Text

Core Operating Limits Report, Cycle 24
	ML25147A139
Person / Time
Site:	Millstone
Issue date:	05/27/2025
From:	Goolsbey M; Dominion Energy Nuclear Connecticut
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	25-146
	Download: ML25147A139 (1)
	v • d • e

Dominion Energy Nuclear Connecticut, Inc.

Millstone Power Station 314 Rope Ferry Road, Waterford, CT 06385 DominionEnergy.com U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 MAY 2 7 2025 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 CORE OPERATING LIMITS REPORT, CYCLE 24 Serial No.

NSSL/TFO Docket No.

License No.25-146 RO 50-423 NPF-49 In accordance with the Millstone Power Station Unit 3 (MPS3) Technical Specifications (TSs), Section 6.9.1.6.d, Dominion Energy Nuclear Connecticut, Inc., hereby submits, as, the Cycle 24 Core Operating Limits Report (COLR).

MPS3 Cycle 24 (M3C24) is the first cycle in the transition from the Westinghouse RFA-2 fuel product to the Framatome GAIA fuel product. A summary of the changes to the MPS3 COLR for Cycle 24 include:

(1) Administrative changes to increment the cycle number from 23 to 24 (2) Overtemperature 11 T and Overpower 11 T penalty constants, K-and f1 (111) terms (COLR Table 2.2-1)

(3) Required Shutdown Margin for MODE 5 with Reactor Coolant Systems (RCS) Loops Filled (COLR Figure 4)

(4) Required Shutdown Margin for MODE 5 with RCS Loops Not Filled (COLR Figure 5)

(5) M3C24 penalty factors for flux map analysis (COLR Table 1)

(6) M3C24 operating space reductions for FQ exceeding its non-equilibrium limits (COLR Table 2)

The M3C24 COLR has been incorporated into the MPS3 Technical Requirements Manual.

If you have any questions or require additional information, please contact Lori K. Kelley at (860) 447-1791.

Sincerely, 1~

\\J, ~ oo/

Mark W. :;':Jey Director-Nuclear Station Safety, & Licensing-Millstone

Enclosures:

1. Appendix 8.1, Core Operating Limits Report, Cycle 24 Commitments made in this letter: None

cc:

Regional Administrator U.S. Nuclear Regulatory Commission Region I 475 Allendale Road, Suite 102 King of Prussia, PA 19406-1415 R. V. Guzman Serial No.25-146 Docket No. 50-423 Core Operating Limits Report, Cycle 24 Page 2 of 2 Senior Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT CYCLE 24 MILLSTONE - UNIT 3 TRM 8.1-1 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 Table of Contents Section INTRODUCTION...................................................................................................................... 8.1-4 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS........................................ 8.1-4 2.1 Safety Limits........................................................................................................................ 8.1-4 2.2 Limiting Safety System Settings.......................................................................................... 8.1-5 3.0/4.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

- - - - .......... 8.1-7 SHUTDOWN MARGIN - MODES 1 and 2................................................................. 8.1-7 SHUTDOWN MARGIN - MODES 3, 4 and 5 Loops Filled........................................ 8.1-7 SHUTDOWN MARGIN - COLD SHUTDOWN - Loops Not Filled............................. 8.1-7 Moderator Temperature Coefficient........................................................................... 8.1-8 Shutdown Bank Insertion Limits................................................................................ 8.1-9 Control Bank Insertion Limits..................................................................................... 8.1-9 3/4.2.1 AXIAL FLUX DIFFERENCE................................................................................... 8.1-9 3/4.2.2 Heat Flux Hot Channel Factor - FQ(Z)................................................................. 8.1-10 3/4.2.3 RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor......................... 8.1-12 3/4.2.5 DNB Parameters.................................................................................................. 8.1-12 3/4.3.5 Shutdown Margin Monitor.................................................................................... 8.1-13 3/4.9 Refueling Operations............................................................................................... 8.1-14 ANAYLTICAL METHODS/ REFERENCES............................................................................ 8.1-25 MILLSTONE - UNIT 3 TRM 8.1-2 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 List of Figures Figure Title Figure 1 Reactor Core Safety Limits.................................................................................... 8.1-15 Figure 2 Required SHUTDOWN MARGIN for MODE 3....................................................... 8.1-16 Figure 3 Required SHUTDOWN MARGIN for MODE 4....................................................... 8.1-17 Figure 4 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Filled................... 8.1-18 Figure 5 Required SHUTDOWN MARGIN for COLD SHUTDOWN with RCS Loops Not Filled

.................................................................................................................................. 8.1-19 Figure 6 Control Rod Bank Insertion Limits versus RATED THERMAL POWER................. 8.1-20 Figure 7 AXIAL FLUX DIFFERENCE Limits as a Function of RATED THERMAL POWER. 8.1-21 Figure 8 K(Z) - Normalized FQ(Z) as a Function of Core Height.......................................... 8.1-22 Table Table 1 Table 2 List of Tables Title Penalty Factors for Flux Map Analysis................................................................... 8.1-23 Required Normal Operating Space Reductions for FQ(Z) Exceeding Its Non-Equilibrium Limits..................................................................................................................... 8.1-24 MILLSTONE - UNIT 3 TRM 8.1-3 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 INTRODUCTION Millstone Unit 3 Cycle 24 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Millstone Unit 3 Cycle 24 has been prepared in accordance with the requirements of Technical Specification 6.9.1.6.a.

The Technical Specifications affected by this report are listed below.

2.1.1 Reactor Core Safety Limits 2.2.1 Limiting Safety System Settings 3/4.1.1.1.1 SHUTDOWN MARGIN - MODES 1 and 2 3/4.1.1.1.2 SHUTDOWN MARGIN - MODES 3, 4 and 5 Loops Filled 3/4.1.1.2 SHUTDOWN MARGIN - COLD SHUTDOWN - Loops Not Filled 3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Bank Insertion Limits 3/4.1.3.6 Control Bank Insertion Limits 3/4.2.1.1 AXIAL FLUX DIFFERENCE 3/4.2.2.1 Heat Flux Hot Channel Factor 3/4.2.3.1 RCS Total Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor 3/4.2.5 DNB Parameters 3/4.3.5 Shutdown Margin Monitor 3/4.9.1.1 Refueling Operations Boron Concentration The cycle-specific parameter limits for the specifications listed above are presented in the following subsections. These limits have been developed using the NRG-approved methodologies specified in Technical Specification 6.9.1.6.b.

Cycle-specific values are presented in bold. Text in italics is provided for information only.

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limits Reactor Core 2.1.1 The combination of THERMAL POWER, Reactor Coolant System highest loop average temperature, and pressurizer pressure shall not exceed the limits shown in Figure 1.

MILLSTONE - UNIT 3 TRM 8.1-4 LBDCR 25:-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 2.2 Limiting Safety System Settings Reactor Trip System Instrumentation Setpoints 2.2.1 The Reactor Trip System Instrumentation and Interlock Setpoints shall be set consistent with the Nominal Trip Setpoint values shown in Table 2.2-1.

Table 2.2-1 Note 1: Overtemperature ~ T

[ ~T](l+tis) <K1-K2 (l+t4s) (T-T')+K3(P-P')-f1(~I)

~ T oJ (1 + t2 s) -

(1 + ts s)

Where:

~ T is measured Reactor Coolant System ~ T, °F;

~TO is loop specific indicated ~Tat RATED THERMAL POWER, °F; (1 +171s)

(1 + 172s) is the function generated by the lead-lag compensator on measured ~ T; 171 and 172 are the time constants utilized in the lead-lag compensator for

~ T, 171.:::, 8 sec, 172 ~ 3 sec; K1 ~ 1.1738; K2.:::, 0.01982 / °F; (1+174s)

(1 + 175S) is the function generated by the lead-lag compensator for 174 and 175 are the time constants utilized in the lead-lag compensator for T avg, 174.:::, 20 sec, 175 ~ 4 sec; T is measured Reactor Coolant System average temperature, °F; T' is loop specific indicated T avg at RATED THERMAL POWER,

~ 587.1 °F; K3 ~ 0.001097 / psi; P is measured pressurizer pressure, psia; MILLSTONE - UNIT 3 TRM 8.1-5 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 P' is nominal pressurizer pressure, ~ 2250 psia; s is the Laplace transform operator, sec-1; and f1 (i1I) is a function of the indicated difference between top and bottom detectors of the power range neutron ion chambers; with nominal gains to be selected based on measured instrument response during plant startup tests calibrations such that:

1. For qt - % between -18% and +10%, f 1 (i1I) ~ 0, where qt and % are percent RATED THERMAL POWER in the upper and lower halves of the core, respectively, and qt + % is the total THERMAL POWER in percent RATED THERMAL POWER;

2. For each percent that the magnitude of qt - % exceeds -18%, the i1 T Trip Setpoint shall be automatically reduced by~ 3. 73% of its value at RATED THERMAL POWER;

3. For each percent that the magnitude of qt - % exceeds +10%, the i1 T Trip Setpoint shall be automatically reduced by~ 2.13% of its value at RATED THERMAL POWER.

Table 2.2-1 Note 3: Overpower 11 T Where:

i1 T is measured Reactor Coolant System i1 T, °F; i1 TO is loop specific indicated ti Tat RATED THERMAL POWER, °F; (1+-r1s)

(1 + -r2s) is the function generated by the lead-lag compensator on measured i1 T;

-r1 and -r2 are the time constants utilized in the lead-lag compensator for i1 T, -r1 ~ 8 sec, -r2 :s_ 3 sec; T is measured average Reactor Coolant System temperature, °F; MILLSTONE - UNIT 3 TRM 8.1-6 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 T" is loop specific indicated T avg at RATED THERMAL POWER,

~ 587.1 °F; K6 ~ 0.00149 / °F when T > T" and K6 ~ 0 / °F when T ~ T";

s is the Laplace transform operator, sec-1; 3.0/4.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.1 Reactivity Control Systems 3/4.1.1.1 Boration Control SHUTDOWN MARGIN - MODES 1 and 2 3.1.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% ~k/k.

The COLR limit of Specification 4. 1. 1. 1. 1 is defined in Specification 3. 1. 1. 1. 1.

SHUTDOWN MARGIN - MODES 3, 4 and 5 Loops Filled 3.1.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in

Figure 2 for MODE 3,

Figure 3 for MODE 4, and

Figure 4 for MODE 5 with RCS Loops Filled.

The COLR limit of Specification 4. 1. 1. 1. 2. 1 is defined in Specification 3.1. 1.1.2.

SHUTDOWN MARGIN - COLD SHUTDOWN - Loops Not Filled 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to

a. the limits shown in Figure 5 for MODE 5 with RCS loops not filled or

b. the limits shown in Figure 4 for MODE 5 with RCS loops filled with the chemical and volume control system (CVCS) aligned to preclude reactor coolant system boron concentration reduction.

The COLR limit of Specification 4. 1. 1. 2. 1 is defined in Specification 3. 1. 1. 2.

MILLSTONE - UNIT 3 TRM 8.1-7 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 Moderator Temperature Coefficient 3.1.1.3 The moderator temperature coefficient (MTC) shall be within the limits specified below:

Where:

The maximum upper limit shall be less positive than

+0.5 x 1 o-4 Llk/k/°F for all the rods withdrawn, beginning of cycle life (BOL), condition for power levels up to 70% RATED THERMAL POWER with a linear ramp to O Llk/k/ °Fat 100% RATED THERMAL POWER.

The MTC EOL limit is:

The ARO/EOL/RTP MTC shall be less negative than

- 5.35 x 10-4 ak/k/°F (-53.5 pcm/°F).

The MTC 300 ppm surveillance limit is:

The 300 ppm/ARO/RTP MTC shall be less negative than or equal to - 4.4 x 1 o-4 ak/k/°F (-44 pcm/°F).

BOL stands for Beginning of Cycle of Life

ARO stands for All Rods Out

EOL stands for End of Cycle Life

RTP stands for RATED THERMAL POWER The COLR limits of Specification 4. 1.1.3 are defined by Specification 3.1.1.3 limits given above.

MILLSTONE - UNIT 3 TRM 8.1-8 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 3/4.1.3 3/4.2 3/4.2.1 Moveable Control Assemblies Shutdown Bank Insertion Limits 3.1.3.5 Each shutdown bank shall be at least 225 steps withdrawn The COLR limit of Specification 4. 1. 3. 5 is defined in Specification 3. 1. 3. 5.

Control Bank Insertion Limits 3.1.3.6 The control banks shall be limited in physical insertion

as shown in Figure 6 for control banks B, C, and D, and

control bank A shall be at least 225 steps withdrawn The insertion limits of Specification 4. 1. 3. 6 are defined in Specification 3.1.3.6.

Power Distribution Limits AXIAL FLUX DIFFERENCE 3.2.1.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the limits shown in Figure 7.

The AFD limits of Specifications 4.2.1.1. 1 and 4.2. 1. 1.2 are defined in Specification 3. 2. 1. 1.

MILLSTONE - UNIT 3 TRM 8.1-9 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 3/4.2.2 Heat Flux Hot Channel Factor - Fa(Z) 3.2.2.1 F0(Z), as approximated by F0M(Z), shall be within the limits specified below:

FRTP F0 M(Z) ~

~ x K(Z) ; for P > 0.5 FRTP F0M(z) ~

0~

x K(Z) ; for P:::; 0.5 Where:

THERMAL POWER p = ----------

RATED THERMAL POWER FoRTP = 2.60 K(Z) = the normalized F0 (Z) as a function of core height as shown in Figure 8.

MILLSTONE - UNIT 3 TRM 8.1-10 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERA TING LIMITS REPORT, CYCLE 24 Where:

The Heat Flux Hot Channel Factor non-equilibrium limit is:

FR;;P X K(Z)

F OM (Z) ~

N z

far P: s; 0. 5 0.5 X

(

)

THERMAL POWER P=----------

RATED THERMAL POWER FoRTP = 2.60 K(Z) = the normalized F 0 (Z) as a function of core height as shown in Figure 8 F q(z), Maximum Condition I N(z) =-~--------

F Q(z), Equilibrium Condition I N(z) values are calculated for each flux map using analytically derived F0(Z) values, consistent with the methodology described in VEP-NE-1.

The factors in Table 1 shall be used for surveillance requirement 4.2.2.1.2.

The values provided in Table 2 shall be used to reduce the normal operating space for F0M(Z) exceeding its non-equilibrium limits.

The Heat Flux Hot Channel Factor limits of Specifications 4. 2. 2. 1. 2 are defined in Specification 3. 2. 2. 1 and the Heat Flux Hot Channel Factor non-equlibrium limit given above.

MILLSTONE - UNIT 3 TRM 8.1-11 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERA TING LIMITS REPORT, CYCLE 24 3/4.2.3 3/4.2.5 RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor 3.2.3.1 The indicated Reactor Coolant System (RCS) total flow rate and FN LlH shall be maintained as follows:

a. RCS Total Flow Rate ~ 363,200 gpm (TS Limit) and greater than or equal to 379,200 gpm (COLR Limit), and N

RTP

(

)]

b. F L'lH :SF L'lH [1.0 + PF LlH 1.0 - P Where: p = __ T_H_E_R_M_A_L_P_O_W_E_R __

RATED THERMAL POWER FRTP l\\H = FN LlH limit at RATED THERMAL POWER= 1.586 PF l\\H = the power factor multiplier for FN LlH = 0.3 for P < 1.0 The COLR limits of Specification 4. 2. 3. 1. 3 are defined in Specification 3.2.3.1.a.

DNB Parameters 3.2.5 The following DNB-related parameters shall be maintained within the limits specified below

a. Reactor Coolant System T avg shall be maintained ::;; 593.5°F

b. Pressurizer Pressure shall be maintained ~ 2204 psia 1 The COLR limits of Specification 4. 2. 5 are defined in Specification 3. 2. 5.

1 Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RA TED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.

MILLSTONE - UNIT 3 TRM 8.1-12 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERA TING LIMITS REPORT, CYCLE 24 3/4.3 3/4.3.5 Instrumentation Shutdown Margin Monitor 3.3.5 Two channels of Shutdown Margin Monitors shall be OPERABLE

a. With a minimum count rate and alarm ratio setting as shown below, or

b. If the minimum count rate in Specification 3.3.5.a cannot be met, then the Shutdown Margin Monitors may be made OPERABLE with a lower minimum count rate and alarm ratio setting as shown below by berating the Reactor Coolant System above the requirements of Specification 3.1.1.1.2 or 3.1.1.2. The additional boration shall be:

1. A minimum of 150 ppm above the SHUTDOWN MARGIN requirements specified in Figure 2 for MODE 3, or

2. A minimum of 350 ppm above the SHUTDOWN MARGIN requirements specified in the

Figure 3 for MODE 4

Figure 4 for MODE 5 with RCS loops filled, and

Figure 5 for MODE 5 with RCS loops not filled.

Tech. Spec. LCO SMM Alarm Ratio Setting Min. Count Rate (counts/sec) 3.3.5.a 1.50 1.0 1.25 0.6 3.3.5.b.1 1.50 0.50 1.25 0.35 3.3.5.b.2 1.50 0.35 1.25 0.25 The combination of the SMM Alarm Ratio setting and minimum count rate accounts for the time lag between the indicated and actual count rates, as well as other uncertainties. The specified SMM Alarm Ratio setting ensures that the assumption that an alarm is generated at flux doubling in the Boron Dilution Event analysis remain valid. The count rate is displayed on the SMM.

The COLR limits of Specification 4. 3. 5 are defined in Specification 3. 3. 5.

MILLSTONE - UNIT 3 TRM 8.1-13 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERA TING LIMITS REPORT, CYCLE 24 3/4.9 3/4.9.1 Refueling Operations Boron Concentration 3.9.1.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained sufficient to ensure that the more restrictive of the following reactivity conditions is met; either:

a. A Keff of 0.95 or less, or

b. A boron concentration of greater than or equal to 2600 ppm2 Additionally, the eves valves of Specification 4.1.1.2.2 shall be closed and secured in position.

2This boron concentration bounds the condition of keff S 0.95 (all rods in less the most reactive two rods) and subcriticality (keff S 1.0 with all rods out).

MILLSTONE - UNIT 3 TRM 8.1-14 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 Figure 1-Reactor Core Safety Limits 680.0 UNACCEPTABLE OPERATION ii:'

L

~

VI u

0::

660.0 640.0 620.0 600.0 580.0 560.0 0

0.2 MILLSTONE - UNIT 3 2425PSIA

........_2250PSIA

......._......._ 2000PSIA 1840 PSIA ACCEPTABLE OPERATION OA 0~

OB 1

1.2 FRACTION OF RATED THERMAL POWER TRM 8.1-15 LBDCR 25-MP3-001

TECHN1CAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERA TING LIMITS REPORT, CYCLE 24 Figure 2-Required SHUTDOWN MARGIN for MODE 3 4.0 3.5 I 1550, 3.ooo I 3.0

Q

<J

~

0

~ 2.5

(.')

a:

<(

~ 2.0 z s 0

0 1.5 I-

J V

~ V

/

I (f) 1.0 Io, 1.300 I I 550, 1.300 I 0.5 0.0 0

500 1000 1500 2000 RCS CRITICAL BORON CONCENTRATION (ppm)

MILLSTONE - UNIT 3 TRM 8.1-16 I 2500, 3.ooo I 2500 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERA TING LIMITS REPORT, CYCLE 24 Figure 3-Required SHUTDOWN MARGIN for MODE 4 6.0 5.5 5.0 4.5 4.0

~

<]

~ 3.5 s:::

"§

~ 3.0 s:::

~

~ 2.5

.s:::

V) 2.0 1.5 1.0 0.5 0.0 0,1.3001

/

1150, 1.300 I 0

MILLSTONE - UNIT 3 11250, 5.3001

/

V

/

,v

/

500 1000 1500 RCS Critical Boron Concentration (ppm)

TRM 8.1-17

2500, 5.300 2000 2500 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 Figure 4-Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Filled 6.0 11255, 5.500 1 5.5 5.0 4.5

.-. 4.0 V <]

'J2--; 3.5

"§ m

~ 3.0 C s

.g 2.5

+-'

J

.c (f) 2. 0 1.5 1.0 1150, uoo 1 0.5 0.0 0

500 1000 1500 2000 RCS Critical Boron Concentration (ppm)

MILLSTONE - UNIT 3 TRM 8.1-18 I 2500, 5.500 I 2500 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERA TING LIMITS REPORT, CYCLE 24 Figure 5-Required SHUTDOWN MARGIN for COLD SHUTDOWN with RCS Loops Not Filled 6.5 6.0 11650, 6.150 1 12500, 6.1501 5.5 5.0 4.5 i 4.0 C

"§ 3.5 C1J

~

~ 3.0 0

u

"::J 2.5

..c Cf) 2.0 1.5 1170, uoo 1 1.0 0.5 0.0 0

500 1000 1500 2000 2500 RCS Critical Boron Concentration (ppm)

TRM 8.1-19 MILLSTONE - UNIT 3 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 Figure 6-Control Rod Bank Insertion Limits versus RATED THERMAL POWER 240 25.9%, 2251 76.3%, 2251 220 200 180 z

~ 160 0:::

0 I !:: 140 s

Cf) o_

w 120 I-

~

z 100 0 E Cf) 0 80 o_

Y'.

z

<(

60 co 0

0 0:::

40

/

V

/

VI Control Bank B

/

I

/

/4.0%, 1661

/v I 100.0%, 1e4I

/

-~

/

I

/

I Control Bank C I

/

//

/4v V

/

I Control Bank D

/

V 10.0%, 51 I

/

20

/

/i28.0%, 01

/

I 0

0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 RATED THERMAL POWER(%)

MILLSTONE - UNIT 3 TRM 8.1-20 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 120.0 100.0

...-.. 80.0

~

0 --

~

w s 0

0...

.....I

<(

60.0

~

w

r:

I-0 w

~ 40.0

~

20.0 0.0

-60 Figure 7-AXIAL FLUX DIFFERENCE Limits as a Function of RATED THERMAL POWER l-12, 1001

!9, 100!

UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION

\\

ACCEPTABLE OPERATION l-3o, sol/

\\,27, sol

-40

-20 0

20 40 FLUX DIFFERENCE(% DELTA I) 60 MILLSTONE - UNIT 3 TRM 8.1-21 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 Figure 8-K(Z) - Normalized F0 (Z) as a Function of Core Height 1.2 1.1 1.0 0.9

N

~

~0.8 0

~

0

<( 0.7 LL C) z

~ 0.6

<(

w 0...

DJ 0.5 N

_J

<(

~ 0.4 a:

0 z 0.3 0.2 0.1 0.0 0

K(Z) 1.0 1.0 0.925 2

MILLSTONE - UNIT 3 Elevation 0.0 ft 6.0 ft 12.0 ft 3

4 5

6 7

8 CORE ELEVATION (FEET)

TRM 8.1-22 9

I

--L..L....L..L_

10 11 12 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 Table 1 Penalty Factors for Flux Map Analysis Burnup (MWD/MTU)

Penalty Factor(%)

0-999 2.0 1000-1999 6.0 2000-2999 8.5 3000-3999 4.0 4000 - 4999 2.0 5000 - 6999 2.0 7000 - 8999 2.0 9000 -10999 2.0 11000 - 12999 2.0 13000 - 14999 2.5 15000 - 16999 2.0 17000 - EOC 2.0 MILLSTONE - UNIT 3 TRM 8.1-23 LBDCR 25-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 Table 2 Required Normal Operating Space Reductions for F0 (Z) Exceeding Its Non-Equilibrium Limits Required Required Required Negative Required Positive Non-Equilibrium THERMAL Band AFD Band AFD Reduction Fa T(Z) Margin POWER Limit Reduction (3/4AFD)

(3/4AFD)

Improvement(%)

(3/4RTP)

> 0% and.S 1%

.S 97.0%

2:. 1.0%

> 1% and.S 2%

.S 96.0%

2:. 1.5%

2:. 2.0%

> 2% and.S 3%

.S 94.0%

2:. 1.5%

2:. 3.0%

>3%

.S 50%

N/A N/A

AFD Limits are provided in COLR Figure 7.

MILLSTONE - UNIT 3 TRM 8.1-24 LBDCR 25-MP3-001

TECHN1CAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 ANAYLTICAL METHODS/ REFERENCES The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents.

1.

VEP-FRD-42-A, Revision 2, Minor Revision 2, "Reload Nuclear Design Methodology," October 2017.

Methodology for Specifications:

2.1.1 Reactor Core Safety Limits

3.1.1.1.1 SHUTDOWN MARGIN - MODES 1 AND 2

3.1.1.1.2 SHUTDOWN MARGIN - MODES 3, 4, and 5 Loops Filled

3.1.1.2 SHUTDOWN MARGIN - COLD SHUTDOWN - Loops Not Filled

3.1.1.3 Moderator Temperature Coefficient

3.1.3.5 Shutdown Bank Insertion Limits

3.1.3.6 Control Bank Insertion Limits

3.2.2.1 Heat Flux Hot Channel Factor

3.2.3.1 Nuclear Enthalpy Rise Hot Channel Factor

3.3.5 Shutdown Margin Monitor

3.9.1.1 Refueling Operations Boron Concentration

2.

VEP-NE-1-A, Revision 0, Minor Revision 3, "Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications," October 2017.

Methodology for Specifications:

3.2.1.1 AXIAL FLUX DIFFERENCE

3.2.2.1 Heat Flux Hot Channel Factor

3.

WCAP-16996-P-A, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology),"

November 2016 (Westinghouse Proprietary).