NOC-AE-02001325, Revision 1 to Unit 1 Cycle 11 Core Operating Limits Report

Revision 1 to Unit 1 Cycle 11 Core Operating Limits Report

ML021410394
Person / Time
Site:	South Texas
Issue date:	05/13/2002
From:	Leazar D South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NOC-AE-02001325, TAC MB2899, TAC MB2903
Download: ML021410394 (15)

Text

w Nuclear Operating Company m19rml South Texas Project ElectricGeneratinSStation PO Box 289 Wadswvorth, Texas 77483 Ak-- ,k-\A -

May 13, 2002 NOC-AE-02001325 File No.: G25 10CFR50.36 STI: 31446010 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Unit 1 Docket No. STN 50-498 Revision 1 to Unit 1 Cycle 11 Core Operating Limits Report

Reference:

Letter from Mohan C. Thadani to William T. Cottle, "South Texas Project, Unit 1 and 2 Issuance of Amendments Approving Uprated Core Thermal Power and Revising the Associated Technical Specifications" (TAC Nos. MB2899 and MB2903), dated April 12, 2002 In accordance with Technical Specification 6.9.1.6.d, the attached Revision I to the Core Operating Limits Report is submitted for South Texas Project Unit 1 Cycle 11. Revision 1 accounts for changes resulting from the power uprate approved in the above reference and several administrative formatting changes. Revised entries are indicated by bars in the margins.

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

David A. Leazar Director, Nuclear Fuel & Analysis kaw

Attachment:

Unit 1 Cycle 11 Core Operating Limits Report, Revision 1 0

cc: Licensing Library RMS (w/o attachment)

O:\QUALITYANDLICENSING\Nl\Nrc-wk\Misc-02\02001325.doc

NOC-AE-02001325 Page 2 cc:

Ellis W. Merschoff A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius U.S. Nuclear Regulatory Commission 1111 Pennsylvania Avenue, N. W.

611 Ryan Plaza Drive, Suite 400 Washington, DC 20004 Arlington, Texas 76011-8064 U. S. Nuclear Regulatory Commission Mohan C. Thadani Attention: Document Control Desk Project Manager One White Flint North U. S. Nuclear Regulatory Commission 11555 Rockville Pike 1 White Flint North, Mail Stop: O-7D1 Rockville, MD 20852 11555 Rockville Pike Rockville, MD 20852-2738 Richard A. Ratliff Bureau of Radiation Control C. A. Johnson/A. C. Bakken, III Texas Department of Health AEP - Central Power and Light Company 1100 West 49th Street P. 0. Box 289, Mail Code: N5022 Austin, TX 78756-3189 Wadsworth, TX 77483 Cornelius F. O'Keefe Jon C. Wood U. S. Nuclear Regulatory Commission Matthews & Branscomb P. O. Box 289, Mail Code: MN116 112 East Pecan, Suite 1100 Wadsworth, TX 77483 San Antonio, TX 78205-3692 A. Ramirez/C. M. Canady M. T. Hardt/W. C. Gunst City of Austin City Public Service Electric Utility Department P. 0. Box 1771 721 Barton Springs Road San Antonio, TX 78296 Austin, TX 78704 R. L. Balcom Reliant Energy, Inc.

P. 0. Box 1700 Houston, TX 77251

SOUTH TEXAS UNIT 1 CYCLE 11 CORE OPERATING LIMITS REPORT REVISION 1 May 2002

South Texas Unit 1 Cycle 11, Revision 1 May 2002 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) 3/4.1.1.3 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 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:

1

South Texas Unit 1 Cycle 11, Revision 1 May 2002 Over-temperature AT Setpoint Parameter Values

'Cl measured reactor vessel AT lead/lag time constant, c1 = 8 sec 2

2 measured reactor vessel AT lead/lag time constant, c2 = 3 sec T3* measured reactor vessel AT lag time constant, r, = 0 sec

'C4 measured reactor vessel average temperature lead/lag time constant, C 4 = 28 sec T5 measured reactor vessel average temperature lead/lag time constant, 'C = 4 sec T6 measured reactor vessel aaverageg temperature lag time constant, 6 = 0 sec tK Overtemperature AT reactor trip setpoint, K- = 1.14 K, Overtemperature AT reactor trip setpoint Tavg coefficient, K2 = 0.028/°F K3 Overtemperature AT reactor trip setpoint pressure coefficient, KI = 0.00143/psig T1 Nominal full power Tv,, T' < 592.0 °F P1 Nominal RCS pressure, P' = 2235 psig f 1(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 qt - q, between -70% and +8%, f1(AI) = 0, where q, 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 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

'E measured reactor vessel AT lead/lag time constant, c1 = 8 sec 12 measured reactor vessel AT lead/lag time constant, T2 = 3 sec Ic3 measured reactor vessel AT lag time constant, c3 = 0 sec I 6 measured reactor vessel average temperature lag time constant, r6 = 0 sec

'r7 Time constant utilized in the rate-lag compensator for Tavg, r7 = 10 sec K4 Overpower AT reactor trip setpoint, K4 = 1.08 K2 Overpower AT reactor trip setpoint Tav, rate/lag coefficient, K, = 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, KE= 0 for T < T" T" Indicated full power Tag, T" < 592.0 'F f,(AI) = 0 for all (AI) 2

South Texas Unit 1 Cycle 11, Revision 1 May 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 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 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 F7Jp = 2.55.

2.6.2 K(Z) is provided in Figure 5.

2.6.3 The F limits for RATED THERMAL POWER (F7r") 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 and D during operation, including the accompanying variations in the axial xenon and power distributions, as described in WCAP-8385. Therefore, these F Ylimits 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).

3

South Texas Unit 1 Cycle 11, Revision 1 May 2002 2.7 ENTHALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3):

2.7.1 WITHOUT RCS Loop-specific Temperature Calibrations:

Standard Fuel' F = 1.46 VANTAGE 5H / RFA Fuel2 FR = 1.53 WITH RCS Loop-specific Temperature Calibrations:

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

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

a. Reactor Coolant System Tavg, < 595 OF4,

b. Pressurizer Pressure, > 2200 psig,

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, 11A, llB, 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 OF 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

South Texas Unit 1 Cycle 11, Revision 1 May 2002 South Texas Unit 1 Cycle 11, Revision 1 May 2002 Figure 1 Reactor Core Safety Limits - Four Loops in Operation 680 660 640 S620 Q600 580 560 540 0 20 40 60 80 100 120 140 Rated Thermal Power (%)

5

South Texas Unit I Cycle 11, Revision 1 May 2002 South Texas Unit 1 Cycle 11, Revision 1 May 2002 Figure 2 MTC versus Power Level 7.0 6.0 Unacceptable Operation-5.0 Wo 4.0 Acceptable Operation 3.0 2.0 1.0 0.0 0

0.i -1.0

-2.0

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

6

South Texas Unit I Cycle 11, Revision 1 May 2002 South Texas Unit 1 Cycle 11, Revision 1 May 2002 Figure 3 Control Rod Insertion Limits* versus Power Level 260 240 220 200 180 160 03J S120 0

S100 8

S80 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 <259 steps withdrawn, inclusive.

7

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

0 60 2

40 20 0

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

South Texas Unit 1 Cycle 11, Revision 1 Figure 5 May 2002 r

K(Z) - Normalized FQ(Z) versus Core Height 1.2 1.0 N

.8 O

LL 0,

ILI 40 c') .6 o1~

I 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) 9

South Texas Unit 1 Cycle 11, Revision 1 May 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 2 4.303 6.60 38 1.932 13.80 3 3.482 6.40 39 1.920 13.60 4 2.661 6.20 40 1.909 13.40 5 2.291 6.00 41 1.898 13.20 6 2.061 5.80 42 1.894 13.00 7 2.096 5.60 43 1.895 12.80 8 2.092 5.40 44 1.894 12.60 9 2.082 5.20 45 1.896 12.40 10 2.057 5.00 46 1.900 12.20 11 2.027 4.80 47 1.907 12.00 12 2.007 4.60 48 1.916 11.80 13 2.002 4.40 49 1.924 11.60 14 2.002 4.20 50 1.929 11.40 15 2.001 4.00 51 1.933 11.20 16 1.999 3.80 52 1.933 11.00 17 1.994 3.60 53 1.926 10.80 18 1.990 3.40 54 1.922 10.60 19 1.986 3.20 55 1.915 10.40 20 1.985 3.00 56 1.901 10.20 21 1.985 2.80 57 1.886 10.00 22 1.986 2.60 58 1.854 9.80 23 1.988 2.40 59 1.816 9.60 24 1.989 2.20 60 1.774 9.40 25 1.990 2.00 61 1.755 9.20 26 1.991 1.80 62 1.744 9.00 27 1.994 1.60 63 1.740 8.80 28 1.999 1.40 64 1.735 8.60 29 2.007 1.20 65 1.744 8.40 30 2.016 1.00 66 1.780 8.20 31 2.024 0.80 67 1.933 8.00 32 2.032 0.60 68 2.351 7.80 33 2.030 0.40 69 2.901 7.60 2.006 0.20 70 3.451 7.40 34 35 1.980 0.00 71 4.001 7.20 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 1 May 2002 Table 2 Unrodded F,] for Each Core Height*

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

NRC CORRESPONDENCE SIGNOFF SHEET Revision 1 to Unit 1 Cycle 11 Core Operating Limits Report Correspondence

Title:

NOC-AE-: 02001325 Review Due Date: May 15, 2002 Condition Report No.:

The persons whose initials appear below have personally reviewed the enclosed materials with regards to their area of responsibility and have verified that it is accurate to the best of their knowledge and belief. Initialing below constitutes acceptance of attached assigned commitments.

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