NOC-AE-03001488, Cycle 11, Revisions 3 & 4, & South Texas Project Unit 2 Cycle 10, Revision 1, Core Operating Limits Reports

Cycle 11, Revisions 3 & 4, & South Texas Project Unit 2 Cycle 10, Revision 1, Core Operating Limits Reports

ML030780031
Person / Time
Site:	South Texas
Issue date:	03/12/2003
From:	Leazar D South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
G25, NOC-AE-03001488, STI: 31574276, TAC MB5160, TAC MB5161
Download: ML030780031 (44)

Text

Nuclear Operating Company South Ts PoiqctEktdric GratingStation PO. Box 289 adswuth, T=5s77483

• March 12,2003 NOC-AE-03001488 File No.: G25 10CFR50.36 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Unit 1 Cycle 11, Revisions 3 and 4, and Unit 2 Cycle 10, Revision 1, Core Operating Limits Reports

Reference:

Letter from Mohan C. Thadani to William T. Cottle, "South Texas Project, Units 1 and 2

- Issuance of Amendments Approving Technical Specification Changes Revising the End of Life Moderator Temperature Coefficient Surveillance Requirements (TAC Nos.

MB5160 and MB5161)", dated November 26, 2002 (ST-AE-NOC-02001002)

In accordance with Technical Specification 6.9.1.6.d, the attached Core Operating Limits Reports (COLR) are submitted for South Texas Unit 1 Cycle 1l(revisions 3 and 4) and Unit 2 Cycle 10 (revision 1).

The Unit 1 Cycle I1 (revision 3) and Unit 2 Cycle 10 (revision 1) reports are a result of License Amendments 150/138 which relocated the shutdown margin limits from Technical Specification 3/4.1.1 to the COLR. The Unit 2 COLR also includes the changes to the end-of-life moderator temperature coefficient surveillance requirements approved in the above reference. Bars in the margins indicate the revised entries.

Subsequently, an error was discovered in the Unit 1 Cycle 11 (revision 3) COLR. In section 2.7.1, Heat Flux Hot Channel Factor, FxyRTr should be FQRTP. The error initially appeared in revision 1 of the Unit 1 Cycle 11 COLR which was sent to the NRC on May 13, 2002. The error was immediately corrected in the Unit 1 Cycle 11 COLR (revision 4). Both revisions are included in this transmittal.

If there are any questions concerning this report, please contact Scott Head at (361) 972-7136 or me at (361) 972-7795.

-7;>David A. Leazar Director, Nuclear Fuel & Analysis kaw Attachments: 1. Unit 1 Cycle 11, Revision 3, Core Operating Limits Report

2. Unit 1 Cycle 11, Revision 4, Core Operating Limits Report

3. Unit 2 Cycle 10, Revision 1, Core Operating Limits Report O:\Wp\NI\Nrc-ap\Misc-03\03001488 (UICI1 revs 3and 4 and U2C10 revlCOLRs) .doc STI:31574276

NOC-AE-03001488 Page 2 cc:

(paper copy) (electronic copy)

Ellis W. Merschoff A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 L. D. Blaylock/W. C. Gunst Arlington, Texas 76011-8064 City Public Service U. S. Nuclear Regulatory Commission Mohan C. Thadani Attention: Document Control Desk U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike R. L. Balcom Rockville, MD 20852 Texas Genco, LP Richard A. Ratliff A. Ramirez Bureau of Radiation Control City of Austin Texas Department of Health 1100 West 49th Street C. A. Johnson Austin, TX 78756-3189 AEP Texas Central Company Cornelius F. O'Keefe Jon C. Wood U. S. Nuclear Regulatory Commission Matthews & Branscomb P. 0. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 O:\Wp\NI\Nrc-ap\Misc-03\03001488 (UlCI 1 rev3 and U2CIO revlCOLRs) .doc STI:31574276

SOUTH TEXAS PROJECT UNIT 1 CYCLE 11 CORE OPERATING LIMITS REPORT REVISION 3 March 2003 I

South Texas Unit 1 Cycle 11, Revision 3 March 2003 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for STPEGS Unit 1 Cycle 11 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.

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

2

South Texas Unit I Cycle 11, Revision 3 March 2003 Over-temperature AT Setpoint Parameter Values "t1 measured reactor vessel AT lead/lag time constant, t 1 = 8 sec

• E2 measured reactor vessel AT lead/lag time constant, T2 = 3 see

'r3 measured reactor vessel AT lag time constant, r3 = 0 see t4 measured reactor vessel average temperature lead/lag time constant, t4 = 28 sec t5 measured reactor vessel average temperature lead/lag time constant, ¶5 = 4 see "T6 measured reactor vessel average temperature lag time constant, '6 = 0 see K1 Overtemperature AT reactor trip setpoint, K1 = 1.14 K2 Overtemperature AT reactor trip setpoint Tavg coefficient, K 2 = 0.028/IF K3 Overtemperature AT reactor trip setpoint pressure coefficient, K3 = 0.00143/psig T' Nominal full power Tavg, T' __592.0 OF P' Nominal RCS pressure, P' = 2235 psig fl(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, - q, between -70% and +8%, fl(AI) = 0, where q, and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL POWER in percent of RATED THERMAL POWER; (2) For each percent that the magnitude of q,- qb exceeds -70%, the AT Trip Setpoint shall be automatically reduced by 0.0% of its value at RATED THERMAL POWER.

(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

"-r measured reactor vessel AT lead/lag time constant, T1 = 8 sec

"-2 measured reactor vessel AT lead/lag time constant, r2 = 3 see T3 measured reactor vessel AT lag time constant, T3 = 0 see T6 measured reactor vessel average temperature lag time constant, r6 = 0 see T7 Time constant utilized in the rate-lag compensator for Tavg, E7 10 see 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 K 6 = 0.002/7F for T > T" and, K6 = 0 for T < T" T" Indicated full power Tavg, T" < 592.0 °F f2 (AI) = 0 for all (AI) 2.3 SHUTDOWN MARGIN (Specification 3.1.1.1):

The SHUTDOWN MARGIN shall be:

2.3.1 Greater than 1.3% Ap for MODES l 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.

3

South Texas Unit I Cycle 11, Revision 3 March 2003 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, IIFP, MTC shall be less negative than -61.2 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 S.R. 4.1.1.3b 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 at least 250 steps withdrawn but not exceeding 259 steps withdrawn.

2.5.2 The Control Banks shall be limited in physical insertion as specified in Figure 5. 1 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).

2.6 AX[AL FLUX DIFFERENCE (Specification 3.2.1):

2.6.1 AFD limits as required by Technical Specification 3.2.1 are determined by 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 BLEAT FLUX HOT CHANNEL FACTOR (Specification 3.2.2):

2.7.1 FkTP = 2.55.

2.7.2 K(Z) is provided in Figure 7.

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

2.7.3.1 Less than or equal to 2.102 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.

4

South Texas Unit I Cycle 11, Revision 3 March 2003 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.

For Unit 1 Cycle 11, the L(Z) penalty is not applied (i.e., L(Z) = 1.0 for all core elevations).

2.8 ENTHALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3):

2.8.1 WITHOUT RCS Loop-specific Temperature Calibrations:

Standard Fuell FMTP = 1.46 VANTAGE 5H / RFA Fuel2 F P = 1.53 WITH RCS Loop-specific Temperature Calibrations:

Standard Fuel 1 FgtTP = 1.49 VANTAGE 5H / RFA Fuel 2 FMP = 1.557 2.8.2 Standard Fuel / VANTAGE 5H / RFA Fuel PFm = 0.3 2.9 DNB PARAMETERS (Specification 3.2.5):

2.9.1 The following DNB-related parameters shall be maintained within the following limits:

a. Reactor Coolant System Tavg, _*595 'F4,

b. Pressurizer Pressure, > 2200 psig 5 ,

c. Minimum Measured Reactor Coolant System Flow > 403,000 gpm 6 .

3.0 REFERENCES

3.1 Letter from T. D. Croyle (Westinghouse) to Dave Hoppes (STPNOC), "Unit 1 Cycle 11 Rev. 2 Final Core Operating Limits Report (COLR) to Support a 1.4% Uprating," NF-TG-02-32 (ST-UB-NOC-02002248),

May 2002.

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

3.3 STPNOC Calculation ZC-7035, Rev. 1, "Loop Uncertainty Calculation for RCS Tavg Instrumentation,"

October 19, 1998.

3.4 STPNOC Calculation ZC-7032, Rev. 3, "Loop Uncertainty Calculation for Narrow Range Pressurizer Pressure Monitoring Instrumentation," June 27, 2001.

1 Applies to Region 5.

2 Applies to Regions 10A, 1IA, 1IB, 12A, 13A and 13B.

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

4 Includes a 1.9 IF measurement uncertainty.

5 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 10.7 psi measurement uncertainty as read on the QDPS display per Reference 3.4.

6 Includes a 2.8% flow measurement uncertainty.

5

South Texas Unit I Cycle 11, Revision 3 March 2003 Figure 1 Reactor Core Safety Limits - Four Loops in Operation 680 660 640

, 620 U 600 580 560 540 0 20 40 60 80 100 120 140 Rated Thermal Power (%)

6

South Texas Unit I Cycle 11, Revision 3 March 2003 Figure 2 Required Shutdown Margin for Modes 3 & 4 0ý 0

0 0

N 0

0 o

o °0.)

N C.

0~

C 000 Cq.)

0 I

0 o .)

0~

0=

0ý 9ý 9ýCý 0 0 0 CD Required Shutdown Margin

(%Delta Rho) 7

South Texas Unit 1 Cycle 11, Revision 3 March 2003 Figure 3 Required Shutdown Margin for Mode 5 0,

0 0

0 r-4 0

- M o 0 00 0

0 0

cc r D  % I ý r - C5 Required Shutdown Margin

(% Delta Rho) 8

South Texas Unit 1 Cycle 11, Revision 3 March 2003 Figure 4 MTC versus Power Level 7.0 6.0 5.0 4.0 U,,,

3.0 I

0

,6, 2.0 1.0 0.0

-1.0

-2.0

-3.0 0 20 40 60 80 100 Rated Thermal Power (%)

9

South Texas Unit 1 Cycle 11, Revision 3 March 2003 Figure 5 Control Rod Insertion Limits* versus Power Level (23,259) 122 Step Overlap (79,259) 122 Step Overlap (23, 258) 121 Step Overlap (79,258) 121 Step Overlap 260 (22, 256) 119 Step Overlap (78,256) 119 Step Overlap (21,254) 117 Step Overlap (77,254) 117 Step Overlap li ~iVi ThzHIH  ;,)

VIK '119C r

• ap*

(19, 250) 113 Step Overlap (75,250) 113 Step Ove erlap 240 220 (2 25115SeOel

-f( 00 174)i 200 Lan .. Ban .C

- B Ban ~ a 180 A i ii i i i L 07 160 Bank I

140 OFI (0,65) 1, EI IF_

120 0 100 (29.0) 4t 80 60 40 20 0

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

"Control Bank A is already withdrawn to Full Out Position Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of 250 and :59 steps withdrawn, inclusive.

10

South Texas Unit I Cycle 11, Revision 3 March 2003 Figure 6 AFD Limits versus Rated Thermal Power 120 100 80 0

60 40 20 0

-50 -30 -10 10 30 50 Axial Flux Difference (A I) 11

South Texas Unit I Cycle 11, Revision 3 March 2003 Figure 7 K(Z) - Normalized FQ(Z) versus Core Height 1.2 1.0 N

k_

.8 0

tM

.6 N Core Elevation (ft) FQ K(Z)

.4 0.0 2.55 1.0 E 7.0 2.55 1.0 Z 14.0 2.359 0.925

.2 0

0.0 7.0 14.0 Core Height (ft) 12

South Texas Unit 1 Cycle 11, Revision 3 March 2003 Table 1 Unrodded Fxy for Each Core Height*

For Cycle Burnups Less Than 9000 MWIJ/MTU Core Height Axial Unrodded Core Height Axial Unrodded (Ft.) Point Fxy (Ft.) Point Fxy 14.UU 1 5.123 6.80 37 1.948 13.80 2 4.303 6.60 38 1.932 13.60 3 3.482 6.40 39 1.920 13.40 4 2.661 6.20 40 1.909 13.20 5 2.291 6.00 41 1.898 13.00 6 2.061 5.80 42 1.894 12.80 7 2.096 5.60 43 1.895 12.60 8 2.092 5.40 44 1.894 12.40 9. 2.082 5.20 45 1.896 12.20 10 2.057 5.00 46 1.900 12.00 11 2.027 4.80 47 1.907 11.80 12 2.007 4.60 48 1.916 11.60 13 2.002 4.40 49 1.924 11.40 14 2.002 4.20 50 1.929 11.20 15 2.001 4.00 51 1.933 11.00 16 1.999 3.80 52 1.933 10.80 17 1.994 3.60 53 1.926 10.60 18 1.990 3.40 54 1.922 10.40 19 1.986 3.20 55 1.915 10.20 20 1.985 3.00 56 1.901 10.00 21 1.985 2.80 57 1.886 9.80 22 1.986 2.60 58 1.854 9.60 23 1.988 2.40 59 1.816 9.40 24 1.989 2.20 60 1.774 9.20 25 1.990 2.00 61 1.755 9.00 26 1.991 1.80 62 1.744 8.80 27 1.994 1.60 63 1.740 8.60 28 1.999 1.40 64 1.735 8.40 29 2.007 1.20 65 1.744 8.20 30 2.016 1.00 66 1.780 8.00 31 2.024 0.80 67 1.933 7.80 32 2.032 0.60 68 2.351 7.60 33 2.030 0.40 69 2.901 7.40 34 2.006 0.20 70 3.451 7.20 35 1.980 0.00 71 4.001 7.00 36 1.962

• For Unit 1 Cycle 11, the L(Z) penalty is not applied (i.e., L(Z) = 1.0 for all core elevations).

13

South Texas Unit I Cycle 11, Revision 3 March 2003 Table 2 Unrodded FXy for Each Core Height*

For Cycle Burnups Greater Than or Equal to 9000 MWD/MTU Core Height Axial Unrodded Core Height Axial Unrodded (Ft.) Point Fxy (Ft.) Point Fxy 14.00 1 5.186 6.80 37 2.125 13.80 2 4.443 6.60 38 2.122 13.60 3 3.665 6.40 39 2.112 13.40 4 2.858 6.20 40 2.101 13.20 5 2.456 6.00 41 2.088 13.00 6 2.180 5.80 42 2.075 12.80 7 2.153 5.60 43 2.063 12.60 8 2.109 5.40 44 2.051 12.40 9 2.082 5.20 45 2.041 12.20 10 2.072 5.00 46 2.031 12.00 11 2.053 4.80 47 2.023 11.80 12 2.035 4.60 48 2.016 11.60 13 2.031 4.40 49 2.006 11.40 14 2.034 4.20 50 1.995 11.20 15 2.036 4.00 51 1.982 11.00 16 2.038 3.80 52 1.970 10.80 17 2.039 3.60 53 1.958 10.60 18 2.040 3.40 54 1.947 10.40 19 2.040 3.20 55 1.936 10.20 20 2.038 3.00 56 1.924 10.00 21 2.037 2.80 57 1.911 9.80 22 2.036 2.60 58 1.879 9.60 23 2.039 2.40 59 1.852 9.40 24 2.045 2.20 60 1.841 9.20 25 2.053 2.00 61 1.831 9.00 26 2.057 1.80 62 1.820 8.80 27 2.059 1.60 63 1.813 8.60 28 2.060 1.40 64 1.827 8.40 29 2.065 1.20 65 1.815 8.20 30 2.074 1.00 66 1.822 8.00 31 2.085 0.80 67 2.066 7.80 32 2.096 0.60 68 2.542 7.60 33 2.105 0.40 69 3.117 7.40 34 2.114 0.20 70 3.656 7.20 35 2.121 0.00 71 4.121 7.00 36 2.125

• For Unit I Cycle 11, the L(Z) penalty is not applied (i.e., L(Z) = 1.0 for all core elevations).

14

SOUTH TEXAS PROJECT UNIT I CYCLE 11 CORE OPERATING LIMITS REPORT REVISION 4 March 2003 I

South Texas Unit 1 Cycle 11, Revision 4 March 2003 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for STPEGS Unit I Cycle 11 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.

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

2

South Texas Unit I Cycle 11, Revision 4 March 2003 Over-temperature AT Setpoint Parameter Values T1 measured reactor vessel AT lead/lag time constant, rl = 8 sec T2 measured reactor vessel AT lead/lag time constant, T2 = 3 sec T3 measured reactor vessel AT lag time constant, T3 = 0 sec T4 measured reactor vessel average temperature lead/lag time constant, E4 = 28 sec T5 measured reactor vessel average temperature lead/lag time constant, 'r5 = 4 sec T6 measured reactor vessel average temperature lag time constant, "r6 =0 sec K1 Overtemperature AT reactor trip setpoint, Kj = 1.14 K2 Overtemperature AT reactor trip setpoint Tavg coefficient, K2 = 0.028/°F K3 Overtemperature AT reactor trip setpoint pressure coefficient, K3 = 0.00143/psig T' Nominal full power Tavg, T' < 592.0 'F P' Nominal RCS pressure, P' = 2235 psig fl(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 q% 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 - q, exceeds -70%, the AT Trip Setpoint shall be automatically reduced by 0.0% of its value at RATED THERMAL POWER.

(3) For each percent that the magnitude of qt - q, 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

'r I measured reactor vessel AT lead/lag time constant, lI = 8 sec T2 measured reactor vessel AT lead/lag time constant, T2 = 3 sec T3 measured reactor vessel AT lag time constant, C3 = 0 sec T6 measured reactor vessel average temperature lag time constant, '6 = 0 sec "T7 Time constant utilized in the rate-lag compensator for Tavg, 'r7 = 10 sec K4 Overpower AT reactor trip setpoint, K4 = 1.08 K5 Overpower AT reactor trip setpoint Tavg rate/lag coefficient, K 5 = 0.02/°F for increasing average temperature, and K5 = 0 for decreasing average temperature K6 Overpower AT reactor trip setpoint Tavg heatup coefficient K6 0.002/7F for T > T" and, K6 = 0 for T < T" T" Indicated full power Tavg, T" < 592.0 'F f 2 (AI) = 0 for all (AI) 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.

3

South Texas Unit I Cycle 11, Revision 4 March 2003 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 -61.2 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/0 F If the Revised Predicted MTC is less negative than the S.R. 4.1.1.3b 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 at least 250 steps withdrawn but not exceeding 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).

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 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 F-w = 2.55.

2.7.2 K(Z) is provided in Figure 7.

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

2.7.3.1 Less than or equal to 2.102 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.

4

South Texas Unit I Cycle 11, Revision 4 March 2003 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.

For Unit 1 Cycle 11, the L(Z) penalty is not applied (i.e., L(Z) = 1.0 for all core elevations).

2.8 ENTHALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3):

2.8.1 WITHOUT RCS Loop-specific Temperature Calibrations:

Standard Fuel1 FR- = 1.46 VANTAGE 5H / RFA Fuel 2 Py = 1.53 WITH RCS Loop-specific Temperature Calibrations:

Standard Fuel1 FI,, = 1.49 VANTAGE 5H / RFA Fuel 2 PF = 1.557 2.8.2 Standard Fuel / VANTAGE 5H / RFA Fuel PFAH = 0.3 2.9 DNB PARAMETERS (Specification 3.2.5):

2.9.1 The following DNB-related parameters shall be maintained within the following limitsý3

a. Reactor Coolant System Tavg, < 595 'F4,

b. Pressurizer Pressure, > 2200 psig 5 ,

c. Minimum Measured Reactor Coolant System Flow > 403,000 gpm 6 .

3.0 REFERENCES

3.1 Letter from T. D. Croyle (Westinghouse) to Dave Hoppes (STPNOC), "Unit 1 Cycle 11 Rev. 2 Final Core Operating Limits Report (COLR) to Support a 1.4% Uprating," NF-TG-02-32 (ST-UB-NOC-02002248),

May 2002.

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

3.3 STPNOC Calculation ZC-7035, Rev. 1, "Loop Uncertainty Calculation for RCS Tavg Instrumentation,"

October 19, 1998.

3.4 STPNOC Calculation ZC-7032, Rev. 3, "Loop Uncertainty Calculation for Narrow Range Pressurizer Pressure Monitoring Instrumentation," June 27, 2001.

1 Applies to Region 5.

2 Applies to Regions 10A, llA, liB, 12A, 13A and 13B.

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

4 Includes a 1.9 'F measurement uncertainty.

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 10.7 psi measurement uncertainty as read on the QDPS display per Reference 3.4.

6 Includes a 2.8% flow measurement uncertainty.

5

South Texas Unit 1 Cycle 11, Revision 4 March 2003 I

Figure 1 Reactor Core Safety Limits - Four Loops in Operation 680 660 640 0 620 S600 580 560 540 0 20 40 60 80 100 120 140 Rated Thermal Power (%)

6

South Texas Unit I Cycle 11, Revision 4 March 2003 Figure 2 Required Shutdown Margin for Modes 3 & 4 C0 C)

C>

oCz 0

0 C.) U C~4 U V C: 0 0

C1 U

94*

o 0

0 Oý 0ý 0 0 0 0) 0C 0 00 r- kn rti ( -

Required Shutdown Margin

(%Delta Rho) 7

South Texas Unit 1 Cycle 11, Revision 4 March 2003 Figure 3 Required Shutdown Margin for Mode 5 0~

0 0

0 oi Or I.-)

0.)

0ý I=

0 Required Shutdown Margin

(% Delta Rho) 8

South Texas Unit 1 Cycle 11, Revision 4 March 2003 SoutReisio Texs 4Uit ICyce 11 arch200 Figure 4 MTC versus Power Level 7.0 6.0 Unacceptable Operation E.

0 5.0 4.0 3.0 Acceptable OperationJ 0,, 2.0 U

1.0 0.0

-1.0 + + 4 4 4

-2.0

-3.0 0 20 40 60 80 100 Rated Thermal Power (%)

9

South Texas Unit 1 Cycle 11, Revision 4 March 2003 I

Figure 5 Control Rod Insertion Limits* versus Power Level (23,259) 122 Step Overlap (79,259) 122 Step Overlap (23, 258) 121 Step Overlap (79,258) 121 Step Overlap 260 (22, 256) 119 Step Overlap (78,256) 119 Step Overlap 1(21,254) 117 Step Overlap (20,252) 115 Step Overlap FI I I I I 1"F4 __1 (77,254) 117 Step Overlap (76, 252) 115 Step Overlap J(19,250) 113 Step Overlap I I '-mlI 240 (75, 250) 113 Step Overlap

• ank B 220 200 180 t 160 Bank C

- 0(0,14 - - --

• = 140 0

• 120

• 100 xz Bank D

• 0 60 (0, 65) 11 - -- - - -

40 1 ([_.

20

,

• or , ,

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

"Control Bank A is already withdrawn to Full Out Position Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of 250 and :'59 steps withdrawn, inclusive 10

South Texas Unit I Cycle 11, Revision 4 March 2003 Figure 6 AFD Limits versus Rated Thermal Power 120 100 I-. 80 X0 60 40 20 0

-50 -30 -10 10 30 50 Axial Flux Difference (A 1) 11

South Texas Unit I Cycle 11, Revision 4 March 2003 South Texas Unit I Cycle 11, Revision 4 March 2003 Figure 7 K(Z) - Normalized FQ(Z) versus Core Height 1.2 1.0

.8 0

14.'

CD CU 0)

.6 Core Elevation (ft) FQ K(Z)

N

.4 0.0 2.55 1.0 0u E 7.0 2.55 1.0 Z 14.0 2.359 0.925

.2 0

0.0 7.0 14.0 Core Height (ft) 12

South Texas Unit I Cycle 11, Revision 4 March 2003 Table 1 Unrodded Fxy for Each Core Height*

For Cycle Burnups Less Than 9000 MWD/MTU Core Height Axial Unrodded Core Height Axial Unrodded (Ft.) Point Fxy (Ft.) Point Fxy 14.00 1 5.123 6.80 37 1.948 13.80 2 4.303 6.60 38 1.932 13.60 3 3.482 6.40 39 1.920 13.40 4 2.661 6.20 40 1.909 13.20 5 2.291 6.00 41 1.898 13.00 6 2.061 5.80 42 1.894 12.80 7 2.096 5.60 43 1.895 12.60 8 2.092 5.40 44 1.894 12.40 9 2.082 5.20 45 1.896 12.20 10 2.057 5.00 46 1.900 12.00 11 2.027 4.80 47 1.907 11.80 12 2.007 4.60 48 1.916 11.60 13 2.002 4.40 49 1.924 11.40 14 2.002 4.20 50 1.929 11.20 15 2.001 4.00 51 1.933 11.00 16 1.999 3.80 52 1.933 10.80 17 1.994 3.60 53 1.926 10.60 18 1.990 3.40 54 1.922 10.40 19 1.986 3.20 55 1.915 10.20 20 1.985 3.00 56 1.901 10.00 21 1.985 2.80 57 1.886 9.80 22 1.986 2.60 58 1.854 9.60 23 1.988 2.40 59 1.816 9.40 24 1.989 2.20 60 1.774 9.20 25 1.990 2.00 61 1.755 9.00 26 1.991 1.80 62 1.744 8.80 27 1.994 1.60 63 1.740 8.60 28 1.999 1.40 64 1.735 8.40 29 2.007 1.20 65 1.744 8.20 30 2.016 1.00 66 1.780 8.00 31 2.024 0.80 67 1.933 7.80 32 2.032 0.60 68 2.351 7.60 33 2.030 0.40 69 2.901 7.40 34 2.006 0.20 70 3.451 7.20 35 1.980 0.00 71 4.001 7.00 36 1.962

• For Unit 1 Cycle 11, the L(Z) penalty is not applied (i.e., L(Z) = 1.0 for all core elevations).

13

South Texas Unit I Cycle 11, Revision 4 March 2003 South Texas Unit 1 Cycle 11, Revision 4 March 2003 Table 2 Unrodded FXy for Each Core Height*

For Cycle Burnups Greater Than or Equal to 9000 MWD/MTU Core Height Axial Unrodded Core Height Axial Unrodded (Ft.) Point Fxy (Ft.) Point Fxy 14.00 1 5.186 6.80 37 2.125 13.80 2 4.443 6.60 38 2.122 13.60 3 3.665 6.40 39 2.112 13.40 4 2.858 6.20 40 2.101 13.20 5 2.456 6.00 41 2.088 13.00 6 2.180 5.80 42 2.075 12.80 7 2.153 5.60 43 2.063 12.60 8 2.109 5.40 44 2.051 12.40 9 2.082 5.20 45 2.041 12.20 10 2.072 5.00 46 2.031 12.00 11 2.053 4.80 47 2.023 11.80 12 2.035 4.60 48 2.016 11.60 13 2.031 4.40 49 2.006 11.40 14 2.034 4.20 50 1.995 11.20 15 2.036 4.00 51 1.982 11.00 16 2.038 3.80 52 1.970 10.80 17 2.039 3.60 53 1.958 10.60 18 2.040 3.40 54 1.947 10.40 19 2.040 3.20 55 1.936 10.20 20 2.038 3.00 56 1.924 10.00 21 2.037 2.80 57 1.911 9.80 22 2.036 2.60 58 1.879 9.60 23 2.039 2.40 59 1.852 9.40 24 2.045 2.20 60 1.841 9.20 25 2.053 2.00 61 1.831 9.00 26 2.057 1.80 62 1.820 8.80 27 2.059 1.60 63 1.813 8.60 28 2.060 1.40 64 1.827 8.40 29 2.065 1.20 65 1.815 8.20 30 2.074 1.00 66 1.822 8.00 31 2.085 0.80 67 2.066 7.80 32 2.096 0.60 68 2.542 7.60 33 2.105 0.40 69 3.117 7.40 34 2.114 0.20 70 3.656 7.20 35 2.121 0.00 71 4.121 7.00 36 2.125

• For Unit 1 Cycle 11, the L(Z) penalty is not applied (i.e., L(Z) = 1.0 for all core elevations).

14

Nuclear Operating Company

- N NF SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION UNIT 2 CYCLE 10 CORE OPERATING LIMITS REPORT Revision 1 March 2003 Core Operating Limits Report Page I

SOUTH TEXAS UNIT 2 CYCLE 10, REVISION I MARCH2003 1.0 CORE OPERATING LUMITS REPORT This Core Operating Limits Report for STPEGS Unit 2 Cycle 10 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.

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

Core Operating Limits Report Page 2

-J-"

SOUTH TEXAS UNIT 2 CYCLE 10, REVISION 1 MARCH2003 Over-temperature AT Setpoint Parameter Values T1 measured reactor vessel AT lead/lag time constant, "t1= 8 sec T2 measured reactor vessel AT lead/lag time constant, T2 = 3 see T3 measured reactor vessel AT lag time constant, T3 = 0 see T4 measured reactor vessel average temperature lead/lag time constant, t4 = 28 see

-15 measured reactor vessel average temperature lead/lag time constant, t5 = 4 see 76 measured reactor vessel average temperature lag time constant, 'r6 = 0 see K1 Overtemperature AT reactor trip setpoint, K1 = 1.14 K2 Overtemperature AT reactor trip setpoint Tavg coefficient, K2 = 0.028/7F K3 Overtemperature AT reactor trip setpoint pressure coefficient; K3 = 0.00143/psig T' Nominal full power Tavg, T' < 592.0 °F 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,- q,between -70% and +8%, fi(Al) = 0, where q, and q1 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 q,- 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 1I measured reactor vessel AT lead/lag time constant, rl = 8 see "T2 measured reactor vessel AT lead/lag time constant, t2 = 3 see T3 measured reactor vessel AT lag time constant, T3 = 0 see t6 measured reactor vessel average temperature lag time constant, .6 = 0 see "T7 Time constant utilized in the rate-lag compensator for Tavg, t7 10 see K4 Overpower AT reactor trip setpoint, K4 = 1.08 K5 Overpower AT reactor trip setpoint Tavg rate/lag coefficient, K5 = 0.02/7F for increasing average temperature, and K 5 = 0 for decreasing average temperature K6 Overpower AT reactor trip setpoint Tavg heatup coefficient K6 = 0.002/°F for T > T", and K6 = 0 for T < T" T1 Indicated full power Tavg, T" <5 592.0 'F f 2 (AI) = 0 for all (AM) 2.3 SHUTDIOWN MARGIN (Specification 3.1.1.1):

The SHUTDOWN MARGIN shall be:

2.3.1 Greater than 1.3% Ap for MODES 1 and2*

• 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.

Core Operating Limits Report Page 3

SouTH TEXAs UNrr2 CYCLE 10, REVISION I MARCH2003 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 inFigure 4.

2.4.2 The EOL, ARO, HFP, MTC shall be less negative than -61.2 pcnIpF.

2.4.3 The 300 ppm, ARO, HFP, MTC shall be less negative than -53.6 pcm/IF (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 IF.

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 + AID Correction - 3 pcm/0 F If the Revised Predicted MTC is less negative than the S.R. 4.1.1.3b 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 at least 250 steps withdrawn but not exceeding 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).

2.6 AXTIL FLUX DIFFERENCE (Specification 3.2.1):

2.6.1 AFD limits as required by Technical Specification 3.2.1 are determined by 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.

Core Operating Limits Report Page 4

SOUTH TEXAS UNIT 2 CYCLE 10, REVISION I MARCH 2003 2.7 hEAT FLUX HOT CHANNEL FACTOR (Specification 3.2.2):

2.7.1 FQRTP = 2.55.

2.7.2 K(Z) is provided in Figure 7.

2.7.3 The Fx, limits for RATED THERMAL POWER (FxyRTP) 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 factorFQ(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, theseFxy 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.

2.8 ENqTALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3):

2.8.1 FAHRTP = 1.5571 2.8.2 PFAH = 0.3 2.9 DNB PARAMETERS (Specification 3.2.5):

2.9.1 The following DNB-related parameters shall be maintained within the following limits.

a. Reactor Coolant System Tavg, _<595 'F 3 ,

b. Pressurizer Pressure, > 2200 psig 4 ,

c. Minimum Measured Reactor Coolant System Flow5 > 403,000 gpm.

3.0 REFERENCES

3.1 Letter from T. D. Croyle (Westinghouse) to D. F. Hoppes (STPNOC), "Unit 2 Cycle 10 Final Reload Evaluation," NF-TG-02-86 (ST-UB-NOC-02002294), October 1, 2002.

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

3.3 STPNOC Calculation ZC-7035, Rev. 1, "Loop Uncertainty Calculation for RCS Tavg Instrumentation," October 19, 1998.

3.4 STPNOC Calculation ZC-7032, Rev. 3, "Loop Uncertainty Calculation for Narrow Range Pressurizer Pressure Monitoring Instrumentation," June 27, 2001.

1 Applies to all fuel in the Umt 2 Cycle 10 Core 2 A discussion of the processes to be used to take these readings is provided in the basis for Technical Specification 3.2 5 3 Includes a 1.9 IF measurement uncertainty per Reference 3.3 4 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 10 7 psi measurement uncertainty as read on QDPS display per Reference 3 4.

5 Includes a 2.8% flow measurement uncertainty Core Operating Limits Report Page 5

p Na 2 CYCLE 10,,rREviSION, I SOUTH T*ExAS UNnT MARCH2003 Figure 1 Reactor Core Safety Limits - Four Loops in Operation 680 660 640 0 620 P.*

r 600 580 560 540 0 20 40 60 80 100 120 140 Rated Thermal Power (%)

Core Operating Lfmits Report Page 6

ArN-SOUTH TEXAS UNIT 2 CYCLE 10, REVISION I MARCH2003 Figure 2 Required Shutdown Margin for Modes 3 & 4 0

0

.j.

00 0

00 0

CD

\20 G.)

o ..) *.

C, 0

0 o 0 0 0 0 D 0 0 0D 00 r- irn I* -ý 0 Required Shutdown Margin

(%Delta Rho)

Core Operating Limits Report Page 7

C) 0 oo

m. 8.0 00 S~7.0 6.0 '---

.ACCEPTABLE REGION ta. 5.0 - -- - -

(2400.4 50)o rD 4.0 - -- -

3.0_

ITQQ 2.0 wI

, 30).-[UNACCEPTABLE REGION 1.0 - - - - (50.130) I.0 00 - -

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

(for ARI minus the most reactive stuck rod) 0~

fbo 000

,2Mr SOUTH TEXAS UNrr 2 CYCLE 10, REVISION 1 MARCH2003 Figure 4 MTC versus Power Level 7.0 6.0 Unacceptable Operation 5.0 1-1 4.0 C

Acceptable Operation Ot3.0 2.0 0

1.0 Q,

0.0

-1.0

-2.0

-3.0 0 20 40 60 80 100 Rated Thermal Power (%)

Core Operating Limits Report Page 9

-N N-f SOUTH TEXAs UNIT 2 CYCLE 1 0, REVISION 1 MARCH 2003 Figure 5 Control Rod Insertion Limits* versus Power Level (23, 259) 122 Step Overlap (79, 259) 122 Step Overlap (23, 258) 121 Step Overlap (79. 258) 121 Step Overlap (78, 256) 119 Step Overlap 260 I (22I 256) 119 Step Overlap

-(21,254) 117 Step Overlap (77,254) 117 Step Overlap (20,252) 115 Step Overlap (76,252) 15Step Overlap rlap 240 _L (920 1StepOverlap L 7.5) lSe~

220 200 180 ,(100, 174) 160

= 140

• 120

' 01 V j 100 9 80

• Z Li: I 60 (0654) ZII 40 20 (29,0

_______I_ I - __I__L__I 0

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

"*Control Bank A is already withdrawn to Full Out Position Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of 250 and .259 steps withdrawn, inclusive Core Operating Limits Report Page 10

SOUTH TEXAS UNIT 2 CYCLE 10, REVISION I MARCH2003 Figure 6 AFD Limits versus Rated Thermal Poiver 120 100 80 C

I-=

60 40 20 0

-50 -30 -10 10 30 50 Axial Flux Difference (A 1)

Core Operating Limits Report Page I11

SOUTH TEXAS UNIT 2 CYCLE 10, REVISION 1 MARCH2003 Figure 7 K(Z) - Normalized FQ(Z) versus Core Height 1.2 1.0 N

Y. .8 0

LL

.6 IL Core Elevation (ft) FQ K(Z)

N

.4 0.0 2.55 1.0 E

7.0 2.55 1.0 0 14.0 2.359 0.925 Z

.2 0

0.0 7.0 14.0 Core Height (ft)

Core Operating Lumits Report Page 12

&EM -

SOUTH TEXAS UNrT 2 CYCLE 10, REVISIO 1 M~ARCH 2003 SoUTH TEXAS UNIT 2 CYCLE 10, REVISION I MARCH2003 Table I (Part I of 2)

Unrodded F.y for Each Core Height for Cycle Burnups Less Than 9000 MWD/MTU Core Height Axial Core Height Axial S(Ft.) Point Unrodded F, (Ft.) Point Unrodded F 14.00 1 5.689 6.80 37 1.955 13.80 2 4.773 6.60 38 1.937 13.60 3 3.857 6.40 39 1.921 13.40 4 2.941 6.20 40 1.907 13.20 5 2.493 6.00 41 1.893 13.00 6 2.193 5.80 42 1.878 12.80 7 2.172 5.60 43 1.867 12.60 8 2.123 5.40 44 1.856 12.40 9 2.087 5.20 45 1.853 12.20 10 2.058 5.00 46 1.856 12.00 11 2.033 4.80 47 1.860 11.80 12 2.018 4.60 48 1.865 11.60 13 2.017 4.40 49 1.871 11.40 14 2.018 4.20 50 1.881 11.20 15 2.016 4.00 51 1.892 11.00 16 2.011 3.80 52 1.898 10.80 17 2.005 3.60 53 1.901 10.60 18 2.000 3.40 54 1.899 10.40 19 1.995 3.20 55 1.897 10.20 20 1.992 3.00 56 1.901 10.00 21 1.989 2.80 57 1.907 9.80 22 1.987 2.60 58 1.914 9.60 23 1.986 2.40 59 1.917 9.40 24 1.984 2.20 60 1.921 920 25 1.983 2.00 61 1.917 9.00 26 1.983 1.80 62 1.911 8.80 27 1.986 1.60 63 1.904 8.60 28 1.989 1.40 64 1.908 8.40 29 1.995 1.20 65 1.950 8.20 30 2.004 1.00 66 2.039 8.00 31 2.015 0.80 67 2.260 7.80 32 2.028 0.60 68 2.641 7.60 2.028 0.40 69 3.094 7.40 34 2.014 0.20 70 3.547 7.20 35 1.990 0.00 71 4.001 7.00 36 1.971 Core Operating Limits Report Page 13

inua-SouTH TEXAS UNIT 2 CYCLE 10, REVISION I MARCH 2003 Table 1 (Part 2 of 2)

Unrodded Fxy for Each Core Height for Cycle Burnups Greater Than or Equal to 9000 MWD/MTU Core Height Axial Core Height Axial (Ft.) Point Unrodded (Ft.) Point Unrodded 14.00 1 4.440 6.80 37 2.075 13.80 2 3.949 6.60 38 2.085 13.60 3 3.400 6.40 39 2.096 13.40 4 2.827 6.20 40 2.094 13.20 5 2.474 6.00 41 2.088 13.00 6 2.189 5.80 42 2.077 12.80 7 2.171 5.60 43 2.066 12.60 8 2.140 5.40 44 2.054 12.40 9 2.114 5.20 45 2.044 12.20 10 2.088 5.00 46 2.035 12.00 11 2.065 4.80 47 2.027 11.80 12 2.055 4.60 48 2.021 11.60 13 2.054 4.40 49 2.010 11.40 14 2.058 4.20 50 1.998 11.20 15 2.063 4.00 51 1.983 11.00 16 2.070 3.80 52 1.970 10.80 17 2.071 3.60 53 1.959 10.60 18 2.071 3.40 54 1.949 10.40 19 2.070 3.20 55 1.934 10.20 20 2.072 3.00 56 1.917 10.00 21 2.076 2.80 57 1.895 9.80 22 2.082 2.60 58 1.870 9.60 23 2.083 240 59 1.844 9.40 24 2.081 2.20 60 1.813 9.20 25 2.077 2.00 61 1.798 9.00 26 2.071 1.80 62 1.786 8.80 27 2.061 1.60 63 1.779 8.60 28 2.051 1.40 64 1.778 8.40 29 2.044 1.20 65 1.806 8.20 30 2.038 1.00 66 1.870 8.00 31 2.032 0.80 67 2.031 7.80 32 2.031 0.60 68 2.295 7.60 33 2.034 0.40 69 2.590 7.40 34 2.042 0.20 70 2.828 7.20 35 2.053 0.00 71 2.885 7.00 36 2.065 Core Operating Limits Report Page 14