L-2019-068, Core Operating Limits Report

Core Operating Limits Report

ML19091A016
Person / Time
Site:	Turkey Point
Issue date:	03/29/2019
From:	Hess R Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2019-068
Download: ML19091A016 (11)

Text

March 29, 2019 L-2019-068 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn : Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Unit 4 Docket No. 50-251 Core Operating Limits Report In accordance with Technical Specification 6.9.1.7, the attached Core Operating Limits Report (COLR) is provided for Turkey Point Unit 4. The COLR is applicable for Unit 4 Cycle 31.

Should there be any questions, please contact Mr. Robert Hess, Licensing Manager, at 305-246-4112.

Licensing Manager Turkey Point Nuclear Plant Attachments cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Florida Power & Light Company 9760 SW 3441h St., Homestead, FL 33035

Attachment to L-2019-068 Page 1 of 10 Turkey Point Unit 4 Cycle 31 Core Operating Limits Report (COLR) 14B-A1

Attachment to L-2019-068 Page 2 of 10

1.0 INTRODUCTION

This Core Operating Limits Report for Turkey Point Unit 4 Cycle 31 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7.

The Technical Specifications (TS) affected by this report are listed below with the section and page for each one of the TS addressed in this COLR document.

Section Technical Specification Page 2.1 2.1.1 Reactor Core Safety Limits 14B-A3 2.2 2.2.1 Reactor Trip System Instrumentation Setpoints, Table 2.2-1, Notes 1 & 3 14B-A3-14B-A4 2.3 3.1.1.1 Shutdown Margin Limit for MODES 1, 2, 3, 4 14B-A4 2.4 3.1.1.2 Shutdown Margin Limit for MODE 5 14B-A4 2.5 3.1.1.3 Moderator Temperature Coefficient 14B-A5 2.6 4.1.1.3 MTC Surveillance at 300 ppm 14B-A5 2.7 3.1.3.2 Analog Rod Position Indication System 14B-A5 2.8 3.1.3.6 Control Rod Insertion Limits 14B-A5 2.9 3.2.1 Axial Flux Difference 14B-A5 2.10 3.2.2 Heat Flux Hot Channel Factor FQ(Z) 14B-A6 2.11 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor 14B-A6 2.12 3.2.5 DNB Parameters 14B-A6 Figure Description A1 Reactor Core Safety Limit - Three Loops in Operation 14B-A7 A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A8 A3 Turkey Point Unit 4 Cycle 31 Rod Insertion Limits vs Thermal Power 14B-A9 A4 Axial Flux Difference as a Function of Rated Thermal Power 14B-A10 14B-A2

Attachment to L-2019-068 Page 3 of 10 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in the Introduction are presented below and listed sequentially by Technical Specification (TS). These limits have been developed using the NRC-approved methodologies specified in TS 6.9.1.7.

2.1 Reactor Core Safety Limits - Three Loops in Operation (TS 2.1.1)

- Figure A1(page 14B-A7) In Modes 1 and 2, the combination of Thermal Power, reactor coolant system highest loop average temperature and pressurizer pressure shall not exceed the limits in Figure A1.

2.2 Reactor Trip System Instrumentation Setpoints (TS 2.2.1)

NOTE 1 on TS Table 2.2-1 Overtemperature T

- 1 = 0s, 2 = 0s Lead/Lag compensator on measured T

- 3 = 2s Lag compensator on measured T

- K1 = 1.31

- K2 = 0.023/F

- 4 = 25s, 5 = 3s Time constants utilized in the lead-lag compensator for Tavg

- 6 = 2s Lag compensator on measured Tavg

- T 583.0 F Indicated Loop Tavg at RATED THERMAL POWER

- K3 = 0.00116/psi

- P 2235 psig Nominal RCS operating pressure

- f1(I) = 0 for qt - qb between - 18% and + 7%

For each percent that the magnitude of qt - qb exceeds - 18%,

the T Trip Setpoint shall be automatically reduced by 3.51%

of its value at RATED THERMAL POWER; and For each percent that the magnitude of qt - qb exceeds + 7%,

the T Trip Setpoint shall be automatically reduced by 2.37%

of its value at RATED THERMAL POWER.

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.

14B-A3

Attachment to L-2019-068 Page 4 of 10 NOTE 2 on TS Table 2.2-1 Overtemperature T (Not affected by COLR, included for completeness)

The Overtemperature T function Allowable Value shall not exceed the nominal trip setpoint by more than 0.5% T span for the T channel, 0.2% T span for the Pressurizer Pressure channel, and 0.4% T span for the f(I) channel. No separate Allowable Value is provided for Tavg because this function is part of the T value.

NOTE 3 on TS Table 2.2-1 Overpower T

- K4 = 1.10

- K5 0.0/F For increasing average temperature

- K5 = 0.0 For decreasing average temperature

- 7 0 s Time constants utilized in the lead-lag compensator for Tavg

- K6 = 0.0016/F For T > T

- K6 = 0.0 For T T

- T 583.0 F Indicated Loop Tavg at RATED THERMAL POWER

- f2 (I) = 0 For all I NOTE 4 on TS Table 2.2-1 Overpower T (Not affected by COLR, included for completeness)

The Overpower T function Allowable Value shall not exceed the nominal trip setpoint by more than 0.5% T span for the T channel. No separate Allowable Value is provided for Tavg because this function is part of the T value.

2.3 Shutdown Margin Limit for MODES 1, 2, 3 and 4 (TS 3.1.1.1)

- Figure A2 (page 14B-A8) 2.4 Shutdown Margin Limit for MODE 5 (TS 3.1.1.2)

- > 1.77% k/k 14B-A4

Attachment to L-2019-068 Page 5 of 10 2.5 Moderator Temperature Coefficient (MTC) (TS 3.1.1.3)

- < + 5.0 x 10-5 k/k/F BOL, HZP, ARO, and from HZP to 70% Rated Thermal Power (RTP)

- From 70% RTP to 100% RTP the MTC decreasing linearly from < + 5.0 x 10-5 k/k/F to < 0.0 x 10-5 k/k/F

- Less negative than - 41.0 x 10-5 k/k/F EOL, RTP, ARO 2.6 MTC Surveillance at 300 ppm (TS 4.1.1.3)

- Less negative than - 35.0 x 10-5 k/k/F(-35 pcm/F) Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm.

- The Revised Predicted near - EOL 300 ppm MTC shall be calculated using the algorithm contained in WCAP-13749-P-A:

Revised Predicted MTC = Predicted MTC + AFD Correction - 3 pcm/F If the Revised Predicted MTC is less negative than the SR 4.1.1.3.b 300 ppm surveillance limit and all the benchmark criteria contained in the surveillance procedure are met, then an MTC measurement in accordance with SR 4.1.1.3.b is not required to be performed.

The neutronics methods used with WCAP-13749-P-A are those described in WCAP-11596-P-A, Qualification of the Phoenix-P/ANC Nuclear Design System for Pressurized Water Reactor Cores, June 1988.

2.7 Analog Rod Position Indication System (TS 3.1.3.2)

- Figure A3 (page 14B-A9) The All Rods Out (ARO) position for all shutdown Banks and Control Banks is defined to be 229 steps withdrawn.

2.8 Control Rod Insertion Limits (TS 3.1.3.6)

- Figure A3 (page 14B-A9) The control rod banks shall be limited in physical insertion as specified in Figure A3 for ARO =229 steps withdrawn.

2.9 Axial Flux Difference (TS 3.2.1)

- Figure A4 (page 14B-A10) 14B-A5

Attachment to L-2019-068 Page 6 of 10 2.10 Heat Flux Hot Channel Factor FQ(Z) (TS 3.2.2)

- [FQ]L = 2.30

- K(z) = 1.0 For 0 < z < 12 where z is core height in ft 2.11 Nuclear Enthalpy Rise Hot Channel Factor (TS 3.2.3)

- FHRTP = 1.600 PFH = 0.3 2.12 DNB Parameters (TS 3.2.5)

- RCS Tavg < 585.0 oF

- Pressurizer Pressure > 2204 psig 14B-A6

Attachment to L-2019-068 Page 7 of 10 FIGURE A1 Reactor Core Safety Limit - Three Loops in Operation FIGURE A1 FIGURE A1 Reactor Core Safety Limit - Three Loops in Operation 14B-A7

Attachment to L-2019-068 Page 8 of 10 FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14B-A8

Attachment to L-2019-068 Page 9 of 10 FIGURE A3 Turkey Point Unit 4 Cycle 31 Rod Insertion Limits vs Thermal Power ARO = 229 Steps Withdrawn, Overlap = 101 Steps 230 (64.0,229) 220 210 (55.2,212) 200 190 RCCA Position (steps withdrawn) 180 (100,171) 170 160 150 Bank C 140 130 120 110 (0,105) 100 90 80 Bank D 70 60 50 40 30 20 10 (12,0) 0 0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power 14B-A9

Attachment to L-2019-068 Page 10 of 10 FIGURE A4 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 4 Cycle 31 14B-A10