ML22332A463

Cycle 26 Core Operating Limits Report

ML22332A463
Person / Time
Site:	Sequoyah
Issue date:	11/28/2022
From:	Marshall T Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML22332A463 (1)

Text

TENNESSEE VALLEY 1\\14 AUTHORITY

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

November 28, 2022 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 26 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 26 Core Operating Limits Report (COLR), Revision 0 that was issued on November 2, 2022.

There are no new regulatory commitments in this letter. If you have any questions, please contact Jeffrey Sowa, SQN Site Licensing Manager at (423) 843-8129.

Respectfully,

Thomas Marshall Site Vice President Sequoyah Nuclear Plant

Enclosure:

Sequoyah Unit 1 Cycle 26 Core Operating Limits Report, Revision 0

cc (Enclosure):

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

SEQUOYAH UNIT 1 CYCLE 26 CORE OPERATING LIMITS REPORT REVISION 0

QA Record L36 220922 801

SEQUOYAH UNIT 1 CYCLE 26 CORE OPERATING LIMITS REPORT REVISION 0

October 2022

Prepared by:

Digitally ligned by S.h.arpe,, Natha n ~I Trevon ON: dc*gov. d,c c tv,a, dc *ma ln, ou ~MMn. ou ~Corpotillle, ou ~ uiers.

cn ::s:Sharper, Natha n! ~ Tre\\'on. emalhmuharper (lltw.gO'v Rea!I.On: I am.approving 1h1, doc.um, n\\

Date: 2022.0921 08:56:34 -04'00' I N. Trevon Sharper, PWR Fuel Engineering Date

Verified by:

Digitally signed by Porter, Mark Donald Porter, Mark DN : dc.=gov, dc =tva, dc = ma ln, ou=Ma in,

ou =Corpor ate, ou =U sers, cn,o Porter, Mark Donald,

email=mdporter@tva.gov Donald Date: 2022.09.27 09;)3:15 -04'00' / Reason : I have reviewe d this document

Mark 0. Porter, PWR Fuel Engineering Date

Reviewed by:

Olgltally signed by Rllthle, John A ON: dc =gov, dc =tva, dc = maln, ou =Ma ln, ou =Co rpo rate, Ritchie, John A o u= Us ers, cn =Rltchle, Jo hn A. emall=J ar1tchle0@tva.gov Reason: I have reviewed this documen t Date: 2022.09.27 t 0:46:57 -04 '00' I John A. Ritchie, PWR Fuel Engineering Manager Date Phillips, Eric Lewis Digitally signed by Phillips, Eric Lewis Date: 2022.09.27 11:15:00 -04'00' I

Eric L. Phillips, Reactor Engineering Manager Date

Approved by :

I Date

Date of PORC Affected Revision Approval Pages Reason for Revision 0 See above All Initial Issue

Unit I Cycle 26 SEQUOYAH Page I of 19 Revision 0 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 M ARGIN (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 - SDM 2.2.6 3 MODE 2 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 5 Rj Penalty Factor 2.6.6 5 Thermal Power Limits 2.6.7 6 UFQ 2.6.8 6 3.2.2 Nuclear Enthalpy Rise Hot Channel F HN 2.7 6 Factor (FH N )

3.2.3 Axial Flux Difference (AFD) AFD Limits 2.8 6 Overtemperature =peo = 2.9.1 7 3.3.1 Reactor Trip System (RTS) power= 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 Analytical Methods Table 1 13 REPORT (COLR)

Unit 1 Cycle 26 SEQUOYAH Page 2 of 19 Revision 0 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 LIMIT S (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 keff < 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 keff 1.0.

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

Unit 1 Cycle 26 SEQUOYAH Page 3 of 19 Revision 0 2.3 MODERATOR TEMPERATURE COEFFICIENT - MTC (LCO 3.1.3)

2.3.1 The Moderator T emperature Coefficient (MTC) limits are:

The BOL/ARO/HZP - MTC shall be less positive than 0 k/k/ °F (upper limit). With the measured BOL/ARO/HZP - MTC more positive than -2. 210 x 10-5 k/k/ °F (as-measured 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

-4.45 x 10 -4 k/k/°F (lower limit).

2.3.2 The 300 ppm surveillance limit is:

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

-3.80 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

-4.20 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 DifferenceTip -to -

Tip Separation (steps) 225 97 1 28 226 98 128 227 99 1 28 228 1 00 1 28 229 1 01 1 28 230 102 1 28 231 103 1 28

Unit 1 Cycle 26 SEQUOYAH Page 4 of 19 Revision 0 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

() = [()] [()]() > 0.5 U

() = [()] [()]() 0.5

0. 5 U

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).

Unit 1 Cycle 26 SEQUOYAH Page 5 of 19 Revision 0 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 FQ margin between surveillances. The factors for ROS1 and ROS2 are provided i n 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 F Q(Z) shall be calculated by the following:

U FQ = Uqu

• Ue

where:

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

U e = Engineering uncertainty factor = 1.03

2.7 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F H N (LCO 3.

FHN

• UH FHRTP * ( 1 + PFH * ( 1-P))

where P = Thermal Power / Rated Thermal Power

FHRTP = 1.70 for RFA-2 fuel, and 1.61 for HTP fuel

PFH = 0.3

The uncertainty, UH, to be applied to measured FHN shall be 1.04 when PDMS is inoperable (UH 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 26 are provided in Figure 4.

Unit 1 Cycle 26 SEQUOYAH Page 6 of 19 Revision 0 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 at RTP 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 K 4 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 K 6 0.0011/°F when T > T 0/°F when T T Nominal Tavg at RTP 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 se tpoint 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).

Unit 1 Cycle 26 SEQUOYAH Page 7 of 19 Revision 0 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 2220psi a

RCS average temperature 583F

RCS flow 378,400gpm

2.11 REFUELING BORON CONCENTRATION (LCO 3.9.1)

The refueling boron concentration shall be 2000 ppm.

Unit 1 Cycle 26 SEQUOYAH Page 8 of 19 Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 26

68()~------------------------~

UNACCE PTABLE 600 OP ERAT ION

6<<)

£

~ !I!'

(/')

u a::

6lD 1860 psia

000 ACCE PTABLE OPERAT ION

550-+-- ~~~~~~-- *- *~~-~~*~*~~~~ - ~~~._..

0 0 2 0.4 0,6 0.8 Fraction o f Ra ted Thenna l Power

Figure 1 Reactor Core Safety Limits RCS T-avg Versus Rated Thermal Power Unit 1 Cycle 26 SEQUOYAH Page 9 of 19 Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 26

23 1 /Fullv Withdrawn Reaion)* (.575, 225) 220./

200 /

/ / (1.0, 182) 180

160 / /

C KC

.::; 0 140 / / BAN ~/

• u5 a.. 0 (.097

0. /

(I) 1 20 if)

~ ~10)

C /

a) ro 100

-0 / BANK D a: 0 / -

80

60 /

40 /

20 /

0 (.09, 0) /

0 0.2 0.4 0.6 0.8 1 (Fully Inserted)

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

Note: 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.

Unit 1 Cycle 26 SEQUOYAH Page 10 of 19 Revision 0 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 0 1 2 3 4 5 6 7 8 9 10 11 12 Core Height (feet)

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

Unit 1 Cycle 26 SEQUOYAH Page 11 of 19 Revision 0 COLR FOR SEQUOYAH UNIT 1 CYCLE 26

110

100 r Unacceptable I Unacceptable I I

I 90 ! *...... - *- * * *- *- - **

Jtr. /*,* \\ ROS 1

,

• I * **** RA-1 80,.. '* ROS 2 Jtr I \\. -.

• RA-2

1,,*

• 70,. I, Acceptable Jtr, *

,..,

• I

60 I

50

ROS 1 ROS2 RA-1 RA-2 40 Power AFD Limit AFD Limit Power AFD Limit AFD Limit

(% RTP) (%) (%) (%RTP) (%) (%)

50 -40 -36 50 -35.5 -31.5 100 -13 -9 90 -14 -10 30 100 7 7 90 8 8 50 28 28 50 25 25

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)

Unit 1 Cycle 26 SEQUOYAH Page 12 of 19 Revision 0 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 OTT and OPT 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 Bor on 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 FQ)

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 DNB Safety Limit, Nuclear Enthalpy Rise Hot Channel Factor, and TS 3.4.1 DNB Limits)

Unit 1 Cycle 26 SEQUOYAH Page 13 of 19 Revision 0

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 DNB Safety Limit)

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 DNB Safe ty Limit)

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 DNB Safety Limit 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, Nu clear 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 Temperat ure 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 FNH 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)

Unit 1 Cycle 26 SEQUOYAH Page 14 of 19 Revision 0 Table 2

[T(Z)]COLR Factors for ROS1

Elevation 150 3000 6000 10000 14000 16000 Point (ft) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 1 12.2067 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 2 12.0033 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 3 11.7998 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 4 11.5964 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 5 11.3929 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 6 11.1895 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 7 10.9860 1.1109 0.9943 1.0176 1.1496 1.2655 1.2510 8 10.7826 1.1424 1.0551 1.0760 1.1961 1.3040 1.2861 9 10.5791 1.1942 1.1169 1.1596 1.2708 1.3551 1.3194 10 10.3757 1.2064 1.1358 1.1910 1.2850 1.3468 1.3063 11 10.1723 1.2266 1.1798 1.2387 1.3093 1.3527 1.3126 12 9.9688 1.2132 1.1703 1.2222 1.2816 1.3084 1.2757 13 9.7654 1.2759 1.2383 1.2884 1.3286 1.3215 1.3081 14 9.5619 1.2474 1.2232 1.2683 1.2895 1.2924 1.2629 15 9.3585 1.2525 1.2490 1.2787 1.2789 1.2875 1.2548 16 9.1550 1.2266 1.2403 1.2554 1.2419 1.2579 1.2249 17 8.9516 1.2557 1.2861 1.2863 1.2645 1.2772 1.2422 18 8.7481 1.2889 1.3357 1.3270 1.2924 1.2936 1.2558 19 8.5447 1.2908 1.3462 1.3292 1.2851 1.2877 1.2440 20 8.3412 1.3468 1.4088 1.3800 1.3225 1.3247 1.2822 21 8.1378 1.3700 1.4362 1.3980 1.3305 1.3334 1.2932 22 7.9344 1.3376 1.4099 1.3669 1.2939 1.2982 1.2623 23 7.7309 1.3462 1.4226 1.3732 1.2930 1.2978 1.2649 24 7.5275 1.3288 1.4056 1.3526 1.2703 1.2776 1.2494 25 7.3240 1.3164 1.3931 1.3359 1.2504 1.2591 1.2353 26 7.1206 1.3625 1.4393 1.3755 1.2788 1.2849 1.2626 27 6.9171 1.3517 1.4251 1.3636 1.2636 1.2672 1.2485 28 6.7137 1.3762 1.4450 1.3828 1.2787 1.2769 1.2614 29 6.5102 1.3236 1.3861 1.3307 1.2322 1.2286 1.2181 30 6.3068 1.3772 1.4337 1.3756 1.2699 1.2576 1.2485 31 6.1034 1.3385 1.3966 1.3392 1.2379 1.2176 1.2166 32 5.8999 1.3264 1.3896 1.3250 1.2274 1.2051 1.2073 33 5.6965 1.2838 1.3504 1.2863 1.1881 1.1657 1.1772 34 5.4930 1.3114 1.3768 1.3117 1.2065 1.1826 1.1915 35 5.2896 1.3537 1.4190 1.3511 1.2443 1.2148 1.2189 36 5.0861 1.3551 1.4200 1.3535 1.2509 1.2185 1.2193 37 4.8827 1.3495 1.4147 1.3516 1.2524 1.2175 1.2149 38 4.6792 1.3514 1.4165 1.3572 1.2613 1.2229 1.2173 39 4.4758 1.3544 1.4198 1.3652 1.2733 1.2312 1.2233 40 4.2723 1.3426 1.4072 1.3611 1.2746 1.2306 1.2221 41 4.0689 1.3030 1.3616 1.3281 1.2505 1.2083 1.2004 42 3.8655 1.2920 1.3447 1.3198 1.2494 1.2073 1.1989 43 3.6620 1.3349 1.3818 1.3627 1.2952 1.2496 1.2357 44 3.4586 1.3480 1.3860 1.3757 1.3191 1.2732 1.2531 45 3.2551 1.3366 1.3656 1.3656 1.3244 1.2819 1.2577 46 3.0517 1.3335 1.3510 1.3582 1.3372 1.2955 1.2729 47 2.8482 1.3369 1.3447 1.3577 1.3461 1.3168 1.2961 48 2.6448 1.3338 1.3339 1.3567 1.3557 1.3373 1.3197 49 2.4413 1.3421 1.3344 1.3648 1.3856 1.3711 1.3585 50 2.2379 1.3198 1.3016 1.3400 1.3827 1.3790 1.3734 51 2.0345 1.3118 1.2815 1.3269 1.3919 1.4005 1.4024 52 1.8310 1.3352 1.2920 1.3435 1.4297 1.4497 1.4585 53 1.6276 1.3184 1.2622 1.3186 1.4268 1.4636 1.4818 54 1.4241 1.2681 1.1990 1.2569 1.3828 1.4375 1.4657 55 1.2207 1.2040 1.1217 1.1777 1.3157 1.3880 1.4260 56 1.0172 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 57 0.8138 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 58 0.6103 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 59 0.4069 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 60 0.2034 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 61 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000

Unit 1 Cycle 26 SEQUOYAH Page 15 of 19 Revision 0 Table 3

[T(Z)]COLR Factors for ROS2

Elevation 150 3000 6000 10000 14000 16000 Point (ft) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 1 12.2067 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 2 12.0033 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 3 11.7998 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 4 11.5964 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 5 11.3929 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 6 11.1895 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 7 10.9860 1.0925 0.9943 1.0037 1.1273 1.2344 1.2510 8 10.7826 1.1226 1.0551 1.0522 1.1732 1.2730 1.2861 9 10.5791 1.1746 1.1169 1.1301 1.2521 1.3226 1.3193 10 10.3757 1.1850 1.1358 1.1630 1.2750 1.3113 1.3064 11 10.1723 1.2104 1.1799 1.2111 1.3090 1.3151 1.3117 12 9.9688 1.2063 1.1687 1.1968 1.2816 1.2786 1.2702 13 9.7654 1.2326 1.2363 1.2637 1.3287 1.3248 1.3003 14 9.5619 1.2171 1.2221 1.2460 1.2928 1.2924 1.2565 15 9.3585 1.2253 1.2492 1.2585 1.2798 1.2833 1.2515 16 9.1550 1.2015 1.2403 1.2374 1.2359 1.2499 1.2253 17 8.9516 1.2325 1.2861 1.2725 1.2471 1.2722 1.2422 18 8.7481 1.2698 1.3357 1.3136 1.2699 1.2907 1.2558 19 8.5447 1.2725 1.3462 1.3165 1.2636 1.2791 1.2440 20 8.3412 1.3289 1.4088 1.3675 1.3014 1.3108 1.2822 21 8.1378 1.3529 1.4362 1.3862 1.3104 1.3149 1.2932 22 7.9344 1.3222 1.4099 1.3561 1.2755 1.2764 1.2623 23 7.7309 1.3319 1.4226 1.3631 1.2758 1.2729 1.2649 24 7.5275 1.3160 1.4056 1.3436 1.2547 1.2504 1.2494 25 7.3240 1.3051 1.3931 1.3279 1.2364 1.2302 1.2353 26 7.1206 1.3519 1.4393 1.3681 1.2659 1.2534 1.2626 27 6.9171 1.3424 1.4251 1.3570 1.2521 1.2363 1.2485 28 6.7137 1.3683 1.4450 1.3771 1.2684 1.2486 1.2614 29 6.5102 1.3176 1.3861 1.3263 1.2240 1.2045 1.2181 30 6.3068 1.3726 1.4337 1.3722 1.2633 1.2364 1.2486 31 6.1034 1.3357 1.3966 1.3370 1.2333 1.2041 1.2122 32 5.8999 1.3253 1.3893 1.3236 1.2247 1.1917 1.2025 33 5.6965 1.2838 1.3492 1.2859 1.1877 1.1588 1.1687 34 5.4930 1.3092 1.3699 1.3091 1.2034 1.1708 1.1827 35 5.2896 1.3482 1.4035 1.3450 1.2328 1.1927 1.2093 36 5.0861 1.3457 1.3946 1.3431 1.2311 1.1919 1.2086 37 4.8827 1.3355 1.3840 1.3342 1.2246 1.1896 1.2033 38 4.6792 1.3331 1.3822 1.3329 1.2252 1.1935 1.2034 39 4.4758 1.3317 1.3817 1.3338 1.2321 1.1999 1.2054 40 4.2723 1.3157 1.3660 1.3217 1.2305 1.1971 1.1985 41 4.0689 1.2697 1.3179 1.2845 1.2046 1.1734 1.1718 42 3.8655 1.2519 1.2958 1.2728 1.2010 1.1703 1.1650 43 3.6620 1.2896 1.3264 1.3105 1.2413 1.2066 1.1954 44 3.4586 1.2972 1.3273 1.3198 1.2564 1.2220 1.2058 45 3.2551 1.2819 1.3026 1.3069 1.2594 1.2296 1.2094 46 3.0517 1.2732 1.2911 1.2992 1.2679 1.2487 1.2210 47 2.8482 1.2750 1.2898 1.3022 1.2789 1.2746 1.2443 48 2.6448 1.2716 1.2786 1.3004 1.2846 1.2977 1.2680 49 2.4413 1.2792 1.2777 1.3080 1.3079 1.3329 1.3031 50 2.2379 1.2579 1.2450 1.2831 1.3022 1.3427 1.3159 51 2.0345 1.2504 1.2247 1.2695 1.3078 1.3655 1.3422 52 1.8310 1.2730 1.2336 1.2843 1.3404 1.4150 1.3943 53 1.6276 1.2575 1.2041 1.2595 1.3350 1.4298 1.4152 54 1.4241 1.2100 1.1429 1.1997 1.2914 1.4052 1.3984 55 1.2207 1.1493 1.0684 1.1233 1.2267 1.3571 1.3593 56 1.0172 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 57 0.8138 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 58 0.6103 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 59 0.4069 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 60 0.2034 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 61 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000

Unit 1 Cycle 26 SEQUOYAH Page 16 of 19 Revision 0 Table 4 Rj Margin Decrease Factors for ROS1

Cycle Burnup Cycle Burnup Cycle Burnup (MWD/MTU) Rj (MWD/MTU) Rj (MWD/MTU) Rj 150 1.0089 7958 1.0266 13671 1.0066 340 1.0111 8148 1.0242 13861 1.0066 531 1.0127 8339 1.0229 14052 1.0065 721 1.0143 8529 1.0215 14242 1.0065 912 1.0234 8720 1.0201 14433 1.0064 1102 1.0324 8910 1.0187 14623 1.0062 1293 1.0412 9101 1.0173 14814 1.0060 1483 1.0484 9291 1.0159 15004 1.0058 1673 1.0532 9481 1.0146 15194 1.0055 1864 1.0555 9672 1.0132 15385 1.0053 2054 1.0558 9862 1.0126 15575 1.0050 2245 1.0533 10053 1.0120 15766 1.0047 2435 1.0437 10243 1.0115 15956 1.0044 2626 1.0336 10434 1.0109 16147 1.0042 2816 1.0241 10624 1.0093 16337 1.0039 3007 1.0170 10814 1.0079 16528 1.0036 3197 1.0117 11005 1.0067 16718 1.0033 3387 1.0079 11195 1.0056 16908 1.0031 3578 1.0052 11386 1.0040 17099 1.0029 3768 1.0033 11576 1.0025 17289 1.0027 3959 1.0020 11767 1.0014 17480 1.0026 4149 1.0009 11957 1.0011 17670 1.0025 4340 1.0000 12147 1.0070 17861 1.0024 4530 1.0002 12338 1.0068 18051 1.0023 4720 BU 6815 1.0000 12528 1.0066 18241 1.0022 7006 1.0045 12719 1.0065 18432 1.0021 7196 1.0100 12909 1.0064 18622 1.0020 7387 1.0154 13100 1.0065 BU 18813 1.0019 7577 1.0209 13290 1.0065 7767 1.0255 13481 1.0065

Values may be interpolated to the surveillance cycle burnup.

Unit 1 Cycle 26 SEQUOYAH Page 17 of 19 Revision 0 Table 5 Rj Margin Decrease Factors for ROS2

Cycle Burnup Cycle Burnup (MWD/MTU) Rj (MWD/MTU) Rj 150 1.0167 9291 1.0065 340 1.0156 9481 1.0109 531 1.0152 9672 1.0173 721 1.0158 9862 1.0199 912 1.0250 10053 1.0199 1102 1.0347 10243 1.0205 1293 1.0433 10434 1.0212 1483 1.0503 10624 1.0388 1673 1.0548 10814 1.0389 1864 1.0568 11005 1.0388 2054 1.0568 11195 1.0384 2245 1.0546 11386 1.0377 2435 1.0443 11576 1.0364 2626 1.0334 11767 1.0345 2816 1.0231 11957 1.0322 3007 1.0158 12147 1.0129 3197 1.0104 12338 1.0105 3387 1.0066 12528 1.0082 3578 1.0040 12719 1.0062 3768 1.0023 12909 1.0044 3959 1.0012 13100 1.0030 4149 1.0004 13290 1.0018 4340 BU 7958 1.0000 13481 1.0010 8148 1.0004 13671 1.0004 8339 1.0035 13861 1.0001 8529 1.0064 BU 14052 1.0000 8720 1.0092 8910 1.0088 9101 1.0054

Values may be interpolated to the surveillance cycle burnup.

Unit 1 Cycle 26 SEQUOYAH Page 18 of 19 Revision 0 Table 6 Required Thermal Power Limits and AFD Reductions

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

4.3 90 See Figure 4 RA-1 ROS1

> 4.3 < 50 N/A

3.7 90 See Figure 4 RA-2 ROS2

> 3.7 < 50 N/A

Unit 1 Cycle 26 SEQUOYAH Page 19 of 19 Revision 0