L-2017-036, Core Operating Limits Report, Cycle 29

Core Operating Limits Report, Cycle 29

ML17123A375
Person / Time
Site:	Turkey Point
Issue date:	04/14/2017
From:	Summers T Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2017-036
Download: ML17123A375 (11)

Text

U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Unit 3 Docket No. 50-250 Core Operating Limits Report APR 1 4 2017 L-2017-036 10 CFR 50.36 In accordance with Technical Specification 6.9.1.7, the attached Core Operating Limits Report (COLR) is provided for Turkey Point Unit 3. The COLR is applicable for Unit 3 Cycle 29. Should there be any questions, please contact Mr. Mitch Guth, Licensing Manager, at 305-246-6698.

Sincerely, Summers Regional Vice President

-Southern Region Turkey Point Nuclear Plant Attachments cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Florida Power & Light Company 9760 SW 344th St., Homestead, FL 33035 L___ -Attachment to L-2017-036 Page 1 of 10 Turkey Point Unit 3 Cycle 29 Core Operating Limits Report (COLR) 14A-A1 Attachment to L-2017-036 Page 2of10

1.0 INTRODUCTION

This Core Operating Limits Report for Turkey Point Unit 3 Cycle 29 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 2.1 2.1.1 2.2 2.2.1 2.3 3.1.1.1 2.4 3.1.1.2 2.5 3.1.1.3 2.6 4.1.1.3 2.7 3.1.3.2 2.8 3.1.3.6 2.9 3.2.1 2.10 3.2.2 2.11 3.2.3 2.12 3.2.5 Figure A1 A2 A3 A4 Reactor Core Safety Limits Reactor Trip System Instrumentation Setpoints, Table 2.2-1, Notes 1 & 3 Shutdown Margin Limit for MODES 1, 2, 3, 4 Shutdown Margin Limit for MODE 5 Moderator Temperature Coefficient MTC Surveillance at 300 ppm Analog Rod Position Indication System Control Rod Insertion Limits Axial Flux Difference Heat Flux Hot Channel Factor F 0 (Z) Nuclear Enthalpy Rise Hot Channel Factor DNB Parameters Description Reactor Core Safety Limit -Three Loops in Operation Required Shutdown Margin vs Reactor Coolant Boron Concentration Turkey Point Unit 3 Cycle 29 Rod Insertion Limits vs Thermal Power Axial Flux Difference as a Function of Rated Thermal Power 14A-A2 Page 14A-A3 14A-A3-14A-A4 14A-A4 14A-A4 14A-A5 14A-A5 14A-A5 14A-A5 14A-A5 14A-A6 14A-A6 14A-A6 14A-A7 14A-A8 14A-A9 14A-A10

.. 2.0 OPERATING LIMITS Attachment to L-2017-036 Page 3of10 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 NRG-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(page14A-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 A 1. 2.2 Reactor Trip System Instrumentation Setpoints (TS 2.2.1) NOTE 1 on TS Table 2.2-1 Overtemperature LiT 't1 = Os, 't 2 = Os Lead/Lag compensator on measured LiT 't 3 = 2s Lag compensator on measured Li T K 2 = 0.023/°F 't4 = 25s, 'ts = 3s Time constants utilized in the lead-lag compensator for Tavg 'te = 2s Lag compensator on measured Tavg T'::;; 583.0 Of Indicated Loop Tavg at RATED THERMAL POWER K 3 = 0.00116/psi P' 2: 2235 psig Nominal RCS operating pressure f1(Lil) = 0 for qi -qb between -18% and + 7% For each percent that the magnitude of qt -qb exceeds -18%, the LiT Trip Setpoint shall be automatically reduced by 3.51% of its value at RATED THERMAL POWER; and For each percent that the magnitude of qi -qb exceeds + 7%, the Li T Trip Setpoint shall be automatically reduced by 2.37% of its value at RA TED 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 RA TED THERMAL POWER. 14A-A3 Attachment to L-2017-036 Page 4of10 NOTE 2 on TS Table 2.2-1 Overtemperature (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% span for the channel, 0.2% span for the Pressurizer Pressure channel, and 0.4% span for the channel. No separate Allowable Value is provided for T avg because this function is part of the T value. NOTE 3 on TS Table 2.2-1 Overpower Ki=1.10 Ks z 0.0/°F For increasing average temperature Ks= 0.0 For decreasing average temperature i;7 z 0 s Time constants utilized in the lead-lag compensator for Tavg Ka= 0.0016/°F For T > T" Ka= 0.0 For T:.::; T" T":.::; 583.0 °F Indicated Loop Tavg at RATED THERMAL POWER fz 0 For all NOTE 4 on TS Table 2.2-1 Overpower (Not affected by COLR. included for completeness)

The 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 T avg 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 14A-A8) 2.4 Shutdown Margin Limit for MODE 5 (TS 3.1.1.2) 1.77%

14A-A4

2.5 Moderator

Temperature Coefficient (MTC) (TS 3.1.1.3) + 5.0 X 10-5 Lik/k/°F From 70% RTP to 100% RTP the MTC decreasing linearly 5.0 X 10-5 Lik/k/°F 0.0 X 10-5 Lik/k/°F Less negative than -41.0 x 10-5 Lik/k/°F 2.6 MTC Surveillance at 300 ppm {TS 4.1.1.3) Attachment to L-2017-036 Page 5of10 BOL, HZP, ARO, and from HZP to 70% Rated Thermal Power (RTP) EOL, RTP, ARO Less negative than -35.0 x 10-5 Lik/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-137 49-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 14A-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 14A-A9) 2.9 Axial Flux Difference

{TS 3.2.1) Figure A4 (page 14A-A10) The control rod banks shall be limited in physical insertion as specified in Figure A3 for ARO =229 steps withdrawn.

14A-A5 2.10 Heat Flux Hot Channel Factor FQ(Z) (TS 3.2.2) [Fa]L = 2.30 Attachment to L-2017-036 Page 6 of 10 K(z) = 1.0 For O' z 12' where z is core height in ft 2.11 Nuclear Enthalpy Rise Hot Channel Factor (TS 3.2.3) Ft.HRTP = 1.600 PFt.H = 0.3 2.12 DNB Parameters (TS 3.2.5) RCS Tavg 585.0 °F Pressurizer 2204 psig 14A-A6 2455 psia. Acceptable Qperalioh Attachment to L-2017-036 Page 7of10 Unacceptable Operation I

0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 Core Power (fraction of 2644 MWt) FIGURE A1 Reactor Core Safety Limit -Three Loops in Operation 14A-A7 (0:0, 1.77) 0.5 0 0 FIGUREA2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 500 1000 1500 RCS BORON CONCENTRATION (PPM) 14A-A8 Attachment to L-2017-036 Page 8of10 2000

' ' 23) 220 210.* 200 100, 1ro 170 I1eo .. 15) 'ti ;C 1"[) 13) Ill c: E *100 i 0 9J a.. ro <( 8 70 0:: 60 Bl 4) 3) 20 10 0 FIGURE A3 Attachment to L-2017-036 Page 9of10 Turkey Point Unit 3 Cycle 29 Rod Insertion Limits vs Thermal Power ARO = 229 Steps Withdrawn, Overlap = 101 Steps (Sol.Cl, l2ZSJ / "".,. 121 v / / / / . Mnn A"70 ,, / / _./ v / 6a1 kC / / ./ v v ... ,,.... / v (( 105) / 1V' ,,V ,, / Bia.nk( / ,, ,,V .. rr ,,.. .... .... ' .,., f1? l1 /' r r ./ 0. 10 70 100 14A-A9

, ' " -e..... a: w 0 a. ...J ct :IE a: w :c I-c w .... 0 c Q) l:! Q) a. 120 100 80 60 40 20 0 -50 FIGUREA4 Attachment to L-2017-036 Page10of10 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 3 Cycle 29 (-9 100) (+6,1( 0) j' \ \ / \ UNAC1 I ur ACCEPTAE LE OPE RATION

/ \ (-30,50) ACCEPT A BLE (+, 0,50) OPERAT ON 30 10 0 10 20 30 40 50 Axial Flux Difference

(%) 14A-A10