 3 3.1.5 Shutdown Bank Insertion LimitsShutdown Bank Insertion Limits SDM 2.3 4 2.1.4 3 3.1.6 Control Bank Insertion Limits Control Bank Insertion Limits 2.4 5 SDM 2.1.5 3 3.1.8 PHYSICS TESTS Exceptions -
TS Section Technical Specification COLR Parameter COLR SectionCOLRPage3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.1 3 3.1.3 Moderator Temperature Coefficient (MTC) BOL MTC Limit EOL MTC Limit 300 ppm Surveillance Limit 60 ppm Surveillance Limit 2.2.1 2.2.2 2.2.3 2.2.4 4 4 4 4 3.1.4 Rod Group Alignment Limits SDM 2.1.3 3 3.1.5 Shutdown Bank Insertion LimitsShutdown Bank Insertion Limits SDM 2.3 4 2.1.4 3 3.1.6 Control Bank Insertion Limits Control Bank Insertion Limits 2.4 5 SDM 2.1.5 3 3.1.8 PHYSICS TESTS Exceptions -
MODE 2 SDM 2.1.6 3 3.2.1 Heat Flux Hot Channel Factor (F Q(X,Y,Z)) F Q RTP 2.5.1 6 K(Z) 2.5.2 6 NSLOPE AFD2.5.3 6 PSLOPE AFD 2.5.4 6 NSLOPE f2(I) 2.5.5 6 PSLOPE f2(I) 2.5.6 6 F Q(X,Y,Z) Appropriate Factor 2.5.7 6 TS LCO 3.2.1 Required Action A.3 2.5.8 6 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FH(X,Y)) MAP(X,Y,Z) 2.6.1 6 RRH 2.6.2 6 TRH 2.6.3 6 FH(X,Y) Appropriate Factor 2.6.4 7 TS 3.2.2 Required Action A.4 2.6.5 7 TS 3.2.2 Required Action B.1 2.6.6 7 3.2.3 AXIAL FLUX DIFFERENCE (AFD) AFD Limits 2.7 7 3.3.1 Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS QPNL, QPPL, QPNS, and QPPS 2.8.1 8 Instrumentation 2.8.2 9 3.9.1 Boron Concentration Refueling Boron Concentration 2.9 9 5.6.3 CORE OPERATING LIMITS REPORT (COLR)
MODE 2 SDM 2.1.6 3 3.2.1 Heat Flux Hot Channel Factor  
 
(FQ(X,Y,Z))
FQRTP 2.5.1 6 K(Z) 2.5.2 6 NSLOPEAFD2.5.3 6 PSLOPEAFD 2.5.4 6 NSLOPEf2(I) 2.5.5 6 PSLOPEf2(I) 2.5.6 6 FQ(X,Y,Z) Appropriate Factor 2.5.7 6 TS LCO 3.2.1 Required Action A.3 2.5.8 6 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FH(X,Y)) MAP(X,Y,Z) 2.6.1 6 RRH 2.6.2 6 TRH 2.6.3 6 FH(X,Y) Appropriate Factor 2.6.4 7 TS 3.2.2 Required Action A.4 2.6.5 7 TS 3.2.2 Required Action B.1 2.6.6 7 3.2.3 AXIAL FLUX DIFFERENCE (AFD) AFD Limits 2.7 7 3.3.1 Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS QPNL, QPPL, QPNS, and QPPS 2.8.1 8 Instrumentation 2.8.2 9 3.9.1 Boron Concentration Refueling Boron Concentration 2.9 9 5.6.3 CORE OPERATING LIMITS REPORT (COLR)
Analytical Methods Table 110 COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 3 of 16 Revision 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the TS listed in section 1.0 are presented in the following subsections.
Analytical Methods Table 110 COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 3 of 16 Revision 0 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 be en developed using the NRC approved methodologies specified in TS 5.6.3.
These limits have be en 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:
T he 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
BOL stands for Beginning of Cycle Life


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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  
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  


COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 6 of 16 Revision 0 2.5 Heat Flux Hot Channel Factor - F Q(X,Y,Z) (TS 3.2.1) 2.5.1 FQRTP =  2.62 2.5.2 K(Z) is provided in Figure 2 2.5.3 NSLOPEAFD =  1.17 2.5.4 PSLOPEAFD =  1.54 2.5.5 NSLOPEf2(I) =  1.48 2.5.6 PSLOPEf2(I) =  2.27 2.5.7 The appropriate factor for increase in F QM(X,Y,Z) for compliance  with SR 3.2.1.2 and SR 3.2.1.3 is specified as follows:
COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 6 of 16 Revision 0 2.5 Heat Flux Hot Channel Factor - F Q(X,Y,Z) (TS 3.2.1) 2.5.1 F QRTP =  2.62 2.5.2 K(Z) is provided in Figure 2 2.5.3 NSLOPE AFD =  1.17 2.5.4 PSLOPE AFD =  1.54 2.5.5 NSLOPE f2(I) =  1.48 2.5.6 PSLOPE f2(I) =  2.27 2.5.7 The appropriate factor for increase in F Q M(X,Y,Z) for compliance  with SR 3.2.1.2 and SR 3.2.1.3 is specified as follows:
For cycle burnups >1302 MWd/mtU to 3631 MWd/mtU, use 3.15%.
For cycle burnups >1302 MWd/mtU to 3631 MWd/mtU, use 3.15%.
For all other burnups, use 2.0%
For all other burnups, use 2.0%
2.5.8 TS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta-T Trip setpoints (value of K
2.5.8 TS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta-T Trip setpoints (value of K
: 4) at least 1% (in T span) for each 1% that FQC(X,Y,Z) exceeds its limit.  
: 4) at least 1% (in T span) for each 1% that F Q C(X,Y,Z) exceeds its limit.  


2.6 Nuclear Enthalpy Rise Hot Channel Factor - FH(X,Y) (TS 3.2.2) 2.6.1 MAP(X,Y,Z) is provided in Table 2.
2.6 Nuclear Enthalpy Rise Hot Channel Factor - FH(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 when P  0.8  Where RRH = Thermal power reduction required to compensate for each 1% that FH(X,Y) exceeds its limit. P = THERMAL POWER / RATED THERMAL POWER 2.6.3 TRH = 0.0334 when 0.8 < P  1.0 TRH = 0.0167 when P  0.8 Where TRH = Reduction in Overtemperature Delta-T K 1 setpoint required to compensate for each 1% that FH(X,Y) exceeds its limit. P = THERMAL POWER / RATED THERMAL POWER COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 7 of 16 Revision 0 2.6.4 The appropriate factor for increase in FHM (X,Y) for compliance with SR 3.2.2.1 and SR 3.2.2.2 is specified as follows:
2.6.2 RRH = 3.34 when 0.8 < P  1.0 RRH = 1.67 when P  0.8  Where RRH = Thermal power reduction required to compensate for each 1% that FH(X,Y) exceeds its limit. P = THERMAL POWER / RATED THERMAL POWER 2.6.3 TRH = 0.0334 when 0.8 < P  1.0 TRH = 0.0167 when P  0.8 Where TRH = Reduction in Overtemperature Delta-T K 1 setpoint required to compensate for each 1% that FH (X,Y) exceeds its limit. P = THERMAL POWER / RATED THERMAL POWER COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 7 of 16 Revision 0 2.6.4 The appropriate factor for increase in FH M (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%
For all cycle burnups, use 2.0%
2.6.5 TS LCO 3.2.2 Required Action A.
2.6.5 TS LCO 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 FH minimum margin.
4 reduces the Overtemperature Delta-T setpoint (K 1 term in Table 3.3.1-1) by  TRH multiplied by the FH minimum margin.
2.6.6 TS LCO 3.2.2 Required Action B.
2.6.6 TS LCO 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 f1(I) minimum margin.  
1 reduces the Overtemperature Delta-T setpoint (K 1 term in Table 3.3.1-1) by  TRH multiplied by the f 1 (I) minimum margin.  


2.7 Axial Flux Difference - AFD (TS 3.2.3) 2.7.1 The AFD limits are specified in Figure 3  
2.7 Axial Flux Difference - AFD (TS 3.2.3) 2.7.1 The AFD limits are specified in Figure 3  


COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 8 of 16 Revision 0 2.8 Reactor Trip System Instrumentation (TS 3.3.1) 2.8.1 Trip Reset Term [f 1(I)] for Overtemperature Delta-T Trip The following parameters are required to specify the power level-dependent f1(I) trip reset term limits for Tabl e 3.3.1-1 (function 6), Overtemperature Delta-T trip function:
COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 8 of 16 Revision 0 2.8 Reactor Trip System Instrumentation (TS 3.3.1) 2.8.1 Trip Reset Term [f 1 (I)] for Overtemperature Delta-T Trip The following parameters are required to specify the power level-dependent f 1 (I) trip reset term limits for Tabl e 3.3.1-1 (function 6), Overtemperature Delta-T trip function:
2.8.1.1 QTNL = -20%  
2.8.1.1 QTNL = -20%  


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where QTPS = the percent reducti on in Overtemperature Delta-T trip setpoint for each per cent that the magnitude of I exceeds its positive limit at RATED THERMAL POWER (QTPL).  
where QTPS = the percent reducti on in Overtemperature Delta-T trip setpoint for each per cent that the magnitude of I exceeds its positive limit at RATED THERMAL POWER (QTPL).  


COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 9 of 16 Revision 0 2.8.2 Trip Reset Term [f 2(I)] for Overpower Delta-T Trip The following parameters are required to specify the power level-dependent f2(I) trip reset term limits for Table 3.3.1-1 (function 7), Overpower Delta-T trip function:
COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 9 of 16 Revision 0 2.8.2 Trip Reset Term [f 2 (I)] for Overpower Delta-T Trip The following parameters are required to specify the power level-dependent f 2 (I) trip reset term limits for Table 3.3.1-1 (function 7), Overpower Delta-T trip function:
2.8.2.1 QPNL = -25%
2.8.2.1 QPNL = -25%
where QPNL = the maximum negative I setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.
where QPNL = the maximum negative I setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.
Line 109: Line 100:
  (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 3.1.1-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 3.1.3-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(I), f2(I) 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), Revision 0 "PWR Small Break LOCA Evaluation Model," March 2001.  
  (Methodology for TS 3.3.1-Reactor Trip System Instrumentation [f 1 (I), f 2 (I) 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), Revision 0 "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-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-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) 6. BAW-10186P-A, Revision 2, "Extended Burnup Evaluation," June 2003.  
Line 115: Line 106:
  (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) 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-10241P-A, Revision 1, "BHTP DNB Correlation Applied with LYNXT," July 2005.  
  (Methodology for TS 3.2.1-Heat Flux Hot Channel Factor) 8. BAW-10241P-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(I) 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 (I) 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  
  (Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor  


Trip System Instrumentation [f 1(I) limits]) 10. BAW-10189P-A, "CHF Testing and Analysis of the Mark-BW Fuel Assembly Design,"
Trip System Instrumentation [f 1 (I) limits]) 10. BAW-10189P-A, "CHF Testing and Analysis of the Mark-BW Fuel Assembly Design,"
January 1996.  
January 1996.  
  (Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor  
  (Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor  


Trip System Instrumentation [f 1(I) limits]) 11. BAW-10159P-A, "BWCMV Correlation of Critical Heat Flux in Mixing Vane Grid Fuel Assemblies," August 1990.  
Trip System Instrumentation [f 1 (I) limits]) 11. BAW-10159P-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  
  (Methodology for TS 3.2.2-Nuclear Enthalpy Rise Hot Channel Factor, 3.3.1-Reactor  


Trip System Instrumentation [f 1(I) 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(I) limits])  
Trip System Instrumentation [f 1 (I) 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 (I) limits])  


COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 11 of 16 Revision 0 Table 2 Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z)  AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 1.1 1 2 3
COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 11 of 16 Revision 0 Table 2 Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z)  AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 1.1 1 2 3
Line 173: Line 164:
COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 13 of 16 Revision 0 Table 2 (continued) AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 2.5 1 2 3
COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 13 of 16 Revision 0 Table 2 (continued) AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 2.5 1 2 3
4 5
4 5
6 7 8 9 10 11 2.8372 2.7099 2.7081 2.6340 2.6483 2.6284 3.0303 2.8965 2.8111 2.7019 2.3542 SEQUORod
6 7 8 9 10 11 2.8372 2.7099 2.7081 2.6340 2.6483 2.6284 3.0303 2.8965 2.8111 2.7019 2.3542 SEQU O Rod
* F atFuCy This figure If the LEF Mreduced b yreturned t oOYAH UNIT Bank Ins eFully withdra wt a position w i ully withdraw n ycle Burnup (
* F a t F u C y This figure If the LEF Mreduced b y returned t o OYAH UNIT Bank Ins e F ully withdra w t a position w i u lly withdraw n ycle Burnup (M 0 is valid for op e M becomes in o y 1.3% in pow e o operation.
M 0 is valid for op eM becomes in oy 1.3% in pow eo operation.
COL 1 Fract i e rtion Lim i wn region sha i thin the inter v n shall be the MWd/mtU)  eration at a R A operable, then p er, and the rod R FOR SEQ U Page 1 i on of R AT Fts Versusll be the con d v al of 225 a nposition as d e ATED THERM A prior to the ne xinsertion limit l UOYAH UNI T 1 4 of 16 TED THER M IGURE 1 THERMA L dition where s n d 231step s efined below, Ste p     2 AL POWER of 3 xt NIS calibrati oines must be i n T 1 CYCLE 2 2 M AL POW E L POWER, shutdown an d s withdrawn.
COL1 Fractiertion Lim iwn region sha ithin the inter vn shall be the MWd/mtU)  eration at a R Aoperable, then per, and the rod R FOR SEQ UPage 1ion of RATFts Versusll be the con dval of 225 anposition as d eATED THERM Aprior to the ne xinsertion limit l UOYAH UNIT14 of 16TED THERM IGURE 1 THERMAL dition where snd 231stepsefined below, Step     2AL POWER of 3xt NIS calibrati oines must be i nT 1 CYCLE 2 2MAL POWEL POWER, shutdown an ds withdrawn.
, ps Withdrawn 2 25 to  231 3455 MWth w h o n, the maxim u ncreased by 3 2 R e E R Four Loo p d control ban k hen the LEFM i um allowable psteps withdra wevision 0 p Operatio n ks are is in operation.ower level mu s wn until the LE F n s t be F M is COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 15 of 16 Revision 0 FIGURE 2 K(Z) - Normalized F Q (X,Y,Z) as a Function of Core Height 0.00.20.4 0.60.81.01.202468101 2Core Height (Feet)K(Z)Elevation        K(z)      (ft)        0.000          1.0000      6.285          1.0000    7.995          1.0000    9.705          1.0000  12.000          1.0000 SEQU O This figure If the LEF Mreduced b y returned t o  OYAH UNIT is valid for op e M becomes in o y 1.3% in pow e o operation.
, ps Withdrawn 225 to  2313455 MWth w hon, the maxim uncreased by 3 2 ReER Four Loop d control ban khen the LEFM ium allowable psteps withdra wevision 0 p Operatio nks are is in operation.ower level mu swn until the LE Fn st be FM is COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 15 of 16 Revision 0 FIGURE 2 K(Z) - Normalized F Q(X,Y,Z) as a Function of Core Height 0.00.20.4 0.60.81.01.2024681012Core Height (Feet)K(Z)Elevation        K(z)      (ft)        0.000          1.0000      6.285          1.0000    7.995          1.0000    9.705          1.0000  12.000          1.0000 SEQUO This figure If the LEF Mreduced b yreturned t o  OYAH UNIT is valid for op eM becomes in oy 1.3% in pow eo operation.
COL 1 AXIA L Funct For eration at a R A operable, then p er, and the AF DR FOR SEQ U Page 1 F L FLUX DI F ion of R AT Burnup R ATED THERM A prior to the ne x D limit lines mu UOYAH UNI T 1 6 of 16 IGURE 3  F FERENC E TED THER M R ange 0 EF   AL POWER of 3 xt NIS calibrati ost be made m o T 1 CYCLE 2 2 E Limits A s M AL POW PD to EO L 3455 MWth w h o n, the maxim u ore restrictive b 2 R e s A ER L hen the LEFM i um allowable p by 1% in AFD uevision 0 is in operation.ower level mu s until the LEFM s t be is}}
COL1 AXIALFunctFor eration at a R Aoperable, then per, and the AF DR FOR SEQ UPage 1FL FLUX DIFion of RATBurnup RATED THERM Aprior to the ne xD limit lines mu UOYAH UNIT16 of 16 IGURE 3  FFERENCETED THERMRange 0 EF AL POWER of 3xt NIS calibrati ost be made m oT 1 CYCLE 2 2E Limits A sMAL POWPD to EOL3455 MWth w hon, the maxim uore restrictive b2 Res A ER L hen the LEFM ium allowable p by 1% in AFD uevision 0 is in operation.ower level mu suntil the LEFM st be is}}

Revision as of 02:07, 8 July 2018

Sequoyah, Unit 1 - Cycle 22 Core Operating Limits Report, Revision 0
ML16357A556
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 12/21/2016
From: Boerschig G A
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML16357A556 (18)
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Tennessee Valley Authority , P ost O ff ice B ox 2000, So d dy Da i sy , T e nn essee 37384-2000 December 21, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-77 NRC Docket No. 50-327 10 CFR 50.4

Subject:

SEQUOYAH UNIT 1 CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 In accordance with Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specification (TS) 5.6.3.d, enclosed is the Unit 1 Cycle 22 Core Operating Limits Report (COLR), Revision 0 that was issued on December 7, 2016. SQN has completed the transition from the Mark-BW fuel design to the Advanced W17 HTP fuel design in Unit 1. Accordingly, the COLR only includes core operating limits associated with the use of Advanced W17 HTP fuel. There are no new regulatory commitments in this letter. If you have any questions, please contact Michael McBrearty , SQN Site Licensing Manager at (423) 843-7170.

Respectfully , Gregory A. Boerschig Site Vice President (interim)

Sequoyah Nuclear Plant Enclosure Sequoyah Unit 1 Cycle 22 Core Operating Limits Report cc (Enclosure):

NRC Regional Administrator-Region II NRC Senior Resident Inspector-SQN ENCLOSURE SEQUOYAH UNIT 1 CYCLE 22 CORE OPERA TING LIMITS REPORT QA Record Prepared by: SEQUOYAH UNIT 1 CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 December 2016 Verified by: L36 161201 800 I 2 / o l / 2-o Date / 1zto\/L.o\(o fvt:JR. Fuel Engineering

_

I 1z-2-2-01(p Date Manager /2 ;, h<. . Date Approved by:

Date I Pl Date Date of PORC Affected Revision Approval Pages Reason for Revision 0 17 1-:i-/1111 All Initial issue. SEQUOYAH-UNIT 1 Page 1 of 16 Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 2 of 16 Revision 0 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 1 Cycle 22 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 Section Technical Specification COLR Parameter COLR SectionCOLR Page3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.1 3 3.1.3 Moderator Temperature Coefficient (MTC) BOL MTC Limit EOL MTC Limit 300 ppm Surveillance Limit 60 ppm Surveillance Limit 2.2.1 2.2.2 2.2.3 2.2.4 4 4 4 4 3.1.4 Rod Group Alignment Limits SDM 2.1.3 3 3.1.5 Shutdown Bank Insertion LimitsShutdown Bank Insertion Limits SDM 2.3 4 2.1.4 3 3.1.6 Control Bank Insertion Limits Control Bank Insertion Limits 2.4 5 SDM 2.1.5 3 3.1.8 PHYSICS TESTS Exceptions -

MODE 2 SDM 2.1.6 3 3.2.1 Heat Flux Hot Channel Factor (F Q(X,Y,Z)) F Q RTP 2.5.1 6 K(Z) 2.5.2 6 NSLOPE AFD2.5.3 6 PSLOPE AFD 2.5.4 6 NSLOPE f2(I) 2.5.5 6 PSLOPE f2(I) 2.5.6 6 F Q(X,Y,Z) Appropriate Factor 2.5.7 6 TS LCO 3.2.1 Required Action A.3 2.5.8 6 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FH(X,Y)) MAP(X,Y,Z) 2.6.1 6 RRH 2.6.2 6 TRH 2.6.3 6 FH(X,Y) Appropriate Factor 2.6.4 7 TS 3.2.2 Required Action A.4 2.6.5 7 TS 3.2.2 Required Action B.1 2.6.6 7 3.2.3 AXIAL FLUX DIFFERENCE (AFD) AFD Limits 2.7 7 3.3.1 Reactor Trip System (RTS) QTNL, QTPL, QTNS, and QTPS QPNL, QPPL, QPNS, and QPPS 2.8.1 8 Instrumentation 2.8.2 9 3.9.1 Boron Concentration Refueling Boron Concentration 2.9 9 5.6.3 CORE OPERATING LIMITS REPORT (COLR)

Analytical Methods Table 110 COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 3 of 16 Revision 0 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 be en developed using the NRC approved methodologies specified in TS 5.6.3.

T he 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 R2.1 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 %k/k in MODE 2 with k eff < 1.0, MODE 3 and MODE 4 2.1.2 For TS 3.1.1, SDM shall be 1.0 %k/k in MODE 5.

2.1.3 For TS 3.1.4, SDM shall be 1.6 %k/k in MODE 1 and MODE 2.

2.1.4 For TS 3.1.5, SDM shall be 1.6 %k/k in MODE 1 and MODE 2.

2.1.5 For TS 3.1.6, SDM shall be 1.6 %k/k in MODE 1 and MODE 2 with k eff 1.0. 2.1.6 For TS 3.1.8, SDM shall be 1.6 %k/k in MODE 2.

COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 4 of 16 Revision 0 2.2 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.2.1 The BOL MTC limit is: less positive than -0.11 x 10

-5 k/k/ºF. 2.2.2 The EOL MTC limit is: less negative than or equal to -4.50 x 10

-4 k/k/ºF. 2.2.3 The 300 ppm Surveillance limit is: less negative than or equal to -3.75 x 10

-4 k/k/ºF. 2.2.4 The 60 ppm Surveillance limit is: less negative than or equal to -4.15 x 10

-4 k/k/ºF.

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:

Cycle Burnup (MWd/mtU)

Steps Withdrawn 0 225 to 231 COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 5 of 16 Revision 0 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

COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 6 of 16 Revision 0 2.5 Heat Flux Hot Channel Factor - F Q(X,Y,Z) (TS 3.2.1) 2.5.1 F QRTP = 2.62 2.5.2 K(Z) is provided in Figure 2 2.5.3 NSLOPE AFD = 1.17 2.5.4 PSLOPE AFD = 1.54 2.5.5 NSLOPE f2(I) = 1.48 2.5.6 PSLOPE f2(I) = 2.27 2.5.7 The appropriate factor for increase in F Q M(X,Y,Z) for compliance with SR 3.2.1.2 and SR 3.2.1.3 is specified as follows:

For cycle burnups >1302 MWd/mtU to 3631 MWd/mtU, use 3.15%.

For all other burnups, use 2.0%

2.5.8 TS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta-T Trip setpoints (value of K

4) at least 1% (in T span) for each 1% that F Q C(X,Y,Z) exceeds its limit.

2.6 Nuclear Enthalpy Rise Hot Channel Factor - FH(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 when P 0.8 Where RRH = Thermal power reduction required to compensate for each 1% that FH(X,Y) exceeds its limit. P = THERMAL POWER / RATED THERMAL POWER 2.6.3 TRH = 0.0334 when 0.8 < P 1.0 TRH = 0.0167 when P 0.8 Where TRH = Reduction in Overtemperature Delta-T K 1 setpoint required to compensate for each 1% that FH (X,Y) exceeds its limit. P = THERMAL POWER / RATED THERMAL POWER COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 7 of 16 Revision 0 2.6.4 The appropriate factor for increase in FH M (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 TS LCO 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 FH minimum margin.

2.6.6 TS LCO 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 (I) minimum margin.

2.7 Axial Flux Difference - AFD (TS 3.2.3) 2.7.1 The AFD limits are specified in Figure 3

COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 8 of 16 Revision 0 2.8 Reactor Trip System Instrumentation (TS 3.3.1) 2.8.1 Trip Reset Term [f 1 (I)] for Overtemperature Delta-T Trip The following parameters are required to specify the power level-dependent f 1 (I) trip reset term limits for Tabl e 3.3.1-1 (function 6), Overtemperature Delta-T trip function:

2.8.1.1 QTNL = -20%

where QTNL = the maximum negative I 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 I 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 reducti on in Overtemperature Delta-T trip setpoint for each per cent that the magnitude of I exceeds its negative limit at RATED THERMAL POWER (QTNL).

2.8.1.4 QTPS = 1.40%

where QTPS = the percent reducti on in Overtemperature Delta-T trip setpoint for each per cent that the magnitude of I exceeds its positive limit at RATED THERMAL POWER (QTPL).

COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 9 of 16 Revision 0 2.8.2 Trip Reset Term [f 2 (I)] for Overpower Delta-T Trip The following parameters are required to specify the power level-dependent f 2 (I) 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 I 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 I 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 eac h percent that the magnitude of I 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 eac h percent that the

magnitude of I 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.

COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 10 of 16 Revision 0 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 (I), f 2 (I) 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), Revision 0 "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-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-10241P-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 (I) 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 (I) 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 (I) limits]) 11. BAW-10159P-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 (I) 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 (I) limits])

COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 11 of 16 Revision 0 Table 2 Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 1.1 1 2 3

4 5

6 7 8 9 10 11 1.8764 1.8761 1.8758 1.8755 1.8750 1.8746 1.8732 1.8731 1.8729 1.8733 1.8320 1.4 1 2

3 4

5 6 7 8 9 10 11 2.7078 2.6846 2.6349 2.5983 2.5933 2.6505 2.6394 2.5563 2.4572 2.2668 2.1190 1.2 1 2

3 4

5 6

7 8

9 10 11 2.1327 2.1321 2.1315 2.1306 2.1295 2.1290 2.1286 2.1274 2.1254 2.0247 1.9355 1.5 1 2

3 4

5 6

7 8

9 10 11 2.8223 2.7591 2.6985 2.6542 2.6482 2.7162 2.7495 2.6507 2.5578 2.3791 2.2011 1.3 1 2

3 4

5 6

7 8

9 10 11 2.4093 2.4077 2.4068 2.4063 2.4050 2.4043 2.4034 2.3923 2.3053 2.1479 2.0305 1.6 1 2

3 4

5 6

7 8

9 10 11 2.8935 2.8252 2.7571 2.7055 2.6985 2.7776 2.8428 2.7401 2.6471 2.4862 2.2766 COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 12 of 16 Revision 0 Table 2 (continued) AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 1.7 1 2 3

4 5

6 7 8 9 10 11 2.9545 2.8786 2.8103 2.7522 2.7457 2.8308 2.9230 2.8209 2.7287 2.5873 2.3478 >1.9 1 2

3 4

5 6

7 8 9 10 11 2.6005 2.5794 2.5536 2.5118 2.4500 2.4520 2.6494 2.5446 2.4371 2.2595 2.0819 1.8 1 2

3 4

5 6

7 8

9 10 11 2.9942 2.9271 2.8570 2.7942 2.7875 2.8823 2.9967 2.8980 2.8027 2.6853 2.4156 2.1 1 2

3 4

5 6

7 8

9 10 11 2.7049 2.6623 2.6375 2.5288 2.5460 2.5252 2.7990 2.6963 2.5830 2.4527 2.1796 1.9 1 2

3 4

5 6

7 8

9 10 11 3.0267 2.9676 2.8960 2.8345 2.8256 2.9291 3.0655 2.9714 2.8741 2.7780 2.4797 2.3 1 2

3 4

5 6

7 8

9 10 11 2.7475 2.7275 2.6457 2.6125 2.5774 2.5707 2.9015 2.7773 2.6757 2.4740 2.2722

COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 13 of 16 Revision 0 Table 2 (continued) AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 2.5 1 2 3

4 5

6 7 8 9 10 11 2.8372 2.7099 2.7081 2.6340 2.6483 2.6284 3.0303 2.8965 2.8111 2.7019 2.3542 SEQU O Rod

  • F a t F u C y This figure If the LEF Mreduced b y returned t o OYAH UNIT Bank Ins e F ully withdra w t a position w i u lly withdraw n ycle Burnup (M 0 is valid for op e M becomes in o y 1.3% in pow e o operation.

COL 1 Fract i e rtion Lim i wn region sha i thin the inter v n shall be the MWd/mtU) eration at a R A operable, then p er, and the rod R FOR SEQ U Page 1 i on of R AT Fts Versusll be the con d v al of 225 a nposition as d e ATED THERM A prior to the ne xinsertion limit l UOYAH UNI T 1 4 of 16 TED THER M IGURE 1 THERMA L dition where s n d 231step s efined below, Ste p 2 AL POWER of 3 xt NIS calibrati oines must be i n T 1 CYCLE 2 2 M AL POW E L POWER, shutdown an d s withdrawn.

, ps Withdrawn 2 25 to 231 3455 MWth w h o n, the maxim u ncreased by 3 2 R e E R Four Loo p d control ban k hen the LEFM i um allowable psteps withdra wevision 0 p Operatio n ks are is in operation.ower level mu s wn until the LE F n s t be F M is COLR FOR SEQUOYAH UNIT 1 CYCLE 22 SEQUOYAH UNIT 1 Page 15 of 16 Revision 0 FIGURE 2 K(Z) - Normalized F Q (X,Y,Z) as a Function of Core Height 0.00.20.4 0.60.81.01.202468101 2Core Height (Feet)K(Z)Elevation K(z) (ft) 0.000 1.0000 6.285 1.0000 7.995 1.0000 9.705 1.0000 12.000 1.0000 SEQU O This figure If the LEF Mreduced b y returned t o OYAH UNIT is valid for op e M becomes in o y 1.3% in pow e o operation.

COL 1 AXIA L Funct For eration at a R A operable, then p er, and the AF DR FOR SEQ U Page 1 F L FLUX DI F ion of R AT Burnup R ATED THERM A prior to the ne x D limit lines mu UOYAH UNI T 1 6 of 16 IGURE 3 F FERENC E TED THER M R ange 0 EF AL POWER of 3 xt NIS calibrati ost be made m o T 1 CYCLE 2 2 E Limits A s M AL POW PD to EO L 3455 MWth w h o n, the maxim u ore restrictive b 2 R e s A ER L hen the LEFM i um allowable p by 1% in AFD uevision 0 is in operation.ower level mu s until the LEFM s t be is

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