ML23138A130

Cycle 25 Core Operating Limits Report

ML23138A130
Person / Time
Site:	South Texas
Issue date:	05/18/2023
From:	Georgeson C South Texas
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
NOC-AE-23003961, 35468803
Download: ML23138A130 (1)

Text

Nuclear Operating Company.......

S0,1/h Te,,1s f'tojcxl Elecltic Gmemlti(t; SWioll f'O 8or.!89 ihdswarlh, Tb.1s77-181

May 18, 2023 NOC-AE-2 3003961 10 CFR 50.36 STI: 35468803

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555- 0001

South Texas Project Unit 1 Docket No. STN 50- 498 Unit 1 Cycle 25 Core Operating Limits Repor t

In accordance with Technical Specification 6.9.1.6.d, STP Nuclear Operati ng Company submits the attached Core Operating Limits Report (COLR) for Unit 1 Cycle 25. The report covers the core design changes made during the 1 RE24 refueling outage.

There are no commitments in this letter.

If there are any questions regarding this report, please contact Tim Hammons at (361) 972-7347 or me at (361) 972-7806.

Christopher H. Georgeson General Manager, Engineering

tjh

Attachment:

South Texas Project Unit 1 Cycle 25 Core Operating Limits Report, Revision 0

cc: Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 E. Lamar Boulevard Arlington, TX 76011-4511 NOC-AE-23 003961 Attachment

Attachment

South Texas Project Unit 1 Cycle 25 Core Operating Limits Report, Revision 0

~.....

Nuclear Operating Company

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SOUTH TEXAS PROJECT

Unit 1 Cycle 25

CORE OPERATING LIMITS REPORT

U1C25-0

Revision 0

Core Operating Limits Report Page 1 of 17 Unit 1 Cycle 25 Core Operating Limits Report Rev. 0

U1C25-0 Page 2 of 17

1.0 CORE OPERATING LIMITS REPORT

This Core Operating Limits Report for STPEGS Unit 1 Cycle 25 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 method ologies 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 LIMI TS

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.

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

Over-temperature T Setpoint Parameter Values 1 measured reactor vessel T lead/lag time constant, 1 = 8 sec 2 measured reactor vessel T lead/lag time constant, 2 = 3 sec 3 measured reactor vessel T lag time constant, 3 = 2 sec 4 measured reactor vessel average temperature lead/lag time constant, 4 = 28 sec 5 measured reactor vessel average temperature lead/lag time constant, 5 = 4 sec 6 measured reactor vessel average temperature lag time constant, 6 = 2 sec K1 Overtemperature T reactor trip setpoint, K1 = 1.14 K2 Overtemperature T reactor trip setpoint Tavg coefficient, K2 = 0.028/°F K3 Overtemperature T reactor trip setpoint pressure coefficient, K3 = 0.00143/psi T Nominal full power T avg, T 592.0 °F P Nominal RCS pressure, P = 2235 psig f1(I) 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 - qb between -70% and +8%, f1(I) = 0, where qt 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 qt - qb is more negative than -70%, the T Trip Setpoint shall be automatically reduced by 0.0% of its value at RATED THERMAL POWER; and (3) For each percent that qt - qb is more positive than +8%, the T Trip Setpoint shall be automatically reduced by 2.65% of its value at RATED THERMAL POWER.

(Reference 3.6 and Section 4.4.1.2 of Reference 3.7)

Over-power T Setpoint Parameter Values 1 measured reactor vessel T lead/lag time constant, 1 = 8 sec 2 measured reactor vessel T lead/lag time constant, 2 = 3 sec 3 measured reacto r vessel T lag time constant, 3 = 2 sec 6 measured reactor vessel average temperature lag time constant, 6 = 2 sec 7 Time constant utilized in the rate-lag compensator for T avg, 7 = 10 sec K4 Overpower T reactor trip setpoint, K4 = 1.08 K5 Overpower T reactor trip setpoint Tavg rate/lag coefficient, K5 = 0.02/°F for increasing average temperature, and K5 = 0 for decreasing average temperature K6 Overpower T reactor trip setpoint Tavg heatup coefficient K6 = 0.002/°F for T > T, and K6 = 0 for T T T Indicated full power T avg, T 592.0 °F f2(I) = 0 for all (I)

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2.3 SHUTDOWN MARGIN1 (Specification 3.1.1.1):

The SHUTDOWN MARGIN shall be:

2.3.1 Greater than 1.3% 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.

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/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 the document referenced by Technical Specification 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 COLR Section 2.4.3 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 1 (Specification 3.1.3.5 and 3.1.3.6):

2.5.1 All banks shall have the same Full Out Position (FOP) of 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).

1 The Shutdown Margin and Rod Insertion Limits account for the removal of RCCA D6 in Shutdown Bank A.

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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 Constant Axial Offset Control (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 FQRTP = 2.55.

2.7.2 K(Z) is provided in Figure 7.

2.7.3 The F limits for RATED THERMAL POWER (FRTP) within specific core planes xy xy 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 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.

2.7.4 The Fxy limits from Section 2.7.3 above are not applicable in the following core plane regions:

2.7.4.1 Upper and lower c ore plane regions as presented in Table 2, and 2.7.4.2 Grid plane regions as presented in Table 2, and 2.7.4.3 Core plane regions within +/- 2% of core height (+/- 3.36 inches) about the bank demand position of the bank D control rods.

2.7.5 Core Power Distribution Measurement Uncertainty for the Heat Flux Hot Channel Factor 2.7.5.1 If the Power Distribution Monitoring System (PDMS) is operable, as defined in the Technical Requirements Manual Section 3.3.3.12, the core power distribution measurement uncertainty (UFQ) to be applied to the FQ(Z) and Fxy(Z) using the PDMS shall be calculated by:

UFQ = (1.0 + (UQ/100))*UE Where:

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UQ = Uncertainty for power peaking factor as defined in Equation 5-19 from the document referenced by Technical Specification 6.9.1.6.b.11 UE = Engineering uncertainty factor of 1.03.

This uncertainty is calculated and applied automatically by the Power Distribution Monitoring System (PDMS).

2.7.5.2 If the moveable detector system is used, the core power distribution measurement uncertainty (UFQ) to be applied to the FQ(Z) and Fxy(Z) shall be calculated by:

UFQ = UQU*UE Where:

UQU = Base FQ measurement uncertainty of 1.05.

UE = Engineering uncertainty factor of 1.03.

2.8 ENTHALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3):

2.8.1 FRTPH = 1.62

2.8.2 PFH = 0.3 2.8.3 Core Power Distribution Measurement Uncertainty for the Enthalpy Rise Hot Channel Factor 2.8.3.1 If the Power Distribution Monitoring System (PDMS) is operable, as defined in the Technical Requirements Manual Section 3.3.3.12, the core power distribution measurement uncertainty (U ) to be applied to the FN F H H using the PDMS shall be the greater of:

UFH = 1.04 OR UFH = 1.0 + (UH/100)

Where:

UH = Uncertainty for power peaking factor as defined in Equation 5-19 from the document referenced in Technical Specification 6.9.1.6.b.11.

This uncertainty is calculated and applied automatically by the Power Distribution Monitoring System.

2.8.3.2 If the moveable detector system is used, the core power distribution measurement uncertainty (UFH) shall be:

UFH = 1.04

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2.9 DNB PARAMETERS (Specification 3.2.5):

2.9.1 The following DNB -related parameters shall be maintained within the following limits (Nominal Values from Reference 3.1, as annotated below) : 1 2.9.1.1 Reactor Coolant System T avg 595 °F 2, 2.9.1.2 Pressurizer Pressure > 2200 psig 3, 2.9.1.3 Minimum Measured Reactor Coolant System Flow > 403,000 gpm 4.

3.0 REFERENCES

3.1 Letter from A. S. Ganey (Westinghouse) to F. Yilmaz (STPNOC), "South Texas Project Electric Generating Station Unit 1 Cycle 25 Final Reload Evaluation" NF-TG-23-007 (ST-UB-NOC-23000005) dated January 26, 2023.

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

3.3 STPNOC Calculation ZC 07035, Rev. 3, Loop Uncertainty Calculation for RCS Tavg Instrumentation, Section 10.1. (STI 35343289) 3.4 STPNOC Calculation ZC 07032, Rev. 7, Loop Uncertainty Calculation for Narrow Range Pressurizer Pressure Monitoring Instrumentation, Section 2.3, Page 9. (STI 35191115) 3.5 Letter from J. S Wyble (Westinghouse) to T. J. Jordan (STPNOC), STP Nuclear Operating Company Units 1 & 2 Power Uprate PCWG Parameters, ST -WN-NOC-00-000072 dated December 15, 2000. (STI 31218644) 3.6 Letter from J. M. Ralston (Westinghouse) to D. F. Hoppes (STPNOC), South Texas Project Electric Generating Station Units 1 and 2 Documentation of the f 1(I) Function in OTT Setpoint Calculation, NF -TG-11-93 (ST-UB-NOC-11003215) dated November 10, 2011.

(STI 33079478) 3.7 Document RSE-U1, Rev. 14, Unit 1 Cycle 25 Reload Safety Evaluation and Core Operating Limits Report. (CR Action 21-12123-55)

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

2 Includes a 1.9 F measurement uncertainty per Reference 3.3, Page 37.

3 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. Per Technical Specification 3.2.5 Bases, this includes a 10.7 psi measurement uncertainty as read on the QDPS display, which when added to the safety analysis limit of 2189 psig gives the COLR limit listed above.

The 10.7 psi uncertainty is bounded by the 9.6 psi averaged measurement calculated in Reference 3.4.

4 Includes the most-limiting flow measurement uncertainty of 2.8% from Reference 3.5.

.,.. Unit 1 Cycle 25 Nuc le a r Opera tin g Co mpa n y Core Operating Limits Report Rev. 0

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F ig u re 1

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.,.. Unit 1 Cycle 25 Nuclear Operating Compan y Core Operating Limits Report Rev. 0

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Figure 2

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.,.. Unit 1 Cycle 25 Nuclear Operating Compan y Core Operating Limits Report Rev. 0

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Figure 3

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Unit 1 Cycle 25 Core Operating Limits Report Rev. 0

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.,.. Unit 1 Cycle 25 Nucl e ar Opera tin g Compan y Core Operating Limits Report Rev. 0

U1C25-0 Page 12 of 17

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.,.. Unit 1 Cycle 25 Nucl e ar Opera tin g Compan y Core Operating Limits Report Rev. 0

U1C25-0 Page 13 of 17

Figure 6

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.,.. Unit 1 Cycle 25 Nuclear Operating Comp any Core Operating Limits Report Rev. 0

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Figure 7

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Table 1 (Part 1 of 2)

Unrodded Fxy for Each Core Height for Cycle Burnups Less Than 10,000 MWD/MTU (Subject to Exclusion Zones of COLR Section 2.7.4)

Core Height Axial Unrodded Core Height Axial Unrodded (Ft.) Point Fxy (Ft.) Point Fxy 14.0 1 6.937 6.8 37 1.933 13.8 2 5.401 6.6 38 2.003 13.6 3 3.869 6.4 39 1.979 13.4 4 2.564 6.2 40 1.915 13.2 5 2.391 6.0 41 1.872 13.0 6 2.127 5.8 42 1.899 12.8 7 2.049 5.6 43 1.916 12.6 8 2.061 5.4 44 1.920 12.4 9 2.030 5.2 45 1.968 12.2 10 1.985 5.0 46 2.046 12.0 11 1.963 4.8 47 2.065 11.8 12 1.985 4.6 48 2.002 11.6 13 2.034 4.4 49 1.935 11.4 14 2.018 4.2 50 1.952 11.2 15 1.958 4.0 51 1.965 11.0 16 1.924 3.8 52 1.956 10.8 17 1.911 3.6 53 1.965 10.6 18 1.894 3.4 54 2.016 10.4 19 1.876 3.2 55 2.051 10.2 20 1.897 3.0 56 1.995 10.0 21 1.954 2.8 57 1.943 9.8 22 1.980 2.6 58 1.949 9.6 23 1.915 2.4 59 1.957 9.4 24 1.878 2.2 60 1.968 9.2 25 1.883 2.0 61 2.009 9.0 26 1.871 1.8 62 2.095 8.8 27 1.872 1.6 63 2.170 8.6 28 1.890 1.4 64 2.149 8.4 29 1.962 1.2 65 2.117 8.2 30 2.037 1.0 66 2.177 8.0 31 1.977 0.8 67 2.568 7.8 32 1.904 0.6 68 3.469 7.6 33 1.882 0.4 69 4.974 7.4 34 1.900 0.2 70 7.098 7.2 35 1.897 0.0 71 10.595 7.0 36 1.883

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Table 1 (Part 2 of 2)

Unrodded Fxy for Each Core Height for Cycle Burnups Greater Than or Equal to 10,000 MWD/MTU (Subject to Exclusion Zones of COLR Section 2.7.4)

Core Height Axial Unrodded Core Height Axial Unrodded (Ft.) Point Fxy (Ft.) Point Fxy 14.0 1 6.378 6.8 37 2.202 13.8 2 5.087 6.6 38 2.246 13.6 3 3.797 6.4 39 2.210 13.4 4 2.694 6.2 40 2.143 13.2 5 2.550 6.0 41 2.106 13.0 6 2.275 5.8 42 2.097 12.8 7 2.122 5.6 43 2.084 12.6 8 2.065 5.4 44 2.068 12.4 9 2.013 5.2 45 2.089 12.2 10 1.965 5.0 46 2.129 12.0 11 1.973 4.8 47 2.127 11.8 12 2.016 4.6 48 2.065 11.6 13 2.074 4.4 49 2.015 11.4 14 2.067 4.2 50 2.009 11.2 15 2.027 4.0 51 1.996 11.0 16 1.986 3.8 52 1.981 10.8 17 2.012 3.6 53 1.984 10.6 18 2.020 3.4 54 2.024 10.4 19 2.022 3.2 55 2.053 10.2 20 2.057 3.0 56 1.994 10.0 21 2.118 2.8 57 1.927 9.8 22 2.146 2.6 58 1.891 9.6 23 2.104 2.4 59 1.873 9.4 24 2.068 2.2 60 1.864 9.2 25 2.083 2.0 61 1.878 9.0 26 2.094 1.8 62 1.922 8.8 27 2.101 1.6 63 1.949 8.6 28 2.118 1.4 64 1.924 8.4 29 2.170 1.2 65 1.936 8.2 30 2.217 1.0 66 2.044 8.0 31 2.174 0.8 67 2.406 7.8 32 2.132 0.6 68 3.123 7.6 33 2.132 0.4 69 4.215 7.4 34 2.142 0.2 70 5.714 7.2 35 2.151 0.0 71 8.362 7.0 36 2.158

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Table 2 Core and Grid Plane Fxy Exclusion Zones Core Core Core Core Axial Height Height Axial Height Height Point (in.) (%) Top/Bottom Grid Point (in.) (%) Top/Bottom Grid 1 168.0 100.0 Excluded 37 81.6 48.6 2 165.6 98.6 Excluded 38 79.2 47.1 Excluded 3 163.2 97.1 Excluded 39 76.8 45.7 Excluded 4 160.8 95.7 Excluded 40 74.4 44.3 5 158.4 94.3 Excluded Excluded 41 72.0 42.9 6 156.0 92.9 Excluded Excluded 42 69.6 41.4 7 153.6 91.4 43 67.2 40.0 8 151.2 90.0 44 64.8 38.6 9 148.8 88.6 45 62.4 37.1 10 146.4 87.1 46 60.0 35.7 Excluded 11 144.0 85.7 47 57.6 34.3 Excluded 12 141.6 84.3 48 55.2 32.9 Excluded 13 139.2 82.9 Excluded 49 52.8 31.4 14 136.8 81.4 Excluded 50 50.4 30.0 15 134.4 80.0 Excluded 51 48.0 28.6 16 132.0 78.6 52 45.6 27.1 17 129.6 77.1 53 43.2 25.7 18 127.2 75.7 54 40.8 24.3 Excluded 19 124.8 74.3 55 38.4 22.9 Excluded 20 122.4 72.9 56 36.0 21.4 Excluded 21 120.0 71.4 Excluded 57 33.6 20.0 22 117.6 70.0 Excluded 58 31.2 18.6 23 115.2 68.6 Excluded 59 28.8 17.1 24 112.8 67.1 60 26.4 15.7 25 110.4 65.7 61 24.0 14.3 26 108.0 64.3 62 21.6 12.9 Excluded 27 105.6 62.9 63 19.2 11.4 Excluded 28 103.2 61.4 64 16.8 10.0 Excluded 29 100.8 60.0 Excluded 65 14.4 8.6 30 98.4 58.6 Excluded 66 12.0 7.1 Excluded 31 96.0 57.1 Excluded 67 9.6 5.7 Excluded 32 93.6 55.7 68 7.2 4.3 Excluded 33 91.2 54.3 69 4.8 2.9 Excluded Excluded 34 88.8 52.9 70 2.4 1.4 Excluded Excluded 35 86.4 51.4 71 0.0 0.0 Excluded Excluded 36 84.0 50.0