NOC-AE-02001434, Revision 2 to Unit 1 Cycle 11 Core Operating Limits Report

Revision 2 to Unit 1 Cycle 11 Core Operating Limits Report

ML023540357
Person / Time
Site:	South Texas
Issue date:	12/11/2002
From:	Leazar D South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NOC-AE-02001434, TAC MB5160, TAC MB5161
Download: ML023540357 (14)

Text

Nuclear Operating Company South Tcxs Pro/c*d Ekdrc EkcneratlngSta1lon PO. BY 289 Madwah Teas 77483-A--,

December 11, 2002 NOC-AE-02001434 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 Unit 1 Docket No. STN 50-498 Revision 2 to the Unit 1 Cycle 11 Core Operating Limits Report

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 Revision 2 to the Core Operating Limits Report (COLR) is submitted for South Texas Project (STP) Unit 1 Cycle 11.

Revision 2 includes the changes to the end-of-life moderator temperature coefficient surveillance requirements approved in the above reference. Revised entries are indicated by bars in the margins.

If there are any questions concerning this report, please contact K. A. Work at (361) 972-7936 or me at (361) 972-7795.

7-D6/ G David A. Leazar Director, Nuclear Fuel & Analysis kaw

Attachment:

Unit I Cycle 11 Core Operating Limits Report, Revision 2

,'col 0 \QUALrrYAND.LICENSING\NI\Nrc-ap\Misc-02\02001434 doc STE:31529934

NOC-AE-02001434 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 M. T. Hardt/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 - Central Power and Light Company Cornelius F. O'Keefe Jon C. Wood U. S. Nuclear Regulatory Commission Matthews & Branscomb P. 0. Box 289, Mail Code: MN116 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704

3/ g0 L899D SOUTH TEXAS UNIT 1 CYCLE 11 CORE OPERATING LIMITS REPORT REVISION 2 November 2002

November 2002 South Texas Unit 1 Cycle 11, Revision 2 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for STPEGS Unit 1 Cycle 11 has been prepared in accordance been with the requirements of Technical Specification 6.9.1.6. The core operating limits have 6.9.1.6.

developed using the NRC-approved methodologies specified in Technical Specification The Technical Specifications affected by this report are:

1) 2.1 SAFETY LIMITS

2) 2.2 LIMITING SAFETY SYSTEM SETTINGS

3) 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT LIMITS

4) 3/4.1.3.5 SHUTDOWN ROD INSERTION LIMITS

5) 3/4.1.3.6 CONTROL ROD INSERTION LIMITS

6) 3/4.2.1 AFD LIMITS

7) 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR

8) 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR

9) 3/4.2.5 DNB PARAMETERS 2.0 OPERATING LIMITS below.

The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented 2.1 SAFETY LIMITS (Specification 2.1):

2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (T.,z) 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:

1

South Texas Unit 1 Cycle 11, Revision 2 November 2002 Over-temperature AT Setpoint Parameter Values Ir, measured reactor vessel AT lead/lag time constant, ;, = 8 sec

• r2 measured reactor vessel AT lead/lag time constant, T2 = 3 sec T3 measured reactor vessel AT lag time constant, ; = 0 sec T4* measured reactor vessel average temperature lead/lag time constant, 'r = 28 sec measured reactor vessel average temperature lead/lag time constant, ir = 4 sec T measured reactor vessel average temperature lag time constant, 'r = 0 sec K1 Overtemperature AT reactor trip setpoint, K1 = 1.14 K2 Overtemperature AT reactor trip setpoint T.,, coefficient, K2 = 0.028/°F K3 Overtemperature AT reactor trip setpoint pressure coefficient, K3 = 0.00143/psig "T' Nominal full power T.,,, T' < 592.0 °F P' Nominal RCS pressure, P' = 2235 psig fj(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%, fý(AI) = 0, where qt and q, are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and q, + q, 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 q, - 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 Il, measured reactor vessel AT lead/lag time constant, ; = 8 sec T2 measured reactor vessel AT lead/lag time constant, T,2 = 3 sec T3* measured reactor vessel AT lag time constant, , = 0 sec Ts measured reactor vessel average temperature lag time constant, r6 = 0 sec T7 Time constant utilized in the rate-lag compensator for Ta,,,, r7 = 10 sec K4 Overpower AT reactor trip setpoint, K, = 1.08 IK Overpower AT reactor trip setpoint T.,, rate/lag coefficient, K5 = 0.02/°F for increasing average temperature, and K5 = 0 for decreasing average temperature K, Overpower AT reactor trip setpoint T.,, heatup coefficient K. = 0.002/°F for T > T" and, K6 = 0 for T < T" T" Indicated full power T.,,, T" __592.0 'F f 2(AI) = 0 for all (AI) 2

South Texas Unit 1 Cycle 11, Revision 2 November 2002 2.3 MODERATOR TEMPERATURE COEFFICIENT (Specification 3.1.1.3):

2.3.1 The BOL, ARO, MTC shall be less positive than the limits shown in Figure 2.

2.3.2 The EOL, ARO, HFP, MTC shall be less negative than -61.2 pcm/0 F.

2.3.3 The 300 ppm, ARO, HFP, MTC shall be less negative than -53.6 pcin/°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.

2.3.4 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 pcmr°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.

2.4 ROD INSERTION LIMITS (Specification 3.1.3.5 and 3.1.3.6):

2.4.1 All banks shall have the same Full Out Position (FOP) of at least 250 steps withdrawn but not exceeding 259 steps withdrawn.

2.4.2 The Control Banks shall be limited in physical insertion as specified in Figure 3.

2.4.3 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).

2.5 AXIAL FLUX DIFFERENCE (Specification 3.2.1):

2.5.1 AFD limits as required by Technical Specification 3.2.1 are determined by CAOC Operations with an AFD target band of +5, -10%.

2.5.2 The AFD shall be maintained within the ACCEPTABLE OPERATION portion of Figure 4, as required by Technical Specifications.

2.6 HEAT FLUX HOT CHANNEL FACTOR (Specification 3.2.2):

2.6.1 F'* = 2.55.

2.6.2 K(Z) is provided in Figure 5.

2.6.3 The F, limits for RATED THERMAL POWER (Fw.) within specific core planes shall be:

2.6.3.1 Less than or equal to 2.102 for all core planes containing Bank "D" control rods, and 2.6.3.2 Less than or equal to the appropriate core height-dependent value from Table 1 for all unrodded core planes.

2.6.3.3 PF, = 0.2.

These F., 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 3

South Texas Unit 1 Cycle 11, Revision 2 November 2002 and D during operation, including the accompanying variations in the axial xenon and power distributions, as described in WCAP-8385. Therefore, these F, 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).

2.7 ENTHALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3):

2.7.1 WITHOUT RCS Loop-specific Temperature Calibrations:

Standard Fuel' F*,p = 1.46 VANTAGE 5H / RFA Fuel 2 FaP = 1.53 WITH RCS Loop-specific Temperature Calibrations:

Standard Fuel1 Ia = 1.49 VANTAGE 5H / RFA Fuel2 FA = 1.557 2.7.2 Standard Fuel / VANTAGE 5H1/ RFA Fuel PFAH = 0.3 2.8 DNB PARAMETERS (Specification 3.2.5):

2.8.1 The following 3

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

a. Reactor Coolant System T.,,, -<595 OFV,

b. Pressurizer Pressure, > 2200 psig5 ,

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 I 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. I and 2.

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

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.

SApplies to Region 5.

2 Applies to Regions 10A, 11A, lB, 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.

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.

4

November 2002 South Texas Unit 1 Cycle 11, Revision 2 Figure 1 Reactor Core Safety Limits - Four Loops in Operation 680 660 640 o620 U 600 580 560 540 0 20 40 60 80 100 120 140 Rated Thermal Power (%)

5

South Texas Unit I Cycle 11, Revision 2 November 2002 South Texas Unit 1 Cycle 11, Revision 2 November 2002 Figure 2 MTC versus Power Level 7.0 6.0 Unacceptable Operation I I 5.0 4.0 Acceptable Operation.

3.0 0

U 2.0 E~

0 1.0 t- 0.0

-1.0

-2.0

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

6

South Texas Unit 1 Cycle 11, Revision 2 November 2002 South Texas Unit 1 Cycle 11, Revision 2 November 2002 Figure 3 Control Rod Insertion Limits* versus Power Level 260 (23, 259): 122 Step Overlap (23.258): 121 (22,256): 119 (21,254): 117 Step Overlap Step Overlap Step Overlap

-JlI i~

[(79. 259): 122 Step (79, 258): 121 Step (78, 256): 119 Step (77. 254): 117 Step Overlap Overlap Overlap Overlap (20, 252): 115 Step Overlap (76. 252): 115 Step Overlap (19, 250): 113 Step Overlap (75,250): 113 Step Overlap 240

• Bank B 220 J!"

200 180 us 160 Bank C C,,

Cm 140 us 0 120 r0 100

_Bank D 80

• OF 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 shutdov, n and control banks are at a position within the interval of 250 and 5259 steps withdrawn, inclusive.

7

South Texas Unit 1 Cycle 11, Revision 2 November 2002 South Texas Unit 1 Cycle 11, Revision 2 November 2002 Figure 4 AFD Limits versus Rated Thermal Power 120 100 80 C

60

-'-a 40 20 0

-50 -30 -10 10 30 50 Axial Flux Difference (A I) 8

South Texas Unit I Cycle 11, Revision 2 November 2002 South Texas Unit 1 Cycle 11, Revision 2 November 2002 Figure 5 K(Z) - Normalized FQ(Z) versus Core Height 1.2 1.0 N

Yi.

.8 0

1=

.6 CO 4-'

Core Elevation (ft) F0 K(Z)

N

.4 0.0 2.55 1.0 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) 9

South Texas Unit 1 Cycle 11, Revision 2 November 2002 Table 1 Unrodded F., for Each Core Height*

For Cycle Burnups Less Than 9000 MWD/MTU Core Height Axial Unrodded Core Height Axial Unrodded (Ft.) Point F., (Ft.) Point F, 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).

10

South Texas Unit 1 Cycle 11, Revision 2 November 2002 South Texas Unit 1 Cycle 11, Revision 2 November 2002 Table 2 Unrodded F, 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 Fý (Ft.) Point F.,

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).

11