ML24109A027

Cycle 27 Core Operating Limits Report Revision 0

ML24109A027
Person / Time
Site:	Sequoyah
Issue date:	04/16/2024
From:	Marshall T Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML24109A027 (1)

Text

Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384

April 16, 2024 10 CFR 50.4

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

Subject:

SEQUOYAH UNIT 1 CYCLE 27 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 27 Core Operating Limits Report (COLR), Revision 0 that was issued on April 02, 2024.

There are no new regulatory commitments in this letter. If you have any questions, please contact Rick Medina, SQN Site Licensing Manager at (423) 843-8129 or rmedina4@tva.gov.

Respectfully, Marshall, Digitally signed by Marshall, Thomas B.

Thomas B. Date: 2024.04.16 10:55:57

-04'00' Thomas Marshall Site Vice President Sequoyah Nuclear Plant

Enclosure:

Sequoyah Unit 1 Cycle 27 Core Operating Limits Report, Revision 0

cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - SQN ENCLOSURE

SEQUOYAH UNIT 1 CYCLE 27 CORE OPERATING LIMITS REPORT REVISION 0

COLR FOR SEQUOYAH UNIT 1 CYCLE 27

1.0 CORE OPERATING LIMITS REPORT

This Core Operating Limits Report (COLR) for Sequoyah Nuclear Plant Unit 1 has been prepared in accordance with the requirements of the Technical Specifications (TS) 5.6.3.

The Technical Specifications affected by this report are listed below:

TS COLR COLR Section Technical Specification COLR Parameter Section Page 2.1.1 Reactor Core Safety Limits Reactor Core Safety Limits 2.1 3 3.1.1 SHUTDOWN MARGIN (SDM) SDM 2.2.1 3 2.2.2 3 BOL MTC Limit 2.3.1 4 3.1.3 Moderator Temperature Coefficient EOL MTC Limit 2.3.1 4 (MTC) 300 ppm Surveillance Limit 2.3.2 4 60 ppm Surveillance Limit 2.3.3 4 3.1.4 Rod Group Alignment Limits SDM 2.2.3 3 3.1.5 Shutdown Bank Insertion Limits Shutdown Bank Insertion Limits 2.4 4 SDM 2.2.4 3 3.1.6 Control Bank Insertion Limits Control Bank Insertion Limits 2.5 4 SDM 2.2.5 3 3.1.8 PHYSICS TESTS Exceptions - MODE 2 SDM 2.2.6 3 FQRTP 2.6.1 5 K(Z) 2.6.2 5 FQW(Z) 2.6.3 5 3.2.1 Heat Flux Hot Channel Factor [T(Z)]COLR 2.6.4 5 (FQ(Z)) Axy(Z) Factor 2.6.5 Rj Penalty Factor 2.6.6 Thermal Power Limits 2.6.7 6 UFQ 2.6.8 6 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F HN) F HN 2.7 6 3.2.3 Axial Flux Difference (AFD) AFD Limits 2.8 6 Overtemperature ¨T Trip Setpoints 2.9.1 7 3.3.1 Reactor Trip System (RTS) Overpower ¨ T Trip Setpoints 2.9.2 7 Instrumentation QTNL, QTPL, QTNS, and QTPS 2.9.3 7 QPNL, QPPL, QPNS, and QPPS 2.9.4 8 RCS Pressure, Temperature, and Pressurizer pressure 3.4.1 Flow Departure from Nucleate RCS average temperature 2.10 8 Boiling (DNB) Limits RCS flow 3.9.1 Boron Concentration Refueling Boron Concentration 2.11 8 5.6.3 CORE OPERATING LIMITS REPORT (COLR) Analytical Methods Table 1 13

Unit 1 Cycle 27 SEQUOYAH Page 2 of 19 Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 27

2.0 OPERATING LIMITS

The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in the Technical Specifications 5.6.3.

The following abbreviations are used in this section:

BOL -- Beginning of Cycle Life ARO -- All Rods Out HZP -- Hot Zero Thermal Power EOL -- End of Cycle Life RTP -- Rated Thermal Power RCS -- Reactor Coolant System RAOC -- Relaxed Axial Offset Control ROS -- RAOC Operating Space SFCP -- Surveillance Frequency Control Program

2.1 REACTOR CORE SAFETY LIMITS (Safety Limit 2.1.1)

In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits in Figure 1.

2.2 SHUTDOWN MARGIN (LCO 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8)

2.2.1 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.

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

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

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

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

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

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2.3 MODERATOR TEMPERATURE COEFFICIENT - MTC (LCO 3.1.3)

2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The ARO/HZP - MTC shall be less positive than 0 k/k/ °F (upper limit). With the BOL/ARO/HZP - MTC more positive than -3.469 x 10 -5 k/k/ °F (BOL MTC limit),

establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 k/k/ °F (upper limit) for all times in core life.

The EOL/ARO/RTP - MTC shall be less negative than or equal to -4.40 x 10 -4 k/k/ °F (lower limit).

2.3.2 The 300 ppm surveillance limit is:

The 300 ppm /ARO/RTP-MTC should be less negative than or equal to

-3.75 x 10-4 k/k/°F.

2.3.3 The 60 ppm surveillance limit is:

The measured 60 ppm /ARO/RTP-MTC should be less negative than or equal to

-4.15 x 10-4 k/k/°F.

2.4 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.5)

2.4.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps withdrawn.

2.5 CONTROL BANK INSERTION LIMITS (LCO 3.1.6)

2.5.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure 2.

2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.

2.5.3 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.

2.5.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap as a function of park position.

Park Position (steps) Bank Overlap (steps) Bank Difference Tip-to-Tip Separ ation (steps) 225 97 128 226 98 128 227 99 128 228 100 128 229 101 128 230 102 128 231 103 128

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2.6 HEAT FLUX HOT CHANNEL FACTOR - F Q(Z) (LCO 3.2.1)

> 0.5

0.5 0.5

where:

= U

=

2.6.1 = 2.62

2.6.2 K(Z) is provided in Figure 3.

2.6.3

>0.5

0.5 0.5

where:

= U >0.5

= U 0.5

and, is the measured planar radial peaking factor.

evaluations are not applicable for axial core regions, measured in percent of core height:

a. Lower core region, from 0 to 10% inclusive,

b. Upper core region, from 90 to 100% inclusive,

c. Grid plane regions, +/-2% inclusive, and

d. Core plane regions, within +/-2% of the bank demand positions of the control banks.

2.6.4 values are provided in Tables 2 and 3 for RAOC operating space one (ROS1) and RAOC operating space two (ROS2).

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2.6.5

The factors adjust the surveillance to the reference conditions assumed in generating the factors. may be assumed to equal 1.0 or may be determined for specific surveillance conditions using the approved methods listed in TS 5.6.3.

2.6.6

The penalty factors account for the potential decrease in transient F Q margin between surveillances. The factors for ROS1 and ROS2 are provided in Tables 4 and 5 respectively.

2.6.7

Table 6 provides the required limits on THERMAL POWER and the required AFD reductions for each ROS in the event that additional margin is required.

2.6.8

The uncertainty, UFQ, to be applied to measured FQ(Z) shall be calculated by the following:

UFQ = Uqu

• Ue

where:

Uqu = Base FQ measurement uncertainty = 1.05 when PDMS is inoperable (Uqu is defined by PDMS and cannot be less than 1.05 when OPERABLE)

Ue = Engineering uncertainty factor = 1.03

2.7 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F H N (LCO 3.2.2)

F HN

• U¨ H F HRTP * ( 1 + PF¨ H * ( 1-P))

where P = Thermal Power / Rated Thermal Power

F HRTP = 1.70 for RFA-2 fuel, and 1.61 for HTP fuel

PF¨ H = 0.3

The uncertainty, U¨ H, to be applied to measured F¨ HN shall be 1.04 when PDMS is inoperable (U¨ H is defined by PDMS and cannot be less than 1.04 when OPERABLE).

2.8 AXIAL FLUX DIFFERENCE - AFD (LCO 3.2.3)

The AFD limits for Cycle 27 are provided in Figure 4.

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2.9 REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION (LCO 3.3.1)

2.9.1 Overtemperature ¨T Trip Setpoints

Parameter Value Overtemperature ¨T reactor trip setpoint K 1 1.15 Overtemperature ¨T reactor trip setpoint T avg coefficient K2 0.015/°F Overtemperature ¨T reactor trip setpoint pressure coefficient K 3 = 0.0008/psig Nominal Tavg atRTP T' 578.2°F Nominal RCS operating pressure P' = 2235 psig Measured RCS ¨T lead/lag time constants 4 5 sec 5 3 sec Measured RCS average temperature lead/lag time constants 1 33 sec 2 4 sec

2.9.2 Overpower ¨T Trip Setpoints

Parameter Value Overpower ¨ T reactor trip setpoint K4 1.087 Overpower ¨ T reactor trip setpoint Tavg rate/lag coefficient K5 0.02/°F for increasing Tavg 0/°F for decreasing Tavg Overpower ¨ T reactor trip setpoint Tavg heatup coefficient K6 0.0011/°F when T > T 0/°F when T T Nominal Tavg atRTP T" 578.2°F Measured RCS ¨T lead/lag time constants 4 5 sec 5 3 sec Measured RCS average temperature rate/lag time constant 3 10 sec

2.9.3 Trip Reset Term [f1( I)] for Overtemperature ¨T Trip The following parameters are required to specify the power level-dependent f 1( I) trip reset term limits for TS Table 3.3.1-1 (function 6), Overtemperature ¨T trip function:

2.9.3.1 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.

2.9.3.2 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.

2.9.3.3 QTNS = 2.50%

where QTNS = the percent reduction in Overtemperature ¨T trip setpoint for each percent that the magnitude of I exceeds its negative limit at RATED THERMAL POWER (QTNL).

2.9.3.4 QTPS = 1.40%

where QTPS = the percent reduction in Overtemperature ¨T trip setpoint for each percent that the magnitude of I exceeds its positive limit at RATED THERMAL POWER (QTPL).

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2.9.4 Trip Reset Term [f2( I)] for Overpower ¨T Trip The following parameters are required to specify the power level-dependent f 2( I) trip reset term limits for TS Table 3.3.1-1 (function 7), Overpower ¨T trip function:

2.9.4.1 QPNL = 0%

where QPNL = the maximum negative I setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.

2.9.4.2 QPPL = 0%

where QPPL = the maximum positive I setpoint at RATED THERMAL POWER at which the trip setpoint is not reduced by the axial power distribution.

2.9.4.3 QPNS = 0%

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

2.9.4.4 QPPS = 0%

where QPPS = the percent reduction in Overpower ¨T trip setpoint for each percent that the magnitude of I exceeds its positive limit at RATED THERMAL POWER (QPPL).

2.10 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS (LCO 3.4.1)

Parameter Indicated Value

Pressurizer pressure 2220 psia

RCS average temperature 583F

RCS flow 378,400 gpm

2.11 REFUELING BORON CONCENTRATION (LCO 3.9.1)

The refueling boron concentration shall be 2000 ppm.

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Figure 1 Reactor Core Safety Limits RCS T-avg Versus Rated Thermal Power Unit 1 Cycle 27 SEQUOYAH Page 9 of 19 Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 27

Figure 2 Control Bank Insertion Limits Versus Rated Thermal Power Four Loop Operation

Notes: The above control bank insertion limits are applicable to both ROS1 and ROS2.

• 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.

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1.2

1.1

1

0.9

0.8

0.7

0.6 Core Height K(Z) 0.000 1.000 0.5 6.000 1.000 12.000 1.000

0.4

0.3

0.2

0.1

0 0123456789101112 Core Height (feet)

Figure 3 K(Z) - Normalized FQ(Z) as a Function of Core Height

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110

100 Unacceptable Unacceptable

90 ROS 1 RA-1 80 ROS 2 RA-2

70 Acceptable

60

50

40

30

20

10

0

-40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 Axial Flux Difference ( I %)

Figure 4 Axial Flux Difference Acceptable Operation Limits as a function of Rated Thermal Power (RAOC)

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Table 1 COLR Methodology Topical Reports

1. WCAP-8745-P-A, Design Bases for the Thermal Overpower ¨T and Thermal Overtemperature

¨T Trip Functions, September 1986.

(methodology for OT¨T and OP¨T Reactor Trip System setpoints in TS 3.3.1)

2. WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985.

(methodology for Shutdown Margin, Moderator Temperature Coefficient, Shutdown Bank Insertion Limit, Control Bank Insertion Limits, Axial Flux Difference, Heat Flux Hot Channel Factor, Nuclear Enthalpy Rise Hot Channel Factor, DNB Limits, Refueling Pool Boron Concentration)

3. WCAP-10216-P-A, Revision 1A, Relaxation of Constant Axial Offset Control - F Q Surveillance Technical Specification, February 1994.

(methodology for Axial Flux Difference limits with Relaxed Axial Offset Control and Heat Flux Hot Channel Factor (W(z)) Surveillance Requirements for F Q)

4. WCAP-10444-P-A, Reference Core Report VANTAGE 5 Fuel Assembly, September 1985.

(methodology for Axial Flux Difference and Heat Flux Hot Channel Factor Limits)

5. WCAP-10444-P-A Addendum 2-A, VANTAGE 5H Fuel Assembly, February 1989.

(methodology for Axial Flux Difference and Heat Flux Hot Channel Factor Limits)

6. WCAP-10965-P-A, ANC: A Westinghouse Advanced Nodal Computer Code, September 1986.

(methodology for Shutdown Margin, Moderator Temperature Coefficient, Shutdown Bank Insertion Limit, Control Bank Insertion Limits, Axial Flux Difference, Heat Flux Hot Channel Factor, Nuclear Enthalpy Rise Hot Channel Factor, Refueling Pool Boron Concentration)

7. WCAP-10965-P-A, Addendum 2-A, Revision 0, Qualification of the New Pin Power Recovery Methodology, September 2010.

(methodology for Shutdown Margin, Moderator Temperature Coefficient, Shutdown Bank Insertion Limit, Control Bank Insertion Limits, Heat Flux Hot Channel Factor, Nuclear Enthalpy Rise Hot Channel Factor, Axial Flux Difference, TS 3.4.1 DNB Limits, Refueling Pool Boron Concentration)

8. WCAP-11397-P-A, Revised Thermal Design Procedure, April 1989.

(methodology for Reactor Core Safety Limits, Nuclear Enthalpy Rise Hot Channel Factor, TS 3.4.1 DNB Limits)

9. WCAP-12610-P-A, VANTAGE+ Fuel Assembly Reference Core Report, April 1995.

(methodology for Axial Flux Difference and Heat Flux Hot Channel Factor Limits)

10. WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, Optimized ZIRLO TM, July 2006.

(methodology for Axial Flux Difference and Heat Flux Hot Channel Factor Limits)

11. WCAP-14565-P-A, VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis, October 1999.

(methodology for Reactor Core Safety Limits, Nuclear Enthalpy Rise Hot Channel Factor, and TS 3.4.1 DNB Limits)

Unit 1 Cycle 27 SEQUOYAH Page 13 of 19 Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 27

12. WCAP-14565-P-A, Addendum 1-A, Revision 0, Addendum 1 to WCAP 14565-P-A Qualification of ABB-NV Critical Heat Flux Correlations with VIPRE-01 Code, August 2004.

(methodology for Axial Flux Difference)

13. WCAP-14565-P-A, Addendum 2-P-A, Revision 0, Addendum 2 to WCAP-14565-P-A Extended Application of ABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Low Pressure Applications, April 2008.

(methodology for TS 3.4.1 DNB Limits)

14. WCAP-15025-P-A, Modified WRB-2 Correlation, WRB-2M, for Predicting Critical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane Grids, April 1999.

(methodology for Reactor Core Safety Limits and Nuclear Enthalpy Rise Hot Channel Factor)

15. WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON, August 2004.

(methodology for Shutdown Margin, Moderator Temperature Coefficient, Shutdown Bank Insertion Limit, Control Bank Insertion Limits, Heat Flux Hot Channel Factor, Nuclear Enthalpy Rise Hot Channel Factor, Axial Flux Difference, TS 3.4.1 DNB Limits, Refueling Pool Boron Concentration)

16. WCAP-16045-P-A, Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology, August 2007.

(methodology for Moderator Temperature Coefficient)

17. WCAP-16996-P-A, Revision 1, Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology), November 2016.

(methodology for FQ and FN¨ H limits)

18. WCAP-17661-P-A, Revision 1, "Improved RAOC and CAOC F Q Surveillance Technical Specifications," February 2019.

(methodology for control bank insertion limits, F Q limits, and AFD limits)

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Table 2

[T(Z)]COLR Factors for ROS1

150 3000 6000 10000 14000 18000 Height (ft) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 12.0720 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.8708 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.6696 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.4684 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.2672 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.0660 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 10.8648 0.9893 0.9078 0.9302 1.0907 1.1859 1.2101 10.6636 1.0814 1.0173 1.0520 1.1821 1.2615 1.2895 10.4624 1.1330 1.0850 1.1346 1.2283 1.2920 1.3179 10.2612 1.1504 1.1181 1.1737 1.2366 1.2838 1.3012 10.0600 1.2343 1.2251 1.2696 1.2996 1.3206 1.3299 9.8588 1.2515 1.2456 1.3020 1.3244 1.3221 1.3218 9.6576 1.2049 1.2159 1.2647 1.2601 1.2714 1.2544 9.4564 1.2264 1.2468 1.2926 1.2728 1.2828 1.2606 9.2552 1.2063 1.2240 1.2791 1.2496 1.2605 1.2396 9.0540 1.1822 1.2029 1.2495 1.2148 1.2252 1.2065 8.8528 1.2568 1.2728 1.2963 1.2640 1.2658 1.2444 8.6516 1.2725 1.2893 1.3010 1.2692 1.2553 1.2295 8.4504 1.3223 1.3432 1.3471 1.3026 1.2876 1.2552 8.2492 1.2650 1.2945 1.2962 1.2485 1.2341 1.2109 8.0480 1.3572 1.3904 1.3815 1.3165 1.2931 1.2699 7.8468 1.3088 1.3518 1.3375 1.2741 1.2499 1.2343 7.6456 1.3304 1.3794 1.3581 1.2802 1.2533 1.2427 7.4444 1.2711 1.3272 1.3044 1.2280 1.2042 1.2027 7.2432 1.2925 1.3552 1.3241 1.2389 1.2114 1.2140 7.0420 1.3359 1.4013 1.3614 1.2641 1.2313 1.2360 6.8408 1.3172 1.3838 1.3413 1.2396 1.2065 1.2163 6.6396 1.3868 1.4529 1.4008 1.2853 1.2472 1.2600 6.4384 1.3716 1.4377 1.3842 1.2659 1.2275 1.2442 6.2372 1.3227 1.3889 1.3359 1.2192 1.1815 1.2012 6.0360 1.3174 1.3818 1.3314 1.2086 1.1690 1.1914 5.8348 1.2931 1.3626 1.3139 1.1877 1.1513 1.1756 5.6336 1.2361 1.3098 1.2673 1.1474 1.1137 1.1410 5.4324 1.2839 1.3690 1.3289 1.1983 1.1560 1.1723 5.2312 1.3209 1.4123 1.3731 1.2359 1.1896 1.2012 5.0300 1.3145 1.4056 1.3695 1.2354 1.1888 1.1987 4.8288 1.3084 1.3983 1.3663 1.2352 1.1885 1.1967 4.6276 1.3138 1.4019 1.3734 1.2475 1.1991 1.2019 4.4264 1.3285 1.4144 1.3886 1.2669 1.2162 1.2132 4.2252 1.3127 1.3956 1.3754 1.2638 1.2134 1.2064 4.0240 1.2479 1.3278 1.3170 1.2260 1.1779 1.1712 3.8228 1.2491 1.3278 1.3192 1.2444 1.1916 1.1786 3.6216 1.3068 1.3833 1.3727 1.3080 1.2497 1.2254 3.4204 1.3165 1.3842 1.3791 1.3297 1.2729 1.2422 3.2192 1.3054 1.3613 1.3639 1.3338 1.2824 1.2455 3.0180 1.3047 1.3453 1.3579 1.3458 1.2992 1.2685 2.8168 1.3053 1.3366 1.3456 1.3528 1.3260 1.2982 2.6156 1.3077 1.3228 1.3281 1.3561 1.3509 1.3239 2.4144 1.3341 1.3343 1.3369 1.3831 1.3990 1.3716 2.2132 1.2720 1.2579 1.2619 1.3334 1.3739 1.3559 2.0120 1.2836 1.2492 1.2577 1.3464 1.4087 1.3968 1.8108 1.3299 1.2695 1.2794 1.3842 1.4672 1.4618 1.6096 1.3321 1.2463 1.2580 1.3783 1.4860 1.4941 1.4084 1.2834 1.1767 1.1896 1.3201 1.4494 1.4739 1.2072 1.2033 1.0792 1.0907 1.2237 1.3676 1.4084 1.0060 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.8048 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.6036 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.4024 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.2012 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000

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Table 3

[T(Z)]COLR Factors for ROS2

150 3000 6000 10000 14000 18000 Height (ft) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 12.0720 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.8708 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.6696 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.4684 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.2672 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.0660 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 10.8648 0.9893 0.9059 0.9302 1.0907 1.1859 1.2101 10.6636 1.0814 1.0173 1.0520 1.1821 1.2615 1.2895 10.4624 1.1330 1.0809 1.1346 1.2283 1.2920 1.3179 10.2612 1.1504 1.1134 1.1737 1.2366 1.2838 1.3019 10.0600 1.2343 1.2253 1.2696 1.2996 1.3206 1.3257 9.8588 1.2515 1.2459 1.3020 1.3244 1.3220 1.3103 9.6576 1.2049 1.2159 1.2647 1.2599 1.2712 1.2521 9.4564 1.2265 1.2468 1.2926 1.2725 1.2825 1.2606 9.2552 1.2018 1.2239 1.2791 1.2493 1.2601 1.2396 9.0540 1.1699 1.2032 1.2495 1.2145 1.2248 1.2065 8.8528 1.2425 1.2701 1.2963 1.2640 1.2656 1.2444 8.6516 1.2597 1.2847 1.3010 1.2692 1.2553 1.2295 8.4504 1.3093 1.3406 1.3471 1.3026 1.2876 1.2552 8.2492 1.2529 1.2933 1.2962 1.2485 1.2341 1.2109 8.0480 1.3447 1.3904 1.3815 1.3165 1.2931 1.2699 7.8468 1.2972 1.3517 1.3375 1.2741 1.2499 1.2343 7.6456 1.3192 1.3794 1.3581 1.2802 1.2533 1.2427 7.4444 1.2607 1.3272 1.3044 1.2280 1.2042 1.2027 7.2432 1.2850 1.3552 1.3241 1.2389 1.2114 1.2140 7.0420 1.3291 1.4013 1.3614 1.2641 1.2313 1.2360 6.8408 1.3113 1.3838 1.3413 1.2396 1.2065 1.2163 6.6396 1.3814 1.4529 1.4008 1.2853 1.2472 1.2600 6.4384 1.3672 1.4377 1.3842 1.2659 1.2275 1.2442 6.2372 1.3194 1.3888 1.3358 1.2192 1.1815 1.2012 6.0360 1.3151 1.3819 1.3314 1.2085 1.1689 1.1906 5.8348 1.2918 1.3620 1.3137 1.1876 1.1511 1.1715 5.6336 1.2359 1.3096 1.2663 1.1456 1.1162 1.1354 5.4324 1.2842 1.3688 1.3184 1.1905 1.1520 1.1687 5.2312 1.3188 1.4087 1.3563 1.2252 1.1822 1.1933 5.0300 1.3035 1.3953 1.3467 1.2215 1.1783 1.1860 4.8288 1.2883 1.3803 1.3376 1.2184 1.1748 1.1782 4.6276 1.2870 1.3790 1.3389 1.2276 1.1823 1.1796 4.4264 1.2949 1.3843 1.3482 1.2439 1.1959 1.1860 4.2252 1.2769 1.3584 1.3300 1.2381 1.1906 1.1748 4.0240 1.2112 1.2866 1.2676 1.1954 1.1542 1.1361 3.8228 1.2097 1.2825 1.2656 1.2043 1.1642 1.1390 3.6216 1.2620 1.3316 1.3150 1.2571 1.2133 1.1771 3.4204 1.2676 1.3284 1.3163 1.2692 1.2265 1.1937 3.2192 1.2539 1.3022 1.2966 1.2708 1.2300 1.2019 3.0180 1.2490 1.2861 1.2865 1.2781 1.2417 1.2186 2.8168 1.2479 1.2693 1.2819 1.2865 1.2522 1.2439 2.6156 1.2489 1.2526 1.2698 1.2927 1.2709 1.2672 2.4144 1.2729 1.2616 1.2801 1.3229 1.3153 1.3123 2.2132 1.2123 1.1869 1.2103 1.2761 1.2901 1.2984 2.0120 1.2214 1.1758 1.2012 1.2880 1.3206 1.3381 1.8108 1.2631 1.1916 1.2166 1.3229 1.3732 1.4000 1.6096 1.2626 1.1681 1.1915 1.3167 1.3881 1.4296 1.4084 1.2140 1.1025 1.1223 1.2607 1.3515 1.4091 1.2072 1.1362 1.0110 1.0252 1.1680 1.2732 1.3457 1.0060 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.8048 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.6036 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.4024 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.2012 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000

Unit 1 Cycle 27 SEQUOYAH Page 16 of 19 Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 27

Table 4 Rj Margin Decrease Factors for ROS1

Cycle Burnup RJ Cycle Burnup RJ Cycle Burnup RJ (MWD/MTU) (MWD/MTU) (MWD/MTU) 150 1.0011 7736 1.0022 15321 1.0007 340 1.0005 7925 1.0058 15511 1.0003 529 1.0002 8115 1.0116 15700 1.0001 719 1.0000 8304 1.0113 15890 1.0000 909 1.0000 8494 1.0133 16080 1.0000 1098 1.0000 8684 1.0152 16269 1.0000 1288 1.0000 8873 1.0170 16459 1.0000 1477 1.0000 9063 1.0188 16648 1.0000 1667 1.0007 9253 1.0205 16838 1.0000 1857 1.0026 9442 1.0221 17028 1.0000 2046 1.0044 9632 1.0237 17217 1.0000 2236 1.0058 9822 1.0253 17407 1.0000 2426 1.0067 10011 1.0244 17597 1.0000 2615 1.0067 10201 1.0236 17786 1.0000 2805 1.0063 10390 1.0236 17976 1.0000 2995 1.0056 10580 1.0314 18166 1.0000 3184 1.0048 10770 1.0312 18355 1.0000 3374 1.0037 10959 1.0309 18545 1.0000 3563 1.0023 11149 1.0304 18735 1.0000 3753 1.0011 11339 1.0300 18924 1.0000 3943 1.0003 11528 1.0295 19114 1.0000 4132 1.0000 11718 1.0285 19303 1.0000 4322 1.0000 11908 1.0268 19493 1.0000 4512 1.0000 12097 1.0175 19683 1.0000 4701 1.0000 12287 1.0161 19872 1.0000 4891 1.0000 12476 1.0149 20062 1.0000 5081 1.0000 12666 1.0137 20252 1.0000 5270 1.0001 12856 1.0125 5460 1.0007 13045 1.0114 5649 1.0012 13235 1.0104 5839 1.0018 13425 1.0095 6029 1.0027 13614 1.0086 6218 1.0009 13804 1.0077 6408 1.0000 13994 1.0068 6598 1.0000 14183 1.0058 6787 1.0000 14373 1.0047 6977 1.0000 14562 1.0036 7167 1.0000 14752 1.0027 7356 1.0000 14942 1.0019 7546 1.0000 15131 1.0012

Values may be interpolated to the surveillance cycle burnup.

Unit 1 Cycle 27 SEQUOYAH Page 17 of 19 Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 27

Table 5 Rj Margin Decrease Factors for ROS2

Cycle Burnup RJ Cycle Burnup RJ Cycle Burnup RJ (MWD/MTU) (MWD/MTU) (MWD/MTU) 150 1.0025 7736 1.0000 15321 1.0079 340 1.0016 7925 1.0000 15511 1.0074 529 1.0008 8115 1.0000 15700 1.0068 719 1.0003 8304 1.0000 15890 1.0062 909 1.0000 8494 1.0000 16080 1.0057 1098 1.0000 8684 1.0000 16269 1.0051 1288 1.0000 8873 1.0007 16459 1.0046 1477 1.0005 9063 1.0065 16648 1.0045 1667 1.0021 9253 1.0121 16838 1.0045 1857 1.0039 9442 1.0152 17028 1.0046 2046 1.0056 9632 1.0185 17217 1.0047 2236 1.0069 9822 1.0197 17407 1.0049 2426 1.0076 10011 1.0191 17597 1.0051 2615 1.0075 10201 1.0178 17786 1.0054 2805 1.0069 10390 1.0168 17976 1.0057 2995 1.0061 10580 1.0142 18166 1.0056 3184 1.0052 10770 1.0136 18355 1.0055 3374 1.0039 10959 1.0131 18545 1.0053 3563 1.0025 11149 1.0127 18735 1.0051 3753 1.0012 11339 1.0124 18924 1.0049 3943 1.0003 11528 1.0123 19114 1.0047 4132 1.0000 11718 1.0121 19303 1.0044 4322 1.0000 11908 1.0115 19493 1.0042 4512 1.0000 12097 1.0130 19683 1.0040 4701 1.0000 12287 1.0125 19872 1.0038 4891 1.0000 12476 1.0121 20062 1.0035 5081 1.0000 12666 1.0118 20252 1.0033 5270 1.0001 12856 1.0115 5460 1.0007 13045 1.0112 5649 1.0012 13235 1.0110 5839 1.0018 13425 1.0110 6029 1.0027 13614 1.0109 6218 1.0009 13804 1.0108 6408 1.0000 13994 1.0107 6598 1.0000 14183 1.0104 6787 1.0000 14373 1.0102 6977 1.0000 14562 1.0098 7167 1.0000 14752 1.0094 7356 1.0000 14942 1.0089 7546 1.0000 15131 1.0084

Values may be interpolated to the surveillance cycle burnup.

Unit 1 Cycle 27 SEQUOYAH Page 18 of 19 Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 27

Table 6 Required Thermal Power Limits and AFD Reductions

RAOC Required FQW(z) Required THERMAL Operating Margin Improvement POWER Limit Required AFD Reduction Space (%)

(%RTP)

ROS1 6.1 90 See Figure 4, RA-1

>6.1 <50 N/A

ROS2 6.0 90 See Figure 4, RA-2

>6.0 <50 N/A

Unit 1 Cycle 27 SEQUOYAH Page 19 of 19 Revision 0