ML030780031
| 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 Poiqct Ektdric Grating Station PO. Box 289 adswuth, T=5s 77483 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 1 l(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 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 Richard A. Ratliff Bureau of Radiation Control Texas Department of Health 1100 West 49th Street Austin, TX 78756-3189 Cornelius F. O'Keefe U. S. Nuclear Regulatory Commission P. 0. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483 A. H. Gutterman, Esquire Morgan, Lewis & Bockius LLP L. D. Blaylock/W. C. Gunst City Public Service Mohan C. Thadani U. S. Nuclear Regulatory Commission R. L. Balcom Texas Genco, LP A. Ramirez City of Austin C. A. Johnson AEP Texas Central Company Jon C. Wood Matthews & Branscomb 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 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 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, K2 = 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 K6 = 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 Fuel1 FgtTP = 1.49 VANTAGE 5H / RFA Fuel2 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 psig5,
- c.
Minimum Measured Reactor Coolant System Flow > 403,000 gpm6.
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, 1 IB, 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
South Texas Unit I Cycle 11, Revision 3 Figure 1 Reactor Core Safety Limits - Four Loops in Operation 680 660 640
, 620 U 600 580 560 540 20 40 60 80 Rated Thermal Power (%)
6 0
100 120 140 March 2003
Figure 2 Required Shutdown Margin for Modes 3 & 4 0ý 0
0 0
N 0
00 o
o
°0.)
N C.
0~
C 0
0 o
.)
0ý 9ý 9ýCý 0 0
0 CD Required Shutdown Margin
(%Delta Rho) 7 South Texas Unit I Cycle 11, Revision 3 March 2003 0
Cq.)
I 0
0~
0=
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
South Texas Unit 1 Cycle 11, Revision 3 Figure 4 MTC versus Power Level 0
20 40 60 80 100 Rated Thermal Power (%)
9 7.0 6.0 5.0 4.0 3.0 2.0 1.0 0.0
-1.0
-2.0
-3.0 I0 U,,,
,6, March 2003
South Texas Unit 1 Cycle 11, Revision 3 Figure 5 Control Rod Insertion Limits* versus Power Level (23,259) 122 Step Overlap (23, 258) 121 Step Overlap (22, 256) 119 Step Overlap (21,254) 117 Step Overlap ThzHIH (79,259) 122 Step Overlap (79,258) 121 Step Overlap (78,256) 119 Step Overlap (77,254) 117 Step Overlap VIK ;,)
'119C r
260 240 220 200 180 160 140 120 100 80 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 li
~iVi (19, 250) 113 Step Overlap (75,250) 113 Step Ove Ban B
~
a
-f(
00 174)i Lan Ban
.C A
i ii i
1, IF_
EI i
i L
07 Bank OFI (0,65)
(2 25115SeOel (29.0) 4t I
0 60 40 20 0
March 2003
- ap*
erlap
South Texas Unit I Cycle 11, Revision 3 Figure 6 AFD Limits versus Rated Thermal Power
-30
-10 10 30 Axial Flux Difference (A I) 11 120 100 0
80 60 40 20 0
-50 50 March 2003
South Texas Unit I Cycle 11, Revision 3 Figure 7 K(Z) - Normalized FQ(Z) versus Core Height 7.0 14.0 Core Height (ft) 12 1.2 1.0
.8
.6
.4 N
k_
0 tM N
E Z
Core Elevation (ft)
FQ K(Z) 0.0 2.55 1.0 7.0 2.55 1.0 14.0 2.359 0.925
.2 0
0.0 March 2003
South Texas Unit 1 Cycle 11, Revision 3 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 13.80 13.60 13.40 13.20 13.00 12.80 12.60 12.40 12.20 12.00 11.80 11.60 11.40 11.20 11.00 10.80 10.60 10.40 10.20 10.00 9.80 9.60 9.40 9.20 9.00 8.80 8.60 8.40 8.20 8.00 7.80 7.60 7.40 7.20 7.00 1
2 3
4 5
6 7
8
- 9.
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 5.123 4.303 3.482 2.661 2.291 2.061 2.096 2.092 2.082 2.057 2.027 2.007 2.002 2.002 2.001 1.999 1.994 1.990 1.986 1.985 1.985 1.986 1.988 1.989 1.990 1.991 1.994 1.999 2.007 2.016 2.024 2.032 2.030 2.006 1.980 1.962 6.80 6.60 6.40 6.20 6.00 5.80 5.60 5.40 5.20 5.00 4.80 4.60 4.40 4.20 4.00 3.80 3.60 3.40 3.20 3.00 2.80 2.60 2.40 2.20 2.00 1.80 1.60 1.40 1.20 1.00 0.80 0.60 0.40 0.20 0.00 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 1.948 1.932 1.920 1.909 1.898 1.894 1.895 1.894 1.896 1.900 1.907 1.916 1.924 1.929 1.933 1.933 1.926 1.922 1.915 1.901 1.886 1.854 1.816 1.774 1.755 1.744 1.740 1.735 1.744 1.780 1.933 2.351 2.901 3.451 4.001
- For Unit 1 Cycle 11, the L(Z) penalty is not applied (i.e., L(Z) = 1.0 for all core elevations).
13 March 2003
South Texas Unit I Cycle 11, Revision 3 Table 2 Unrodded FXy for Each Core Height*
For Cycle Burnups Greater Than or Equal to 9000 MWD/MTU Core Height (Ft.)
Axial Point Unrodded Fxy 14.00 13.80 13.60 13.40 13.20 13.00 12.80 12.60 12.40 12.20 12.00 11.80 11.60 11.40 11.20 11.00 10.80 10.60 10.40 10.20 10.00 9.80 9.60 9.40 9.20 9.00 8.80 8.60 8.40 8.20 8.00 7.80 7.60 7.40 7.20 7.00 Core Height (Ft.)
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 Axial Point 5.186 4.443 3.665 2.858 2.456 2.180 2.153 2.109 2.082 2.072 2.053 2.035 2.031 2.034 2.036 2.038 2.039 2.040 2.040 2.038 2.037 2.036 2.039 2.045 2.053 2.057 2.059 2.060 2.065 2.074 2.085 2.096 2.105 2.114 2.121 2.125 Unrodded Fxy 6.80 6.60 6.40 6.20 6.00 5.80 5.60 5.40 5.20 5.00 4.80 4.60 4.40 4.20 4.00 3.80 3.60 3.40 3.20 3.00 2.80 2.60 2.40 2.20 2.00 1.80 1.60 1.40 1.20 1.00 0.80 0.60 0.40 0.20 0.00
- For Unit I Cycle 11, the L(Z) penalty is not applied (i.e., L(Z) = 1.0 for all core elevations).
14 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 2.125 2.122 2.112 2.101 2.088 2.075 2.063 2.051 2.041 2.031 2.023 2.016 2.006 1.995 1.982 1.970 1.958 1.947 1.936 1.924 1.911 1.879 1.852 1.841 1.831 1.820 1.813 1.827 1.815 1.822 2.066 2.542 3.117 3.656 4.121 March 2003
SOUTH TEXAS PROJECT UNIT I CYCLE 11 CORE OPERATING LIMITS REPORT REVISION 4 March 2003 I
South Texas Unit 1 Cycle 11, Revision 4 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 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, l I = 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, 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 0.002/7F 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 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
South Texas Unit I Cycle 11, Revision 4 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 Fuel2 Py = 1.53 WITH RCS Loop-specific Temperature Calibrations:
Standard Fuel1 FI,, = 1.49 VANTAGE 5H / RFA Fuel2 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 psig5,
- c.
Minimum Measured Reactor Coolant System Flow > 403,000 gpm6.
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 March 2003
South Texas Unit 1 Cycle 11, Revision 4 Figure 1 Reactor Core Safety Limits - Four Loops in Operation 680 660 640 0 620 S600 580 560 540 20 40 60 80 100 120 Rated Thermal Power (%)
6 0
140 I
March 2003
South Texas Unit I Cycle 11, Revision 4 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
o 94*
0 0
Oý 0ý 0
0 0
- 0) 0C 0
00 r-kn rti
(
Required Shutdown Margin
(%Delta Rho) 7 March 2003
Figure 3 Required Shutdown Margin for Mode 5 Required Shutdown Margin
(% Delta Rho) 8 South Texas Unit 1 Cycle 11, Revision 4 March 2003 0~
0 0
0 oi Or I.-)
0.)
0ý I=
0
Sout Texs Uit ICyce 11 Reisio 4 arch200 Figure 4 MTC versus Power Level 20 40 60 80 100 Rated Thermal Power (%)
9 7.0 6.0 5.0 4.0 3.0 2.0 1.0 0.0 0 E.
U 0,,
-1.0
-2.0
-3.0 Unacceptable Operation Acceptable OperationJ
+
+
4 4
4 0
South Texas Unit 1 Cycle 11, Revision 4 March 2003
South Texas Unit 1 Cycle 11, Revision 4 Figure 5 Control Rod Insertion Limits* versus Power Level (23,259) 122 Step Overlap (23, 258) 121 Step Overlap (22, 256) 119 Step Overlap 1(21, 254) 117 Step Overlap (20,252) 115 Step Overlap J(19,250) 113 Step Overlap FI I I I I 1"F4 __1
'-mlI (79,259) 122 Step Overlap (79,258) 121 Step Overlap (78,256) 119 Step Overlap (77,254) 117 Step Overlap (76, 252) 115 Step Overlap (75, 250) 113 Step Overlap 260 240 220 200 180 t
160
- = 140 0
120 100 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 ank B Bank C 0(0,14 xz Bank D (0, 65) 11 1 ([_.
or 60 40 20 0
I March 2003 I I
South Texas Unit I Cycle 11, Revision 4 Figure 6 AFD Limits versus Rated Thermal Power
-30
-10 10 30 50 Axial Flux Difference (A 1) 11 120 100 I-.
X0 80 60 40 20 0
-50 March 2003
South Texas Unit I Cycle 11, Revision 4 March 2003 Figure 7 K(Z) - Normalized FQ(Z) versus Core Height 14.0 7.0 Core Height (ft) 12 1.2 1.0
.8
.6
.4 0
14.'
CD CU
- 0)
N 0u E
Z Core Elevation (ft)
FQ K(Z) 0.0 2.55 1.0 7.0 2.55 1.0 14.0 2.359 0.925
.2 0
0.0 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 13.80 13.60 13.40 13.20 13.00 12.80 12.60 12.40 12.20 12.00 11.80 11.60 11.40 11.20 11.00 10.80 10.60 10.40 10.20 10.00 9.80 9.60 9.40 9.20 9.00 8.80 8.60 8.40 8.20 8.00 7.80 7.60 7.40 7.20 7.00 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 5.123 4.303 3.482 2.661 2.291 2.061 2.096 2.092 2.082 2.057 2.027 2.007 2.002 2.002 2.001 1.999 1.994 1.990 1.986 1.985 1.985 1.986 1.988 1.989 1.990 1.991 1.994 1.999 2.007 2.016 2.024 2.032 2.030 2.006 1.980 1.962 6.80 6.60 6.40 6.20 6.00 5.80 5.60 5.40 5.20 5.00 4.80 4.60 4.40 4.20 4.00 3.80 3.60 3.40 3.20 3.00 2.80 2.60 2.40 2.20 2.00 1.80 1.60 1.40 1.20 1.00 0.80 0.60 0.40 0.20 0.00 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 1.948 1.932 1.920 1.909 1.898 1.894 1.895 1.894 1.896 1.900 1.907 1.916 1.924 1.929 1.933 1.933 1.926 1.922 1.915 1.901 1.886 1.854 1.816 1.774 1.755 1.744 1.740 1.735 1.744 1.780 1.933 2.351 2.901 3.451 4.001
- 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 (Ft.)
14.00 13.80 13.60 13.40 13.20 13.00 12.80 12.60 12.40 12.20 12.00 11.80 11.60 11.40 11.20 11.00 10.80 10.60 10.40 10.20 10.00 9.80 9.60 9.40 9.20 9.00 8.80 8.60 8.40 8.20 8.00 7.80 7.60 7.40 7.20 7.00 Axial Point 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 Unrodded Fxy 5.186 4.443 3.665 2.858 2.456 2.180 2.153 2.109 2.082 2.072 2.053 2.035 2.031 2.034 2.036 2.038 2.039 2.040 2.040 2.038 2.037 2.036 2.039 2.045 2.053 2.057 2.059 2.060 2.065 2.074 2.085 2.096 2.105 2.114 2.121 2.125 Core Height (Ft.)
6.80 6.60 6.40 6.20 6.00 5.80 5.60 5.40 5.20 5.00 4.80 4.60 4.40 4.20 4.00 3.80 3.60 3.40 3.20 3.00 2.80 2.60 2.40 2.20 2.00 1.80 1.60 1.40 1.20 1.00 0.80 0.60 0.40 0.20 0.00 Axial Point 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 Unrodded Fxy 2.125 2.122 2.112 2.101 2.088 2.075 2.063 2.051 2.041 2.031 2.023 2.016 2.006 1.995 1.982 1.970 1.958 1.947 1.936 1.924 1.911 1.879 1.852 1.841 1.831 1.820 1.813 1.827 1.815 1.822 2.066 2.542 3.117 3.656 4.121
- For Unit 1 Cycle 11, the L(Z) penalty is not applied (i.e., L(Z) = 1.0 for all core elevations).
14 South Texas Unit I Cycle 11, Revision 4 March 2003
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 1 I 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 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 for T < T" T1 Indicated full power Tavg, T" <5 592.0 'F f2(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/0F 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 psig4,
- 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
,r SOUTH T*ExAS UNnT 2 CYCLE 10, REviSION, I MARCH2003 Figure 1 Reactor Core Safety Limits - Four Loops in Operation 680 660 640 0 620 P.*
r 600 580 560 540 20 40 60 80 100 Rated Thermal Power (%)
Core Operating Lfmits Report 0
120 140 Page 6
ArN-Figure 2 Required Shutdown Margin for Modes 3 & 4 0
0
.j.
0 0 0
0 CD 00
\\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 SOUTH TEXAS UNIT 2 CYCLE 10, REVISION I MARCH2003 Page 7
oo C) 0 00
- m.
8.0 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 I.0 1.0 (50.130) 00 0
400 800 1200 1600 2000 2400 RCS Critical Boron Concentration (ppm)
(for ARI minus the most reactive stuck rod) 000 0~
fbo
,2Mr SOUTH TEXAS UNrr 2 CYCLE 10, REVISION 1 Figure 4 MTC versus Power Level 20 40 60 80 Rated Thermal Power (%)
Core Operating Limits Report MARCH2003 7.0 6.0 5.0 4.0 3.0 2.0 1.0 0.0
-1.0
-2.0
-3.0 C
1-1 Ot 0
Q, Unacceptable Operation Acceptable Operation 0
100 Page 9
-N &
N-f Figure 5 Control Rod Insertion Limits* versus Power Level (23, 259) 122 Step Overlap (23, 258) 121 Step Overlap (22I 256) 119 Step Overlap
-(21,254) 117 Step Overlap (20,252) 115 Step Overlap (79, 259) 122 Step Overlap (79. 258) 121 Step Overlap (78, 256) 119 Step Overlap (77,254) 117 Step Overlap (76,252) 15Step Overlap 260 240 220 200 180 160
= 140
- 120 100 9
80 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
_L (920 1StepOverlap L
7.5) lSe~
V j
01
,(100, 174)
Li:
- Z I
ZII (0654)
_______I_
I
__I__L__I (29,0 60 40 20 0
I SOUTH TEXAs UNIT 2 CYCLE 1 0, REVISION 1 MARCH 2003 rlap Page 10
SOUTH TEXAS UNIT 2 CYCLE 10, REVISION I MARCH2003 Figure 6 AFD Limits versus Rated Thermal Poiver 120 100 C
I-=
80 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 Figure 7 K(Z) - Normalized FQ(Z) versus Core Height 7.0 Core Height (ft)
Core Operating Lumits Report MARCH2003 1.2 1.0
.8
.6
.4 N
Y.
0 LL IL N
E 0 Z Core Elevation (ft)
FQ K(Z) 0.0 2.55 1.0 7.0 2.55 1.0 14.0 2.359 0.925
.2 0
0.0 14.0 Page 12
&E M 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 S(Ft.)
14.00 13.80 13.60 13.40 13.20 13.00 12.80 12.60 12.40 12.20 12.00 11.80 11.60 11.40 11.20 11.00 10.80 10.60 10.40 10.20 10.00 9.80 9.60 9.40 920 9.00 8.80 8.60 8.40 8.20 8.00 7.80 7.60 7.40 7.20 7.00 Axial Point 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 34 35 36 Unrodded F, 5.689 4.773 3.857 2.941 2.493 2.193 2.172 2.123 2.087 2.058 2.033 2.018 2.017 2.018 2.016 2.011 2.005 2.000 1.995 1.992 1.989 1.987 1.986 1.984 1.983 1.983 1.986 1.989 1.995 2.004 2.015 2.028 2.028 2.014 1.990 1.971 Core Height Axial (Ft.)
Point 6.80 6.60 6.40 6.20 6.00 5.80 5.60 5.40 5.20 5.00 4.80 4.60 4.40 4.20 4.00 3.80 3.60 3.40 3.20 3.00 2.80 2.60 2.40 2.20 2.00 1.80 1.60 1.40 1.20 1.00 0.80 0.60 0.40 0.20 0.00 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 Unrodded F 1.955 1.937 1.921 1.907 1.893 1.878 1.867 1.856 1.853 1.856 1.860 1.865 1.871 1.881 1.892 1.898 1.901 1.899 1.897 1.901 1.907 1.914 1.917 1.921 1.917 1.911 1.904 1.908 1.950 2.039 2.260 2.641 3.094 3.547 4.001 Core Operating Limits Report SOUTH TEXAS UNrT 2 CYCLE 10, REVISIO 1 M~ARCH 2003 Page 13
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 (Ft.)
14.00 13.80 13.60 13.40 13.20 13.00 12.80 12.60 12.40 12.20 12.00 11.80 11.60 11.40 11.20 11.00 10.80 10.60 10.40 10.20 10.00 9.80 9.60 9.40 9.20 9.00 8.80 8.60 8.40 8.20 8.00 7.80 7.60 7.40 7.20 7.00 Core Height Axial (Ft.)
Point Axial Point 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 Unrodded 4.440 3.949 3.400 2.827 2.474 2.189 2.171 2.140 2.114 2.088 2.065 2.055 2.054 2.058 2.063 2.070 2.071 2.071 2.070 2.072 2.076 2.082 2.083 2.081 2.077 2.071 2.061 2.051 2.044 2.038 2.032 2.031 2.034 2.042 2.053 2.065 6.80 6.60 6.40 6.20 6.00 5.80 5.60 5.40 5.20 5.00 4.80 4.60 4.40 4.20 4.00 3.80 3.60 3.40 3.20 3.00 2.80 2.60 240 2.20 2.00 1.80 1.60 1.40 1.20 1.00 0.80 0.60 0.40 0.20 0.00 Core Operating Limits Report inua-37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 Unrodded 2.075 2.085 2.096 2.094 2.088 2.077 2.066 2.054 2.044 2.035 2.027 2.021 2.010 1.998 1.983 1.970 1.959 1.949 1.934 1.917 1.895 1.870 1.844 1.813 1.798 1.786 1.779 1.778 1.806 1.870 2.031 2.295 2.590 2.828 2.885 Page 14