L-2016-176, Submittal of Core Operating Limits Report Cycle 28 and Cycle 29

Submittal of Core Operating Limits Report Cycle 28 and Cycle 29

ML16265A606
Person / Time
Site:	Turkey Point
Issue date:	09/13/2016
From:	Summers T Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2016-176
Download: ML16265A606 (22)

Text

..

September 13, 2016 L-2016-176 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Core Operating Limits Reports

References:

1. Florida Power and Light Company (FPL) letter L-2015-271, "Turkey Point Unit 3 Docket No. 50-250, Core Operating Limits Report," dated November 16, 2015.

2. Florida Power and Light Company (FPL) letter L-2016-081, "Turkey Point Unit 4 Docket No. 50-251', Core Operating Limits Report," dated April 14, 2016.

3. USNRC letter, "Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Issuance of Amendments Regarding Technical Specifications for Moderator Temperature Coefficient Measurements (CAC NOS. MF6783 and MF6784,." Dated June 20, 2016.

In accordance with Technical Specification 6.9.1.7, the Core Operating Limits Report (COLR) for Turkey Point Unit 3 Cycle 28 was submitted by Reference 1. The COLR for Turkey Point Unit 4 Cycle 29 was submitted by Reference 2.

On June 20, 2016, the U.S. Nuclear Regulatory Commission (NRC) issued Amendments 271 and 266 to Renewed Facility Operating Licenses (RFOLs) No. DPR-31 and DPR-41 for Turkey Point Units 3 and 4, respectively (Reference 3). License Amendments 271 and 266 revised Technical Specification (TS) 3/4.1, "Reactivity Control Systems, Moderator Temperature Coefficient," Surveillance Requirement 4.1.1.3.b to allow the near end-of-life Moderator Temperature Coefficient (MTC) measurement requirement to not be performed by placing a set of conditions on reactor core operation. The amendments also revised TS 6.9.1. 7, "Core Operating Limits Report," to include the analytical methods used to support the suspension of the near end-of-life MTC. In addition, the amendments require that the physics codes used to support the suspension of the near end-of-life MTC be specified in the COLR for the current cycle.

Florida Power & Light Company 9760 SW 344 St Homestead, FL 33035

L-2016-176 Page2 Amendments 271 and 266 have been implemented; therefore, in accordance with Technical Specification 6.9. 1. 7, this letter provides the updated COLRs for Turkey Point Units 3 and 4.

Attachment 1 provides the revised COLR for Turkey Point Unit 3. The COLR is applicable for Unit 3 Cycle 28. Attachment 2 provides the revised COLR for Turkey Point Unit 4. The COLR is applicable for Unit 4 Cycle 29. The attachments to this letter replace the COLRs submitted by References 1 and 2 in their entirety.

Should there be any questions, please contact Mr. Mitch Guth, Licensing Manager, at 305-246-6698.

Sincerely, "7-l~,......___

Ahomas Summers Site Vice President Turkey Point Nuclear Plant Attachments cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant

Attachment 1 to L-2016-176 Page 1 of 10 Revised Turkey Point Unit 3 Cycle 28 Core Operating Limits Report (COLR) 14A-A1

Attachment 1 to L-2016-176 Page 2of10

1.0 INTRODUCTION

This Core Operating Limits Report for Turkey Point Unit 3 Cycle 28 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 14A-A3 2.2 2.2.1 Reactor Trip System Instrumentation Setpoints, Table 2.2-1, Notes 1 & 3 14A-A3-14A-A4 2.3 3.1.1.1 Shutdown Margin Limit for MODES 1, 2, 3, 4 14A-A4 2.4 3.1.1.2 Shutdown Margin Limit for MODE 5 14A-A4 2.5 3.1.1.3 Moderator Temperature Coefficient 14A-A5 2.6 4.1.1.3 MTC Surveillance at 300 ppm 14A-A5 2.7 3.1.3.2 Analog Rod Position Indication System 14A-A5 2.8' 3.1.3.6 Control Rod Insertion Limits 14A-A5 2.9 3.2.1 Axial Flux Difference 14A-A5 2.10 3.2.2 Heat Flux Hot Channel Factor F0 (Z) 14A-A6 2.11 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor 14A-A6 2.12 3.2.5 DNB Parameters 14A-A6 Figure Description A1 Reactor Core Safety Limit - Three Loops in Operation 14A-A7 A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 14A-A8 A3 Turkey Point Unit 3 Cycle 28 Rod Insertion Limits vs Thermal Power 14A-A9 A4 Axial Flux Difference as a Function of Rated Thermal Power 14A-A10 14A-A2

Attachment 1 to L-2016-176 Page 3of10 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 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 A 1(page 14A-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 L1T

• 1 = Os, *2 = Os Lead/Lag compensator on measured L1T

't3 =2s Lag compensator on measured L1T K1=1.31 K2 = 0.023/°F

't4 = 25s, *s = 3s Time constants utilized in the lead-lag compensator for T avg

• e =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(111) = 0 for qt - qb between - 18% and + 7%

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

the L1T 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 L1T 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 14A-A3

Attachment 1 to L-2016-176 Page 4of10 NOTE 2 on TS Table 2.2-1 Overtemperature LiT (Not affected by COLR. included for completeness)

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

NOTE 3 on TS Table 2.2-1 Overpower LiT

~=1.10 Ks ~ 0.0/°F For increasing average temperature Ks= 0.0 For decreasing average temperature

• 7 ~ 0s Time constants utilized in the lead-lag compensator fo_r T avg Ka= 0.0016/°F For T > T" For T:.::; T" T":.::; 583.0 °F Indicated Loop Tavg at RATED THERMAL POWER fz (iii)= 0 For all Lil NOTE 4 on TS Table 2.2-1 Overpower LiT (Not affected by COLR. included for completeness)

The Overpower LiT function Allowable Value shall not exceed the nominal trip setpoint by more than 0.5% LiT span for the LiT channel. No separate Allowable Value is provided for T avg because this function is part of the LiT 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% Lik/k 14A-A4

Attachment 1 to L-2016-176 Page 5of10 2.5 Moderator Temperature Coefficient (MTC) (TS 3.1.1.3)

~ + 5.0 X 10-5 i1k/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 i1k/k/°F to~ 0.0 X 10-5 i1k/k/°F Less negative than - 41.0 x 1ff5 i1k/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 i1k/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 14A-A9) The All Rods Out (ARO) position for all shutdown Banks and Control Banks is defined to be 228 steps withdrawn.

2.8 Control Rod Insertion Limits (TS 3.1.3.6)

Figure A3 (page 14A-A9) The control rod banks shall be limited in physical insertion as specified in Figure A3 for ARO =228 steps withdrawn.

2.9 Axial Flux Difference (TS 3.2.1)

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

Attachment 1 to L-2016-176 Page 6of10 2.10 Heat Flux Hot Channel Factor Fa(Z} (TS 3.2.2)

[Fa]L = 2.30 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 Pressure ~ 2204 psig 14A-A6

Attachment 1 to L-2016-176 Page 7 of 10 2455 psia Unacceptable Operation Acceptable Operation 0.0 0.2 0.4 0.6 0 .6 1.0 1.2 1.4 Core Power (fract ion of 2644 MWt)

FIGURE A1 Reactor Core Safety Limit- Three Loops in Operation 14A-A7

Attachment 1 to L-2016-176 Pag e 8 of 10 FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 2

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0 500 1000 1500 2000 RCS BORON CONCENTRATION (PPM) 14A-A8

Attachment 1 to L-2016-176 Page 9 of 10 FIGURE A3 Turkey Point Unit 3 Cycle 28 Rod Insertion Limits vs Thermal Power ARO = 228 Steps Withd rawn , Overlap = 100 Steps 228 v

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0 0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power 14A-A9

Attachment 1 to L-2016-176 Page 10of10 FIGUREA4 Axial Flux Difference as a Function of Rated Thermal Power Turkey Point Unit 3 Cycle 28 120

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14A-A10

Attachment 2 to L-2016-176 Page1of10 Revised Turkey Point Unit 4 Cycle 29 Core Operating Limits Report (COLR) 14B-A1

Attachment 2 to L-2016-176 Page 2of10 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Turkey Point Unit 4 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 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 F0 (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 148-AS A3 Turkey Point Unit 4 Cycle 29 Rod Insertion Limits vs Thermal Power 14B-A9 A4 Axial Flux Difference as a Function of Rated Thermal Power 14B-A10 14B-A1

Attachment2 to L-2016-176 Page 3of10 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR 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 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(page14B-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 t1 =Os, =Os t2 Lead/Lag compensator on measured ~T Lag compensator on measured ~T K1=1.31 K2 = 0.023/°F t4 = 25s, ts = 3s Time constants utilized in the lead-lag compensator for Tavg Lag compensator on measured Tavg T':::;; 583.0 °F Indicated Loop Tavg at RATED THERMAL POWER Ks = 0.00116/psi P' z 2235 psig Nominal RCS operating pressure f 1(~I) = 0 for qt - qb between - 18% and + 7%

For each percent that the magnitude of% - 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 % and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and q1 + qb is total THERMAL POWER in percent of RATED THERMAL POWER.

14B-A3

Attachment 2 to L-2016-176 Page 4of10 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR NOTE 2 on TS Table 2.2-1 Overtemperature LiT (Not affected by COLR. included for completeness)

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

NOTE 3 on TS Table 2.2-1 Overpower LiT Ki=1.10 Ks ; : : 0.0/°F For increasing average temperature Ks= 0.0 For decreasing average temperature

• 7 ;;:::: 0s Time constants utilized in the lead-lag compensator for T avg K6 = 0.0016/°F For T > T" Ks= 0.0 For T::; T" T"::; 583.0°F Indicated Loop Tavg at RATED THERMAL POWER f2 (Lil) = 0 For all Lil NOTE 4 on TS Table 2.2-1 Overpower LiT (Not affected by COLR. included for completeness)

The Overpower LiT function Allowable Value shall not exceed the nominal trip setpoint by more than 0.5% LiT span for the LiT channel. No separate Allowable Value is provided for T avg because this function is part of the LiT 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% Liklk 14B-A4

Attachment 2 to L-2016-176 Page 5of10 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR 2.5 Moderator Temperature Coefficient (MTC) (TS 3.1.1.3)

~ + 5.0 X 10-5 Lik/k/°F BOL, HZP, ARO, and from HZP to 70% Rated Thermal Power (RTP)

From 70% RTP to 100% RTP the MTG decreasing linearly from ~ + 5.0 X 10-5 Lik/k/°F to~ 0.0 X 10- Lik/k/°F 5

Less negative than - 41.0 x 10-5 Lik/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 Lik/k/°F (-35 pcm/°F) Within 7 EFPD of reaching equilibrium boron concentration of 300 ppm.

The Revised Predicted near - EOL 300 ppm MTG shall be calculated using the algorithm contained in WCAP-137 49-P-A:

Revised Predicted MTG = Predicted MTG + AFD Correction - 3 pcm/°F If the Revised Predicted MTG 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 MTG 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-PfANG 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) 148-AS

Attachment 2 to L-2016-176 Page 6of10 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR 2.10 Heat Flux Hot Channel Factor Fa(Z) (TS 3.2.2)

[Fo]L = 2.30 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)

PFb.H = 0.3 2.12 DNB Parameters (TS 3.2.5)

RCS Tavg _:::. 585.0°F Pressurizer Pressure .::: 2204 psig 148-A6

Attachment 2 to L-2016-176 Page 7 of 10 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR 2455 psia Unacceptable Operatfon t

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FIGURE A1 Reactor Core Safety Limit- Three Loops in Operation 14B-A7

Attachment 2 to L-2016-176 Page 8 of 10 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR FIGURE A2 Required Shutdown Margin vs Reactor Coolant Boron Concentration 2

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Attachment 2 to L-2016-176 Page 9of10 REVISED TURKEY POINT UNIT 4 CYCLE 29 COLR FIGUREA3 Turkey Point Unit 4 Cycle 29 Rod Insertion Limits vs Thermal Power

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