NOC-AE-05001946, Cycle 12 Core Operating Limits Report

Cycle 12 Core Operating Limits Report

ML053180173
Person / Time
Site:	South Texas
Issue date:	11/03/2005
From:	Leazar D South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NOC-AE-05001946, STI: 31951676
Download: ML053180173 (17)

Text

l South Te sPn/d EWledrc a-nMSSWIM P. Bar 2829 aredh,Tbas 77483 November 3, 2005 NOC-AE-05001946 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 2 Docket No. STN 50-499 Unit 2 Cycle 12 Core Operating Limits Report In accordance with Technical Specification 6.9.1.6.d, the attached Core Operating Limits Report is submitted for Unit 2 Cycle 12. This report reflects core design changes made during the 2RE1 1 refueling outage.

There are no commitments in this letter.

If there are any questions concerning this report, please contact Joe Loya at (361) 972-7922 or me at (361) 972-7795.

,p,- David A. Leazar Director, Nuclear Fuel & Analysis jal

Attachment:

Unit 2 Cycle 12 Core Operating Limits Report, Rev. 0.

STI: 31951676

NOC-AE-05001 946 Page 2 of 2 cc:

(paper copy) (electronic copy)

Bruce S. Mallett A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Mohan C. Thadani Arlington, Texas 76011-8064 U. S. Nuclear Regulatory Commission Richard A. Ratliff Jack A. Fusco Bureau of Radiation Control Michael A. Reed Texas Department of State Health Services Texas Genco, LP 1100 West 49th Street Austin, TX 78756-3189 Jeffrey Cruz C. Kirksey U. S. Nuclear Regulatory Commission City of Austin P. 0. Box 289, Mail Code: MN1 16 Wadsworth, TX 77483 Jon C. Wood Cox Smith Matthews C. M. Canady J. J. Nesrsta City of Austin R. K. Temple Electric Utility Department E. Alarcon 721 Barton Springs Road City Public Service Austin, TX 78704 STI: 31951676

39 YYWD Io Nucl ar Operating Company SOUTH TEXAS PROJECT Unit 2 Cycle 12 CORE OPERATING LIMITS REPORT Revision 0 Core Operating Limits Reporo Page I of 15

Unit 2 Cycle 12 I - Core Operating Limits Report Rev. 0 Page 2 of 15 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for STPEGS Unit 2 Cycle 12 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 (Tvg) 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.

A -Unit 2 Cycle 12

, .2 Core Operating Limits Report Rev. 0 Page 3 of 15 2.2.2 The Over-temperature AT and Over-power AT setpoint parameter values are listed below:

Over-temperature AT Setpoint Parameter Values xl 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, r3 = 2 sec T4 measured reactor vessel average temperature lead/lag time constant, T4 = 28 sec T5 measured reactor vessel average temperature lead/lag time constant, x5 = 4 sec x6 measured reactor vessel average temperature lag time constant, T6= 2 sec K, Overtemperature AT reactor trip setpoint, KI = 1.14

• K2 Overtemperature AT reactor trip setpoint Tavg coefficient, K2 = 0.028/ 0 F K3 Overtemperature AT reactor trip setpoint pressure coefficient, K3 = 0.001 43/psig T' Nominal full power Tavg, T'< 592.0 'F P' Nominal RCS pressure, P' = 2235 psig f1 (Al) 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:

(I) For q, - qb between -70% and +8%, f(AI) = 0, where q, and qt are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and q,+ qb is total THERMAL POWER in percent of RATED THERMAL POWER; (2) For each percent that the magnitude of qt - qb exceeds -70%, the AT Trip Setpoint shall be automatically reduced by 0.0% of its value at RATED THERMAL POWER; and (3) For each percent that the magnitude of q, - 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 Tl measured reactor vessel AT lead/lag time constant, Tl = 8 sec T2 measured reactor vessel AT lead/lag time constant, x2 = 3 sec 13 measured reactor vessel AT lag time constant, T3 = 2 sec T6 measured reactor vessel average temperature lag time constant, T6 =2 sec 17 Time constant utilized in the rate-lag compensator for T[vg, T7 = 10 Sec K4 Overpower AT reactor trip setpoint, K4 = 1.08 Ks Overpower AT reactor trip setpoint T.vg ratc/lag coefficient, Ks = 0.02/0 F for increasing average temperature, and Ks = 0 for decreasing average temperature K6 Overpower AT reactor trip setpoint Tavg heatup coefficient K6 = 0.002/0 F for T>T",andK 6 = OforT< T" T" Indicated full power Tayg T'< 592.0 TF f2 (AI) = 0 for all (Al)

T M NuIarOpVr"ting p Unit 2 Cycle 12 Core Operating Limits Report Rev. 0 W AF N--Page 4 of IS 2.3 SHUTDOWN MARGIN (Specification 3.1.1.1):

The SHUTDOWN MARGIN shall be:

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

• See Special Test Exception 3. 10.1 2.3.2 Greater than the limits in Figure 2 for MODES 3 and 4.

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

2.4 MODERATOR TEMPERATURE COEFFICIENT (Specification 3.1.1.3):

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

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

2.4.3 The 300 ppm, ARO, HFP, MTC shall be less negative than -53.6 pcm/PF (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. 0:

Revised Predicted MTC = Predicted MTC + AFD Correction - 3 pcmI0 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 either 255 steps withdrawn or 259 steps withdrawn.

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

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

Unit 2 Cycle 12 aOprrorng Core Operating Limits Report Rev. 0 O' APage 5 of 15 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 FRTP = 2.55.

2.7.2 K(Z) is provided in Figure 7.

2.7.3 The Fxy limits for RATED THERMAL POWER (FRyTp) 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 I for all unrodded core planes.

2.7.3.3 PFXy = 0.2.

These Fey 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 Fy 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.

Unit 2 Cycle 12 AuZTr"pang ~ Core Operating Limits Report Rev. 0

~ N AF- Pagc 6of 15 2.8 ENTHALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3):

2.8.1 FH= 1.557' 2.8.2 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: 2 2.9.1.1 Reactor Coolant System Tavg, < 595 'F 3, 2.9.1.2 Pressurizer Pressure, > 2200 psig4, 2.9.1.3 Minimum Measured Reactor Coolant System Flow 5 > 403,000 gpm.

3.0 REFERENCES

3.1 Letter from D. E. Robinson (Westinghouse) to D. F. Iloppes (STPNOC), "South Texas Project Nuclear Operating Company South Texas Project Electric Generating Station Unit 2 Cycle 12 Final Reload Evaluation (RE) Revision 2," ST-UB-NOC-05002587, Rev. 2, October 21, 2005.

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

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

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

3.5 Condition Report Engineering Evaluation 04-5927-9, Revision 0, "Reload Safety Evaluation and Core Operating Limits Report for South Texas Unit 2 Cycle 12."

Applies to all fuel in the Unit 2 Cycle 12 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 'F 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 9.6 PSI measurement uncertainty as read on QDPS display per Reference 3.4.

5 Includes a 2.8% flow measurement uncertainty.

0 T Unit 2 Cycle 12 Rev. 0 NuclearOptlng ' ny Core Operating Limits Report Page 7 of 15 Figure 1 Reactor Core Safety Limits - Four Loops in Operation 680 660 640 620 C

C0 us U) 600 580 560 540 0 20 40 60 80 100 120 140 Rated Thermal Power (%)

Unit 2 Cycle 12 uAr Opering y Core Operating Limits Report Rev. 0 PageS ofl5 Figure 2 Required Shutdown Margin for Modes 3 & 4 7.0

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M M Unit 2 Cycle 12 Rev. 0 NuclarOpenUng pn Core Operating Limits Report Page 9 of 15 Figure 3 Required Shutdownv Margin for Mode 5 7.0 6.0 _____ W __

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r T M .Unit 2 Cycle 12 O pN n9 _ Core Operating Limits Report Rev. 0 Page 10 of 15 Figure 4 MTC versus Power Level 7.0 6.0 z~L I UnacceptableOperati3-F I I .

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/, - Unit 2 Cycle 12 rOpertin Core Operating Limits Report Rev. 0 Pagc II of 15 Figure 5 Control Rod Insertion Limits* versus Power Level 260 . I II I I (23,259): 122StepOvelaplL. II I I I I (79,259): 122StcpOvallp 240 I I1 , 255 I 4+ 1(77,255): 118 StepOvca 220 200 180 s

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.Tr Unit 2 Cycle 12 Nuclear Operating Company Core Operating Limits Report Rev. 0 Page 12 of 15 Figure 6 AFD Limits versus PowerLcvel 120 110 VHi Unaccept!b l I Ir!1 - U It c p b +.LL I I: I tillH , 1 S ' ,

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I -tUnit 2 Cycle 12 NuclearOperating m Core Operating Limits Report Rev. 0 Page 13 of 15 Figure 7 K(Z) - Normalized FQ(Z) verus Core Height 1.2 I! ! I Il II - i ILI DU=IIFTI 7

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A Nr "Ait Unit 2 Cycle 12 Core

Operating Limits Report Rev. 0 W Page 14 ofi5 Table 1 (Part I of 2)

Unrodded Fy 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 5.271 6.80 37 1.955 13.80 2 4.497 6.60 38 1.948 13.60 3 3.723 6.40 39 1.940 13.40 4 2.949 6.20 40 1.933 13.20 5 2.563 6.00 41 1.928 13.00 6 2.303 5.80 42 1.927 12.80 7 2.269 5.60 43 1.927 12.60 8 2.209 5.40 44 1.928 12.40 . 9 2.156 5.20 45 1.933 12.20 10 2.104 5.00 46 1.938 12.00 11 2.073 4.80 47 1.946 11.80 12 2.053 4.60 48 1.955 11.60 13 2.043 4.40 49 1;960 11.40 14 2.037 4.20 50 1.965 11.20 15 2.033 4.00 51 1.968 11.00 16 2.029 3.80 52 1.965 10.80 17 2.023 3.60 53 1.958 10.60 18 2.016 3.40 54 1.954 10.40 19 2.010 3.20 55 1.952 10.20 20 2.010 3.00 56 1.952 10.00 21 2.010 2.80 57 1.945 9.80 22 2.010 2.60 58 1.944 9.60 23 2.014 2.40 59 1.944 9.40 24 2.017 2.20 60 1.945 9.20 25 2.021 2.00 61 1.948 9.00 26 2.026 1.80 62 1.948 8.80 27 2.034 1.60 63 1.945 8.60 28 2.043 1.40 64 1.957 8.40 29 2.054 1.20 65 1.980 8.20 30 2.065 1.00 66 2.031 8.00 31 2.073 0.80 67 2.229 7.80 32 2.069 0.60 68 2.756 7.60 33 2.054 0.40 69 3.447 7.40 34 2.038 0.20 70 4.138 7.20 35 2.010 0.00 71 4.829 7.00 36 1.976

r Tx Opff ngmny Unit 2 Cycle 12 Core Operating Limits Report Rev. 0 Page 15 of IS Table I (Part 2 of 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 4.128 6.80 37 2.142 13.80 2 3.681 6.60 38 2.141 13.60 3 3.234 6.40 39 2.129 13.40 4 2.788 6.20 40 2.116 13.20 5 2.497 6.00 41 2.102 13.00 6 2.254 5.80 42 2.092 12.80 7 2.190 5.60 43 2.081 12.60 8 2.133 5.40 44 2.071 12.40 9 2.084 5.20 45 2.060 12.20 10 2.043 5.00 46 2.051 12.00 11 2.014 4.80 47 2.042 11.80 12 2.013 4.60 48 2.035 11.60 13 2.017 4.40 49 2.025 11.40 14 2.026 4.20 50 2.015 11.20 15 2.031 4.00 51 2.003 11.00 16 2.036 3.80 52 1.992 10.80 17 2.042 3.60 53 1.982 10.60 18 2.045 3.40 54 1.972 10.40 19 2.046 3.20 55 1.960 10.20 20 2.048 3.00 56 1.944 10.00 21 2.049 2.80 57 1.925 9.80 22 2.051 2.60 58 1.899 9.60 23 2.054 2.40 59 1.873 9.40 24 2.058 2.20 60 1.846 9.20 25 2.062 2.00 61 1.837 9.00 26 2.066 1.80 62 1.833 8.80 27 2.069 1.60 63 1.832 8.60 28 2.073 1.40 64 1.832 8.40 29 2.078 1.20 65 1.862 8.20 30 2.084 1.00 66 1.932 8.00 31 2.091 0.80 67 2.144 7.80 32 2.099 0.60 68 2.520 7.60 33 2.107 0.40 69 2.976 7.40 34 2.116 0.20 70 3.433 7.20 35 2.127 0.00 71 3.889

.7.00 36 2.137