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3.1.1 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 -
3.1.1 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  
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 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)
 
(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 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 SEQUOYAH UNIT 2 Page 3 of 16 Revision 0 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. T he versions of the topical reports, which describe the methodologies used for this cycle are listed in Table 1.
Analytical Methods Table 110 SEQUOYAH UNIT 2 Page 3 of 16 Revision 0 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. 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:
The following abbreviations are used in this section:
Line 52: Line 49:
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  


SEQUOYAH UNIT 2 Page 6 of 16 Revision 0 Q F =  2.62 K(Z) is provided in Figure 2 NSLOPEAFD =  1.3 PSLOPEAFD =  1.6 NSLOPEf2(I) =  1.6 PSLOPEf2(I) =  2.3 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:
SEQUOYAH UNIT 2 Page 6 of 16 Revision 0 Q F =  2.62 K(Z) is provided in Figure 2 NSLOPE AFD =  1.3 PSLOPE AFD =  1.6 NSLOPE f2(I) =  1.6 PSLOPE f2(I) =  2.3 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 >2921 MWd/mtU to 4223 MWd/mtU, use 2.61%.
For cycle burnups >2921 MWd/mtU to 4223 MWd/mtU, use 2.61%.
For all other burnups, use 2.0%
For all other burnups, use 2.0%
TS LCO 3.2.1 Required Action A.3 reduces the Overpower Delta-T Trip setpoints (value of K
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.
MAP(X,Y,Z) is provided in Table 2. RRH = 3.34 when 0.8 < P  1.0RRH = 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 TRH = 0.0334 when 0.8 < P  1.0 TRH = 0.0167 when P  0.8 Where TRH = Reduction in Ov ertemperature Delta-T K 1 setpoint required to compensate for each 1% that FH(X,Y) exceeds its limit. P = THERMAL POWER / RATED THERMAL POWER SEQUOYAH UNIT 2 Page 7 of 16 Revision 0 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:
MAP(X,Y,Z) is provided in Table 2. RRH = 3.34 when 0.8 < P  1.0RRH = 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 TRH = 0.0334 when 0.8 < P  1.0 TRH = 0.0167 when P  0.8 Where TRH = Reduction in Ov ertemperature Delta-T K 1 setpoint required to compensate for each 1% that FH (X,Y) exceeds its limit. P = THERMAL POWER / RATED THERMAL POWER SEQUOYAH UNIT 2 Page 7 of 16 Revision 0 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%
TS LCO 3.2.2 Required Action A.
TS LCO 3.2.2 Required Action A.
4 reduces the Ov ertemperature Delta-T setpoint (K 1 term in Table 3.3.1-1) by  TRH multiplied by the FH minimum margin. TS LCO 3.2.2 Required Action B.
4 reduces the Ov ertemperature Delta-T setpoint (K 1 term in Table 3.3.1-1) by  TRH multiplied by the FH minimum margin. TS LCO 3.2.2 Required Action B.
1 reduces the Ov ertemperature Delta-T setpoint (K 1 term in Table 3.3.1-1) by  TRH multiplied by the f1(I) minimum margin.  
1 reduces the Ov ertemperature Delta-T setpoint (K 1 term in Table 3.3.1-1) by  TRH multiplied by the f 1 (I) minimum margin.  


The AFD limits are specified in Figure 3.  
The AFD limits are specified in Figure 3.  


SEQUOYAH UNIT 2 Page 8 of 16 Revision 0 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 Table 3.3.1-1 (function 6), Overtemperature Delta-T trip function: QTNL = -20%
SEQUOYAH UNIT 2 Page 8 of 16 Revision 0 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 Table 3.3.1-1 (function 6), Overtemperature Delta-T trip function: 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. QTPL = +5%
where QTNL = the maximum negative I setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution. 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.
where QTPL = the maximum positive I setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.
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where QTPS = the percent reducti on in Overtemperature Delta-T trip setpoint for each pe rcent 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 pe rcent that the magnitude of I exceeds its positive limit at RATED THERMAL POWER (QTPL).  


SEQUOYAH UNIT 2 Page 9 of 16 Revision 0 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: QPNL = -25%
SEQUOYAH UNIT 2 Page 9 of 16 Revision 0 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: 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. QPPL = +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. 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.
where QPPL = the maximum positive I setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.
Line 90: Line 87:
  (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 96: Line 93:
  (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])  


SEQUOYAH UNIT 2 Page 11 of 16 Revision 0 AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z)  AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 1.03 1 2 3
SEQUOYAH UNIT 2 Page 11 of 16 Revision 0 AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z)  AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 1.03 1 2 3
Line 163: Line 160:
* Fully withdrawn region shall be the condition where shutdown and control banks are  at a position within the interval of 225 and 231steps withdrawn.
* Fully withdrawn region shall be the condition where shutdown and control banks are  at a position within the interval of 225 and 231steps withdrawn.
Fully withdrawn shall be the position as defined below, Cycle Burnup (MWd/mtU)  Steps Withdrawn  0        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.
Fully withdrawn shall be the position as defined below, Cycle Burnup (MWd/mtU)  Steps Withdrawn  0        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 2 Page 15 of 16 Revision 0 0.00.20.4 0.60.81.01.2024681012 SEQUOYAH UNIT 2 Page 16 of 16 Revision 0 This figure is valid for operation at a RATED THERMAL POWER of 3455 MWth when the LEFM is in operation.
SEQUOYAH UNIT 2 Page 15 of 16 Revision 0 0.00.20.4 0.60.81.01.202468101 2 SEQUOYAH UNIT 2 Page 16 of 16 Revision 0 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.}}
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.}}

Revision as of 21:10, 7 July 2018

Sequoyah, Unit 2 - Cycle 22 Core Operating Limits Report, Revision 0
ML17152A272
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 06/01/2017
From: Williams A L
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L36 170508 801, Rev. 0
Download: ML17152A272 (18)
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Text

SEQUOYAH UNIT 2 Page 2 of 16 Revision 0 This CORE OPERATING LIMITS REPORT (COLR) for Sequoyah Unit 2 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:

3.1.1 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 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 SEQUOYAH UNIT 2 Page 3 of 16 Revision 0 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. 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 RATED THERMAL POWER

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.

For TS 3.1.1, SDM shall be 1.0 %k/k in MODE 5.

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

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

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

For TS 3.1.8, SDM shall be 1.6 %k/k in MODE 2.

SEQUOYAH UNIT 2 Page 4 of 16 Revision 0 The BOL MTC limit is: less positive than -0.16 x 10

-5 k/k/ºF.

The EOL MTC limit is: less negative than or equal to -4.50 x 10

-4 k/k/ºF. The 300 ppm Surveillance limit is: less negative than or equal to -3.80 x 10

-4 k/k/ºF. The 60 ppm Surveillance limit is: less negative than or equal to -4.20 x 10

-4 k/k/ºF.

Each shutdown bank shall be withdrawn to a position as defined below:

Cycle Burnup (MWd/mtU)

Steps Withdrawn 0 225 to 231 SEQUOYAH UNIT 2 Page 5 of 16 Revision 0 The control banks shall be limited in physical insertion as shown in Figure 1.

Each control bank shall be consider ed fully withdrawn from the core at 225 steps. 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.

Each control bank not fully withdraw n 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 2 Page 6 of 16 Revision 0 Q F = 2.62 K(Z) is provided in Figure 2 NSLOPE AFD = 1.3 PSLOPE AFD = 1.6 NSLOPE f2(I) = 1.6 PSLOPE f2(I) = 2.3 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 >2921 MWd/mtU to 4223 MWd/mtU, use 2.61%.

For all other burnups, use 2.0%

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.

MAP(X,Y,Z) is provided in Table 2. RRH = 3.34 when 0.8 < P 1.0RRH = 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 TRH = 0.0334 when 0.8 < P 1.0 TRH = 0.0167 when P 0.8 Where TRH = Reduction in Ov ertemperature Delta-T K 1 setpoint required to compensate for each 1% that FH (X,Y) exceeds its limit. P = THERMAL POWER / RATED THERMAL POWER SEQUOYAH UNIT 2 Page 7 of 16 Revision 0 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%

TS LCO 3.2.2 Required Action A.

4 reduces the Ov ertemperature Delta-T setpoint (K 1 term in Table 3.3.1-1) by TRH multiplied by the FH minimum margin. TS LCO 3.2.2 Required Action B.

1 reduces the Ov ertemperature Delta-T setpoint (K 1 term in Table 3.3.1-1) by TRH multiplied by the f 1 (I) minimum margin.

The AFD limits are specified in Figure 3.

SEQUOYAH UNIT 2 Page 8 of 16 Revision 0 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 Table 3.3.1-1 (function 6), Overtemperature Delta-T trip function: 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. 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.

QTNS = 2.50%

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

QTPS = 1.40%

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

SEQUOYAH UNIT 2 Page 9 of 16 Revision 0 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: 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. 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.

QPNS = 1.70%

where QPNS = the percent r eduction in Overpower Delta-T trip setpoint for each percent that the magnitude of I exceeds its negative limit at RATED THERMAL POWER (QPNL).

QPPS = 1.70%

where QPPS = the percent reduction in Overpower Delta-T trip setpoint for each percent that the

magnitude of I exceeds its positive limit at RATED THERMAL POWER (QPPL).

The refueling boron concentration shall be 2026 ppm.

SEQUOYAH UNIT 2 Page 10 of 16 Revision 0 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])

SEQUOYAH UNIT 2 Page 11 of 16 Revision 0 AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 1.03 1 2 3

4 5 6 7 8

9 10 11 1.7084 1.7084 1.7083 1.7082 1.7081 1.7079 1.7078 1.7073 1.7072 1.7072 1.7066 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 1.1 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

SEQUOYAH UNIT 2 Page 12 of 16 Revision 0 AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 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 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 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

SEQUOYAH UNIT 2 Page 13 of 16 Revision 0 AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) AXIAL(X,Y) Elevation (ft) MAP(X,Y,Z) 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 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

SEQUOYAH UNIT 2 Page 14 of 16 Revision 0

  • Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of 225 and 231steps withdrawn.

Fully withdrawn shall be the position as defined below, Cycle Burnup (MWd/mtU) Steps Withdrawn 0 225 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 2 Page 15 of 16 Revision 0 0.00.20.4 0.60.81.01.202468101 2 SEQUOYAH UNIT 2 Page 16 of 16 Revision 0 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.

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