NOC-AE-11002765, Cycle 16 Core Operating Limits Report

Cycle 16 Core Operating Limits Report

ML11342A054
Person / Time
Site:	South Texas
Issue date:	12/01/2011
From:	Dunn R South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NOC-AE-11002765
Download: ML11342A054 (27)

Text

Nuclear Operating Company South Texas Pro/cd Electnc GeneratingStation PO. Bar 289 Wadswrth. Texas 77483 /

December 1, 2011 NOC-AE-1 1002765 File No.: G25 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Unit 2 Docket No. STN 50-499 Unit 2 Cycle 16 Core Operatinq Limits Report Pursuant to Technical Specification 6.9.1.6.d, STP Nuclear Operating Company submits the attached Core Operating Limits Report for Unit 2 Cycle 16. The report covers the core design changes made during the 2RE15 refueling outage. Revision 0 is applicable to Modes 3, 4, and 5 and Revision 1 incorporates information to include Modes 1 and 2.

There are no commitments included in this letter.

If there are any questions on this report, please contact either Marilyn Kistler at (361) 972-8385 or me at (361) 972-7743.

Roland F. Dunn Manager, Nuclear Fuel & Analysis MK Attachments: 1) Revision 0 Unit 2 Cycle 16 Core Operating Limits Report

2) Revision 1 Unit 2 Cycle 16 Core Operating Limits Report STI: 33112964

NOC-AE-1 1002765 Page 2 of 2 cc:

(paper copy) (electronic copy)

Regional Administrator, Region IV A. H. Gutterman, Esquire U. S. Nuclear Regulatory Commission Morgan, Lewis & Bockius LLP 612 East Lamar Blvd, Suite 400 Arlington, Texas 76011-4125 Balwant K. Singal U. S. Nuclear Regulatory Commission Balwant K. Singal John Ragan Senior Project Manager Chris O'Hara U.S. Nuclear Regulatory Commission Jim von Suskil One White Flint North (MS 8 B1) NRG South Texas LP 11555 Rockville Pike Rockville, MD 20852 Kevin Polio Senior Resident Inspector Richard Pena U. S. Nuclear Regulatory Commission City Public Service P. 0. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483 C. M. Canady Peter Nemeth City of Austin Crain Caton & James, P.C.

Electric Utility Department 721 Barton Springs Road C. Mele Austin, TX 78704 City of Austin Richard A. Ratliff Texas Department of State Health Services Alice Rogers Texas Department of State Health Services

ATTACHMENT 1 South Texas Project Revision 0 Unit 2 Cycle 16 Core Operating Limits Report

SOUTH TEXAS PROJECT Unit 2 Cycle 16 CORE OPERATING LIMITS REPORT Revision 0 MODES 3, 4 and 5 Core Operating Limits Report Page I of 7

Unit 2 Cycle 16 N lur X Core Operating Limits Report Rev. 0 W AED N Page2 of 7 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for STPEGS Unit 2 Cycle 16 has been prepared in accordance with the requirements of Technical Specification 6.9.1.6. The core operating limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.6.

The Technical Specifications affected by this report are:

1) 2.1 SAFETY LIMITS

2) 2.2 LIMITING SAFETY SYSTEM SETTINGS

3) 3/4.1.1.1 SHUTDOWN MARGIN

4) 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT LIMITS

5) 3/4.1.3.5 SHUTDOWN ROD INSERTION LIMITS

6) 3/4.1.3.6 CONTROL ROD INSERTION LIMITS

7) 3/4.2.1 AFD LIMITS

8) 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR

9) 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR

10) 3/4.2.5 DNB PARAMETERS 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented below.

2.1 SAFETY LIMITS (Specification 2.1):

2.1.1 Will be added prior to Mode 2.

2.2 LIMITING SAFETY SYSTEM SETTINGS (Specification 2.2):

2.2.1 Will be added prior to Mode 2.

2.2.2 The Over-temperature AT and Over-power AT setpoint parameter values are listed below:

Over-temperature AT Setpoint Parameter Values Will be added prior to Mode 2.

Over-power AT Setpoint Parameter Values Will be added prior to Mode 2.

2.3 SHUTDOWN MARGIN (Specification 3.1.1.1):

The SHUTDOWN MARGIN shall be:

2.3.1 Will be added prior to Mode 2.

2.3.2 Greater than the limits in Figure 2 for MODES 3 and 4.

2.3.3 Greater than the limits in Figure 3 for MODE 5.

Unit 2 Cycle 16 Core Operating Limits Report Rev. 0 W E E Page 3of 7 2.4 MODERATOR TEMPERATURE COEFFICIENT (Specification 3.1.1.3):

2.4.1 Will be added prior to Mode 2.

2.4.2 Will be added prior to Mode 2.

2.4.3 Will be added prior to Mode 2.

2.4.4 Will be added prior to Mode 2.

2.5 ROD INSERTION LIMITS (Specification 3.1.3.5 and 3.1.3.6):

2.5.1 Will be added prior to Mode 2.

2.5.2 Will be added prior to Mode 2.

2.5.3 Will be added prior to Mode 2.

2.6 AXIAL FLUX DIFFERENCE (Specification 3.2.1):

2.6.1 Will be added prior to Mode 2.

2.6.2 Will be added prior to Mode 2.

2.7 HEAT FLUX HOT CHANNEL FACTOR (Specification 3.2.2):

2.7.1 Will be added prior to Mode 2.

2.7.2 Will be added prior to Mode 2.

2.7.3 Will be added prior to Mode 2.

2.7.4 Will be added prior to Mode 2.

2.8 ENTHALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3):

2.8.1 Will be added prior to Mode 2.

2.8.2 Will be added prior to Mode 2.

2.8.3 Will be added prior to Mode 2.

2.9 DNB PARAMETERS (Specification 3.2.5):

2.9.1 Will be added prior to Mode 2.

3.0 REFERENCES

3.1 Letter from J. M. Ralston (Westinghouse) to D. F. Hoppes (STPNOC), "South Texas Project Nuclear Operating Company South Texas Project Electric Generating Station Unit 2 Cycle 16 Final Reload Evaluation (RE)," ST-UB-NOC-1 1003208, November 1,2011.

3.2 NUREG-1346, Technical Specifications, South Texas Project Unit Nos. 1 and 2.

3.3 Document RSE-U2, Rev. 0, "Unit 2 Cycle 16 Reload Safety Evaluation for Modes 3, 4, and 5."

(CR Action 10-9938-85)

W Unit 2 Cycle 16 Core Operating Limits Report Rev. 0 W E, Page 4 of 7 FIGURE I Reactor Core Safety Limits - Four Loops in Operation Will be added prior to Mode 2.

Sun Unit 2 Cycle 16 Core Operating Limits Report Rev. 0 SrN Page 5of 7 Figure 2 Required Shutdown Margin for Modes 3 & 4 7.0 6.0 Acceptable (2400 2400 =1515) 5.0

/

OF

.0 001/

4.0

!E 3.0 a-2.0 I

__ I I I I I - * ~-I-----i + 1--F-I--

IUnacceptab1lej (600,1.30) 1.0 0.0 0 400 800 1200 1600 2000 2400 RCS Critical Boron Concentration (ppm)

(for ARI minus most reactive stuck rod)

Unit 2 Cycle 16 Core Operating Limits Report Rev. 0 W EA Page 6of 7 Figure 3 Required Shutdown Margin for Mode 5 7.0 6.0 5.0 4.0 g=

I-0 2.0 1.0 0.0 0 400 800 1200 1600 2000 2400 RCS Critical Boron Concentration (ppm)

(for ARI minus most reactive stuck rod)

Unit 2 Cycle 16 NleM n Core Operating Limits Report Rev. 0

ý NPage r 7of 7 FIGURE 4 MTC versus Power Level Will be added prior to Mode 2.

FIGURE 5 Control Rod Insertion Limits versus Power Level Will be added prior to Mode 2.

FIGURE 6 AFD Limits versus Power Level Will be added prior to Mode 2.

FIGURE 7 K(Z) - Normalized FQ(Z) versus Core Height Will be added prior to Mode 2.

TABLE 1 Unrodded Fxy for Each Core Height Will be added prior to Mode 2.

ATTACHMENT 2 South Texas Project Revision I Unit 2 Cycle 16 Core Operating Limits Report

Inc Pom pWany SOUTH TEXAS PROJECT Unit 2 Cycle 16 CORE OPERATING LIMITS REPORT Revision 1 Core Operating Limits Report Page I of 16

NI! MT ". mny Unit 2 Cycle 16 N14 n r Core Operating Limits Report Rev. 1 Page 2 of 16 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for STPEGS Unit 2 Cycle 16 has been prepared in accordance with the requirements of Technical Specification 6.9.1.6. The core operating limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.6.

The Technical Specifications affected by this report are:

1) 2.1 SAFETY LIMITS

2) 2.2 LIMITING SAFETY SYSTEM SETTINGS

3) 3/4.1.1.1 SHUTDOWN MARGIN

4) 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT LIMITS

5) 3/4.1.3.5 SHUTDOWN ROD INSERTION LIMITS

6) 3/4.1.3.6 CONTROL ROD INSERTION LIMITS

7) 3/4.2.1 AFD LIMITS

8) 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR

9) 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR

10) 3/4.2.5 DNB PARAMETERS 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented below.

2.1 SAFETY LIMITS (Specification 2.1):

2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (Tavg) shall not exceed the limits shown in Figure 1.

2.2 LIMITING SAFETY SYSTEM SETTINGS (Specification 2.2):

2.2.1 The Loop design flow for Reactor Coolant Flow-Low is 98,000 gpm.

Unit 2 Cycle 16 e m ny Core Operating Limits Report Rev. 1 AF* XrPage_ 3 of16 2.2.2 The Over-temperature AT and Over-power AT setpoint parameter values are listed below:

Over-temperature AT Setpoint Parameter Values t1 measured reactor vessel AT lead/lag time constant, rI = 8 sec T2 measured reactor vessel AT lead/lag time constant, T2 = 3 sec T3 measured reactor vessel AT lag time constant, 'T3 = 2 sec T4 measured reactor vessel average temperature lead/lag time constant, Tr4 = 28 sec T5 measured reactor vessel average temperature lead/lag time constant, T5 = 4 sec T6 measured reactor vessel average temperature lag time constant, T6 = 2 sec KI Overtemperature AT reactor trip setpoint, K, = 1.14 K2 Overtemperature AT reactor trip setpoint Tavg coefficient, K2 = 0.028/°F K3 Overtemperature AT reactor trip setpoint pressure coefficient, K3 = 0.00 143/psig T' Nominal full power Tavg, T'__ 592.0 IF P' Nominal RCS pressure, P' = 2235 psig f1 (AI) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(1) For q, - qb between -70% and +8%, fl(AI) = 0, where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and q, + qb is total THERMAL POWER in percent of RATED THERMAL POWER; (2) For each percent that the magnitude of qt - qb exceeds -70%, the AT Trip Setpoint shall be automatically reduced by 0.0% of its value at RATED THERMAL POWER; and (3) For each percent that the magnitude of qt - qb exceeds +8%, the AT Trip Setpoint shall be automatically reduced by 2.65% of its value at RATED THERMAL POWER.

Over-power AT Setpoint Parameter Values Ti measured reactor vessel AT lead/lag time constant, T, = 8 sec T2 measured reactor vessel AT lead/lag time constant, T2 = 3 sec T3 measured reactor vessel AT lag time constant, T3 = 2 sec T6 measured reactor vessel average temperature lag time constant, T6 = 2 sec T7 Time constant utilized in the rate-lag compensator for Tavg, T7 = 10 sec K4 Overpower AT reactor trip setpoint, K4 = 1.08 K5 Overpower AT reactor trip setpoint Tavg rate/lag coefficient, K5 = 0.02/°F for increasing average temperature, and K5 = 0 for decreasing average temperature K6 Overpower AT reactor trip setpoint Tavg heatup coefficient K6 = 0.002/°F for T>T",and K6 = 0 forT__ T" T" Indicated full power Tavg, T"__ 592.0 IF f2(AI) = 0 for all (AI)

7.mpany 1r nUnit 2 Cycle 16 Core Operating Limits Report Rev. 1 W NPage r 4 of 16 2.3 SHUTDOWN MARGIN (Specification 3.1.1.1):

The SHUTDOWN MARGIN shall be:

2.3.1 Greater than 1.3% Ap for MODES 1 and 2*

• See Special Test Exception 3.10.1 2.3.2 Greater than the limits in Figure 2 for MODES 3 and 4.

2.3.3 Greater than the limits in Figure 3 for MODE 5.

2.4 MODERATOR TEMPERATURE COEFFICIENT (Specification 3.1.1.3):

2.4.1 The BOL, ARO, MTC shall be less positive than the limits shown in Figure 4.

2.4.2 The EOL, ARO, HFP, MTC shall be less negative than -62.6 pcm/°F.

2.4.3 The 300 ppm, ARO, HFP, MTC shall be less negative than -53.6 pcm/°F (300 ppm Surveillance Limit).

Where: BOL stands for Beginning-of-Cycle Life, EOL stands for End-of-Cycle Life, ARO stands for All Rods Out, HFP stands for Hot Full Power (100% RATED THERMAL POWER),

HFP vessel average temperature is 592 'F.

2.4.4 The Revised Predicted near-EOL 300 ppm MTC shall be calculated using the algorithm from T.S. 6.9.1.6.b.10:

Revised Predicted MTC = Predicted MTC + AFD Correction - 3 pcm/°F If the Revised Predicted MTC is less negative than the COLR Section 2.4.3 limit and all of the benchmark data contained in the surveillance procedure are met, then an MTC measurement in accordance with S.R. 4.1.1.3b is not required.

2.5 ROD INSERTION LIMITS (Specification 3.1.3.5 and 3.1.3.6):

2.5.1 All banks shall have the same Full Out Position (FOP) of either 258 or 259 steps withdrawn.

2.5.2 The Control Banks shall be limited in physical insertion as specified in Figure 5.

2.5.3 Individual Shutdown bank rods are fully withdrawn when the Bank Demand Indication is at the FOP and the Rod Group Height Limiting Condition for Operation is satisfied (T.S. 3.1.3.1).

Nn I Unit 2 Cycle 16 N nompN Core Operating Limits Report Rev. 1 I1* ArPage- 5 of l6 2.6 AXIAL FLUX DIFFERENCE (Specification 3.2.1):

2.6.1 AFD limits as required by Technical Specification 3.2.1 are determined by Constant Axial Offset Control (CAOC) Operations with an AFD target band of +5, -10%.

2.6.2 The AFD shall be maintained within the ACCEPTABLE OPERATION portion of Figure 6, as required by Technical Specifications.

2.7 HEAT FLUX HOT CHANNEL FACTOR (Specification 3.2.2):

2.7.1 FQT = 2.55.

2.7.2 K(Z) is provided in Figure 7.

2.7.3 The Fxy limits for RATED THERMAL POWER (FRTP) within specific core planes shall be:

2.7.3.1 Less than or equal to 2.102 for all cycle burnups for all core planes containing Bank "D" control rods, and 2.7.3.2 Less than or equal to the appropriate core height-dependent value from Table 1 for all unrodded core planes.

2.7.3.3 PFxy = 0.2.

These Fxy limits were used to confirm that the heat flux hot channel factor FQ(Z) will be limited by Technical Specification 3.2.2 assuming the most-limiting axial power distributions expected to result for the insertion and removal of Control Banks C and D during operation, including the accompanying variations in the axial xenon and power distributions, as described in WCAP-8385. Therefore, these Fxy limits provide assurance that the initial conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10 CFR 50.46.

2.7.4 Core Power Distribution Measurement Uncertainty for the Heat Flux Hot Channel Factor 2.7.4.1 If the Power Distribution Monitoring System(PDMS) is operable, as defined in the Technical Requirements Manual Section 3.3.3.12, the core power distribution measurement uncertainty (UFQ) to be applied to the FQ(Z) and Fxy(Z) using the PDMS shall be calculated by:

UFQ = (1.0 + (UQ/100))*UE Where:

UQ = Uncertainty for power peaking factor as defined in Equation 5-19 from the document referenced by Technical Specification 6.9.1.6.b. 11 UE = Engineering uncertainty factor of 1.03.

This uncertainty is calculated and applied automatically by the BEACON computer code.

W oUnit 2 Cycle 16

, *N" Core Operating Limits Report Rev. 1 WN - Page 6 of 16 2.7.4.2 If the moveable detector system is used, the core power distribution measurement uncertainty (UFQ) to be applied to the FQ(Z) and Fxy(Z) shall be calculated by:

UFQ --= UQU*UE Where:

UQU = Base FQ measurement uncertainty of 1.05.

UE = Engineering uncertainty factor of 1.03.

2.8 ENTHALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3):

RTP 2.8.1 F = 1.62' 2.8.2 PFA = 0.3 2.8.3 Core Power Distribution Measurement Uncertainty for the Enthalpy Rise Hot Channel Factor 2.8.3.1 If the Power Distribution Monitoring System (PDMS) is operable, as defined in the Technical Requirements Manual Section 3.3.3.12, the core power distribution measurement uncertainty (UFAH) to be applied to the FN using the PDMS shall be the greater of:

UFAH = 1.04 OR UFAH = 1.0 + (UH/100)

Where:

UA = Uncertainty for power peaking factor as defined in Equation 5-19 from the document referenced in Technical Specification 6.9.1.6.b.11.

This uncertainty is calculated and applied automatically by the BEACON computer code.

2.8.3.2 If the moveable detector system is used, the core power distribution measurement uncertainty (UFAH) shall be:

UFAn = 1.04 Applies to all fuel in the Unit 2 Cycle 16 Core.

I 0Unit 2 Cycle 16

. re,,y Core Operating Limits Report Rev. 1 Page 7 of 16 2.9 DNB PARAMETERS (Specification 3.2.5):

2.9.1 The following DNB-related parameters shall be maintained within the following limits:I 2.9.1.1 Reactor Coolant System Tavg :s 595 OF 2 2.9.1.2 Pressurizer Pressure > 2200 psig 3 2.9.1.3 Minimum Measured Reactor Coolant System Flow > 403,000 gpm 4 .

3.0 REFERENCES

3.1 Letter from J. M. Ralston (Westinghouse) to D. F. Hoppes (STPNOC), "South Texas Project Nuclear Operating Company South Texas Project Electric Generating Station Unit 2 Cycle 16 Final Reload Evaluation (RE)," ST-UB-NOC-1 1003208, November 1,2011.

3.2 NUREG-1346, Technical Specifications, South Texas Project Unit Nos. 1 and 2.

3.3 STPNOC Calculation ZC-7035, Rev. 2, "Loop Uncertainty Calculation for RCS Tavg Instrumentation," Section 10.1.

3.4 STPNOC Calculation ZC-7032, Rev. 4, "Loop Uncertainty Calculation for Narrow Range Pressurizer Pressure Monitoring Instrumentation," Section 2.3, Page 9.

3.5 5Z529ZB01025 Rev. 4, Design Basis Document, Technical Specifications /LCO, Tech Spec Section 3.2.5.c.

3.6 Document RSE-U2, Rev. 1, "Unit 2 Cycle 16 Reload Safety Evaluation for Modes 1, 2, 3, 4, and 5." (CR Action 10-9938-9)

A discussion of the processes to be used to take these readings is provided in the basis for Technical Specification 3.2.5.

2 Includes a 1.9 'F measurement uncertainty per Reference 3.3.

3 Limit not applicable during either a Thermal Power ramp in excess of 5% of RTP per minute or a Thermal Power step in excess of 10% RTP. Includes a 9.6 PSI averaged measurement uncertainty as read on QDPS display per Reference 3.4.

4 Includes the most limiting flow measurement uncertainty of 2.8% from Reference 3.5.

NI Popelm Unit 2 Cycle 16 Al Ar Core Operating Limits Report Rev. 1 Page 8 of 16 Figure 1 Reactor Core Safety Limits - Four Loops in Operation 680 660 640 620 600 580 560 540 0 20 40 60 80 100 120 140 Rated Thermal Powver (%)

p ouI lUnit 2 Cycle 16 A.mpany Core Operating Limits Report Rev. 1 Page 9 of 16 Figure 2 Required Shutdown Margin for Modes 3 & 4 7.0 6.0 5.0 4.0 3.0 PC Ir Qo

.09 2.0 1.0 0.0 0 400 800 1200 1600 2000 2400 RCS Critical Boron Concentration (ppm)

(for ARI minus most reactive stuck rod)

dPIrm '-Unit 2 Cycle 16 op y Core Operating Limits Report Rev. 1 Page 10 of 16 Figure 3 Required Shutdown Margin for Mode 5 7.0 6.0 5.0 4.0

" 3.0 rA I

2.0 1.0 0.0 0 400 800 1200 1600 2000 2400 RCS Critical Boron Concentration (ppm)

(for ARI minus most reactive stuck rod)

Nu rUnit 2 Cycle 16 y

• Nebpean Core Operating Limits Report Rev. 1 Page 11 of 16 Figure 4 MTC versus Power Level 7.0 6.0 -- - -. . - -- - - - - - -

6. I_Unacceptable OperationI 5.0 -

4.0 -

[Acceptable operationj 3.0 S3.0 -

1.0-a-0.0

-1.0

-2.0

-3.0 0 10 20 30 40 50 60 70 80 90 100 Rated Thermal Power (%)

Unit 2 Cycle 16 Num Core Operating Limits Report Rev. 1

ý N-Page r 12 of 16 Figure 5 Control Rod Insertion Limits* versus Power Level 260 - ' I1(

, Step Overlap 122 )5 epver ap (78,258):12121teteOveeraap 22 258 ): 121 Step Overlap 78_258 121 Step Overlap 240 --

Bank B---

220 -- 0 200 0,202 0,74 180 ---

• " 160 rJ J 80 40 20 - -- Fully withdrawn shall he the condition where shutdown and control hanks are at the position of either 258 or 259 steps 010 20 30 40 50 60 70 80 90 100 Rated Thermal Power(%)

NU pUnit 2 Cycle 16

,. mpany Core Operating Lhnits Report Rev. 1 AW AF Nr- Page 13 of 16 Figure 6 AFD Limits versus Power Level 120 11 11 1 11 11 111 1 1 1 11 1 I I I

!I 110 100 90 I L, I I I 1 1 80 i

• A Unacceptable NX Unacceptable i Operation (-31i 0 )  ;

50 11Acceptable I Operation I-70 Operation I I I 0

964 60 2

50 40 30 20 10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (% Delta-I)

tNgW* 0Unit 2 Cycle 16 Iomy Core Operating Limits Report Rev. 1 I AF Nr- Page 14 of 16 Figure 7 K(Z) - Normalized FQ(Z) versus Core Height 1.2 111111 111111 III I 1.1 I! I I I!ii II l li l I I I I i l I  :  :  :  : l  :  : l l l l ; l l l l l l l l I I I I 1.0 11'11 I

!i i i i i i i i i ! ' I ii I I i Ii i i i i i i t  ; . I, ,I ,I . I , I, , ,

, . ,- I 0.9 I lqll ~li il li i i i i i i i i i i i i i ... i i i i i i l l ~ l bl~.i.i.i i 0.8 II II 111111111 I II 11111.111 1111111 liii 11111111111] 111111111 0.7 0.6 CoreElev. (ft FQ K(Z) 0.

1 0.0 2.55 1.0-S7.0 2.55 1.0

.0.5

!14.0 2.359 0.925 0.4 0.3 A 0.2 0.1 1' -

I LIIII~ E I I I I I I I E! IIIF 1 I I I iI l lI~ llI I I J - -

iii ~i~ i ! l~ i l ~l~ ~l i !~~~ - 1!i11111i 1i i LLL!illi 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Core Height (ft)

NAr- Ing Unit 2 Cycle 16 e , r Core Operating Limits Report Rev. 1 Page 15 of 16 Table 1 (Part 1 of 2)

Unrodded Fy for Each Core Height for Cycle Burnups Less Than 10000 MWD/MTU Core Height Axial Unrodded Core Height Axial Unrodded (Ft.) Point Fxy (Ft.) Point Fxy 14.0 1 4.337 6.8 37 1.957 13.8 2 3.807 6.6 38 1.953 13.6 3 3.277 6.4 39 1.947 13.4 4 2.747 6.2 40 1.943 13.2 5 2.420 6.0 41 1.942 13.0 6 2.157 5.8 42 1.941 12.8 7 2.122 5.6 43 1.942 12.6 8 2.078 5.4 44 1.945 12.4 9 2.042 5.2 45 1.950 12.2 10 2.006 5.0 46 1.955 12.0 11 1.982 4.8 47 1.962 11.8 12 1.965 4.6 48 1.965 11.6 13 1.956 4.4 49 1.963 11.4 14 1.945 4.2 50 1.959 11.2 15 1.931 4.0 51 1.955 11.0 16 1.914 3.8 52 1.951 10.8 17 1.904 3.6 53 1.948 10.6 18 1.898 3.4 54 1.950 10.4 19 1.894 3.2 55 1.948 10.2 20 1.898 3.0 56 1.946 10.0 21 1.906 2.8 57 1.945 9.8 22 1.916 2.6 58 1.942 9.6 23 1.925 2.4 59 1.940 9.4 24 1.935 2.2 60 1.941 9.2 25 1.943 2.0 61 1.934 9.0 26 1.950 1.8 62 1.920 8.8 27 1.958 1.6 63 1.903 8.6 28 1.967 1.4 64 1.913 8.4 29 1.986 1.2 65 1.911 8.2 30 2.007 1.0 66 1.934 8.0 31 2.022 0.8 67 2.156 7.8 32 2.028 0.6 68 2.571 7.6 33 2.012 0.4 69 3.082 7.4 34 1.998 0.2 70 3.593 7.2 35 1.982 0.0 71 4.105 7.0 36 1.967

NIN Unit 2 Cycle 16 Nl n rm Core Operating Limits Report Rev. 1 Page 16 of 16 Table 1 (Part 2 of 2)

Unrodded Fxy for Each Core Height for Cycle Burnups Greater Than or Equal to 10000 MWD/MTU Core Height Axial Unrodded Core Height Axial Unrodded (Ft.) Point Fxy (Ft.) Point Fxy 14.00 1 4.109 6.80 37 2.116 13.80 2 3.688 6.60 38 2.116 13.60 3 3.268 6.40 39 2.118 13.40 4 2.847 6.20 40 2.118 13.20 5 2.559 6.00 41 2.118 13.00 6 2.308 5.80 42 2.115 12.80 7 2.213 5.60 43 2.109 12.60 8 2.134 5.40 44 2.100 12.40 9 2.071 5.20 45 2.087 12.20 10 2.030 5.00 46 2.074 12.00 11 2.020 4.80 47 2.063 11.80 12 2.013 4.60 48 2.052 11.60 13 2.010 4.40 49 2.039 11.40 14 2.011 4.20 50 2.025 11.20 15 2.014 4.00 51 2.009 11.00 16 2.020 3.80 52 1.997 10.80 17 2.022 3.60 53 1.986 10.60 18 2.023 3.40 54 1.977 10.40 19 2.025 3.20 55 1.960 10.20 20 2.042 3.00 56 1.938 10.00 21 2.065 2.80 57 1.909 9.80 22 2.092 2.60 58 1.877 9.60 23 2.106 2.40 59 1.847 9.40 24 2.110 2.20 60 1.818 9.20 25 2.109 2.00 61 1.806 9.00 26 2.103 1.80 62 1.799 8.80 27 2.099 1.60 63 1.798 8.60 28 2.096 1.40 64 1.809 8.40 29 2.095 1.20 65 1.851 8.20 30 2.095 1.00 66 1.927 8.00 31 2.096 0.80 67 2.085 7.80 32 2.100 0.60 68 2.333 7.60 33 2.106 0.40 69 2.626 7.40 34 2.111 0.20 70 2.919 7.20 35 2.114 0.00 71 3.212 7.00 36 2.115