Text

Core Operating Limits Report, Cycle 21
	ML21014A339
Person / Time
Site:	Millstone
Issue date:	12/21/2020
From:	Armstrong L; Dominion Energy Nuclear Connecticut
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	20-424
	Download: ML21014A339 (30)
	v • d • e

Domm1on Energy NucJear ConQect1cut, Inc Millstone Power Station

~

i4 & Domin ion 314 Rope Farry Road, Waterford, CT 06385 Domm1onEnergy com J j ir Energye DEC 2 1 2020 U. S. Nuclear Regulatory Commission Serial No.20-424

- Attention: Document Control Desk NSSUMLC RO*

Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 CORE OPERATING LIMITS REPORT, CYCLE 21 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 Enclosure 1, the Cycle 21 Core Operating Limits Report (COLR).

The changes to th~ MPS3 COLR for Cycle 21 are summarized below:

(1) Administrative changes to increment the cycle number from 20 to 21.

(2) Changes to COLR limits using the NRG-approved methodologies. The changed parameters include:

Mode 4 and 5 Variable Shutdown Margin (VSDM) c*urves ,

300 ppm Moderator Temperature Coefficient (MTG) surveillance requirement

Penalty Factors for Flux Map Analysis

Normal Operating Space Reductions for Non-Equilibrium FQ Exceeding its Limits The COLR has been incorporated into the MPS3 Technical Requirements Manual.

If you have any questions or require additional information, please contact Jeffry A.

Langan at (860) 444-5544.

Sincerely, L. J. Armstrong Director, Nuclear Station Safety and Licensing - Millstone

Enclosures:

(1)

Commitments made in this letter: None.

Serial No.20-424 Docket No. 50-423 Core Operating Limits Report, Cycle 21 Page 2 of 2 cc: Regional Administrator, U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman 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 NRG Senior Resident Inspector Millstone Power Station

Serial No.20-424 Docket No. 50-423 ENCLOSURE 1 CORE OPERATING LIMITS REPORT, CYCLE 21 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT CYCLE 21 MILLSTONE - UNIT 3 TRM 8.1-1 LBDCR 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LJMITS REPORT, CYCLE 21 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 FIiied ............................. 8.1-7 Moderator Temperature Coefficient ........................................................................... 8.1-8 Shutdown Rod Insertion Limits .................................................................................. 8.1-9 Control Rod lnsertioh Limits ..................................................................................... 8.1-9 3/4.2.1 AXIAL FLUX DIFFERENCE ................................................................................... 8.1-9 3/4.2.2 Heat Flux Hot Channel Factor - F0 (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 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 List of Figures Figure Title Figure 1 Reactor Core Safety Limits .................................................................................... 8.1-15 Figure 2 Required SHUIDOWN MARGIN for MODE 3 ....................................................... 8.1-16 Figure 3 Required SHUTDOWN MARGIN for MODE 4 ....................................................... 8.1-17 Figure 4 Required SHUIDOWN MARGIN for MODE 5 with RCS Loops FIiied ................... 8.1-18 Figure 5 Required SHUTDOWN MARGIN for COLD SHUIDOWN 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 Fa(Z) as a Function of Core Height.. ........................................ 8.1-22 List of Tables Table Trtle Table 1 Penalty Factors for Flux Map Analysis ................................................................... 8.1-23 Table 2 Required Normal Operatlng Space Reductions for Fa(Z) Exceeding Its Non-Equilibrium Limits ..................................................................................................................... 8.1-24 MILLSTONE - UNIT 3 TRM 8.1-3 LBDCR 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 Millstone Unit 3 Cycle 21 CORE OPERATING LIMITS REPORT INTRODUCTION This CORE OPERATING LIMITS REPORT (COLR) for Millstone Unit 3 Cycle 21 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 Rod Insertion Limits 3/4.1.3.6 Control Rod 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 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LilvJITS REPORT, CYCLE 21 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 11T l1Tl(1+1:is) <K -K2 (1+'4s) (T-T')+K3(P-P')-f1(Lil)

[ /1ToJ (1 + 1:2 s) - 1 (1 + 1:5 s)

Where:

11Tis measured Reactor Coolant System /1T, °F;

/1T0 is loop specific indicated L~.T at RATED THERMAL POWER, °F; (1 +'t s) 1 (1 + 't2 s) is the function generated by the lead-lag compensator on measured 11T;

't1 and 't2 are the time constants utilized in the lead-lag compensator for

/1T, 't1 ?. 8 sec, -c2 ,::S. 3 sec; K2 ?. 0.025 / °F; (1 +'t4S)

(1 + 't5S) is the function generated by the lead-lag compensator for

-c4 and -c5 are the time constants utilized in the lead-lag compensator for Tavg, 't4?. 20 sec, -c5 .::S. 4 sec; Tis measured Reactor Coolant System average temperature, °F; T' is loop specific Indicated T avg at RATED THERMAL POWER,

,::S.587.1 °F; K3 ~ 0.00113 / psi; P is measured pressurizer pressure, psia; MILLSTONE - UNIT 3 TRM 8.1-5 LBDCR 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 P' is nominal pressurizer pressure, ~ 2250 psia; s is the Laplace transform operator, sec- 1 ;

and f 1 (Al) 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(AI) :2: 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 AT Trip Setpoint shall be automatically reduced by~ 3.75% of its value at RATED THERMAL POWER;

3. For each percent that the magnitude of qt - % exceeds +10%, the AT Trip Setpoint shall be automatically reduced by~ 2.14% of its value at RATED THERMAL POWER.

Table 2.2-1 Note 3: Overpower .LiT Where:

AT is measured Reactor Coolant System /1 T, °F; AT 0 is loop specific indicated Lff at RATED THERMAL POWER, °F; (1 +--c1s)

(1 + 't2s) is the function generated by the lead-lag compensator on measured AT;

--c1 and --c2 are the time constants utilized in the lead-lag compensator for AT, --c 1 ?. 8 sec, --c2 ,:S 3 sec; T is measured average Reactor Coolant System temperature, °F; MILLSTONE - UNIT 3 TRM 8.1-6 LBDCR 20-MP3-009

TECHNICAL REQUIR.Rr\IBNTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 T' is loop specific indicated T avg at RATED THERMAL POWER,

.'.::. 587.1 °F; Ke~ 0.0015 / °F when T > r* and Ke.'.::. 0 I °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% 6k/k.

The COLR limit of Specificailon 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 Specificailon 4.1.1.2.1 is defined In Specification 3.1.1.2.

MILLSTONE - UNIT 3 TRM 8.1-7 LBDCR 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 Moderator Temperature Coefficient 3.1.1.3 The moderator temperature coefficient (MTC) shall be within the limits specified below:

The maximum upper limit shall be less positive than

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

The MTC EOL limit is:

The ARO/EOURTP 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 MTG shall be less negative than or equal to - 4.4 x 10 4 Ak/k/°F (-44 pcm/°F).

Where:

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 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 3/4.1.3 Moveable Control Assemblies Shutdown Rod Insertion Limits 3.1.3.5 All shutdown rods shall be at least 220 steps withdrawn The COLR limit of Specificauon 4.1.3.5 is defined in Specification 3.1.3.5.

Control Rod 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 220 steps withdrawn The insertion limits of Specification 4.1.3.6 are defined in Specification 3.1.3.6. 1 3/4.2 Power Distribution Limits 3/4.2.1 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 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 3/4.2.2 Heat Flux Hot Channel Factor - F0 (Z) 3.2.2.1 F 0 (Z), as approximated by F 0 M(Z), shall be within the limits specified below:

FRTP FoM(z) ~ ~ x K(Z) ; for P > 0.5 Where: p = __T_'H_E_RMAL

___P_O_W_E_R__

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

MILLSTONE - UNIT 3 TRMB.1-10 LBDCR 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 The Heat Flux Hot Channel Factor non-equilibrium llmlt is:

?_TP x K(Z)

, for P ~ o.5 0

F0 M(z) < N Z)

-

0.5 X (

Where:

p = THERMAL POWER RATED THERMAL POWER FoRTP = 2.60 K(Z) = the normalized F0 (Z) as a function of core height as shown in Figure 8 N(z) = Fq(z), Maximm Condition I F Q(z), Equilibrium Condition I N(z) values are calculated for each flux map using analytically derived FQ(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 F0 M(Z) exceeding its non-equilibrium llmlts.

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 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 3/4.2.3 RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor 3.2.3.1 The indicated Reactor Coolant System (RCS) total flow rate and FNfl.H 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

b. F~ :::;F!: [1.0 + PFMI (1.0-P)]

Where: p = THERMAL POWER RATED THERMAL POWER FRTP6 H:::: FNnH limit at RATED THERMAL POWER:::: 1.586 PF 6 H = the power factor multiplier for FNMi :::: 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.

3/4.2.5 DNB Parameters 3.2.5 The following NB-related parameters shall be maintained within the limits specified below

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

b. Pressurizer Pressure shall be maintained 2': 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 TIIBRMAL POWER ramp in excess of 5% of RA1ED THERMAL POWER per minute or a TIIBRMAL POWER step in excess of 10% of RATED TIIBRMAL POWER.

MILLSTONE - UNIT 3 TRM 8.1-12 LBDCR 20-MP3-009

TECHNICAL REQUIREMENfS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 3/4.3 Instrumentation 3/4.3.5 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 wrth 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) 3.3.5.1:1 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 fag between the indicated and actual count rates, as wefl as other uncertainties. The specified SMM Alarm Ratio setting ensures that the assumpilon 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 20-MP3-009

TECHNICAL REQUJREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 3/4.9 Refueling Operations 3/4.9.1 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 ta ensure that the mare restrictive of the fallowing reactivity conditions is met; either:

a. A Katr of 0.95 or less, or

b. A boron concentration of greater than or equal to 2600 ppm 2 Additionally, the eves valves of Specification 4.1.1.2.2 shall be closed and secured in position.

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

MILLSTONE - UNIT 3 TRM 8.1-14 LBDCR 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX8.l CORE OPERATING LIMITS REPORT, CYCLE 21 Figure 1-Reactor Core Safety Limits 680.0 - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,

UNACCEPTABLE OPERATION 660.0 2425 PSIA 2250 PSIA 640.0 .....

G::'

..... .... 2000 PSIA 0

(.')

l-~620.0 ..... .....

..... ..... \\

~ ..... ..... \

D:'.'. \

..... .... \

..... ..... \

600.0 "\

ACCEPTABLE OPERATION '

580.0 5 60. 0 +--'------'-_J..--+-----l....-.L..--l---'------'------'----l----'--L...-~-+- -'-----'------'----l----'--L...-~

0 0.2 0.4 0.6 0.8 1 1.2 FRACTION OF RATED THERMAL POWER MILLSTONE - UNIT 3 TRM 8.1-15 LBDCR 20-MP3-009

IBCHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 Figure 2-Required SHUTDOWN MARGIN for MODE 3 4.0 3.5 11 s5o, 3.ooo I j 2500, 3.ooo I 3.0

-- 1,1"'

~

<J

~ 2.5 /

C) er:

<t:

~ 2.0

.V z

s0

~ 1.5

) /

/

I Cf) lo, 1.3ool I550, 1.300 I 1.0 0.5 0.0 0 500 1000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm)

TRM 8.1-16 MILLSTONE - UNIT 3 LBDCR 20-MP3-009

TECBNICAL REQUIREMENTS MANUAL APPENDJX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 Figure 3-Required SHUTDOWN MARGIN for MODE 4 6.0 55 I 1250, 5.300 I I 2500, 5.300 5.0 /

45

//

/

4.0

/

2.0

/

1.5 a, 1.300 I

/

iiso,1.300!

LO 05 0.0 0 500 1000 1500 2000 2500 RCS Critical Boron Concentratlon (ppm)

TRM 8.1-17 MILLSTONE - UNIT 3 LBDCR 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 Figure 4-Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Filled 6.0 5.5 I1250, 5.440 I I 2500, 5.440 \

5.0 /

4.5

/

4.0

/

,,V 2.0

/

0,1.3001 /

1.5

/

1150, 1.300 I 1.0 0.5 0.0 0 500 1000 1500 2000 2500 RCS Critical Boron Concentration (ppm}

TRM 8.1-18 MILLSTONE - UNIT 3 LBDCR 20-MP3-009

1ECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 Figure 5-Required SHUTDOWN MARGIN for COLD SHUTDOWN with RCS Loops Not Filled 7.0 65 i 1800, 6.150 I I2500, 6.150 I 6.0 I1125, 5 . ~;_------- - -

5.5 5.0

/

4.5

/

~

~4.0 /

~

i C

35

/

C

~

'B 3.0 V

/

i5i /

2.5 2.0

/

LS o, 1.300 I

/

1.0 i170, 1.300 I 0.5 0.0 0 500 1000 1500 2000 2500 RCS Critical Boron Concentration (ppm)

TRM 8.1-19 MILLSTONE - UNIT 3 LBDCR 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 Figure 6-Control Rod Bank Insertion Limits versus RATED THERMAL POWER 240 I*~~if~3/4H~~1f~]

~~-...-.,,.....-... ._.._A-".,._;,.;,...

1:1-?:iH~~~gi 220

/ V 200 / /

/1 Control Bank B /

180

/ /

z V V iJi:of~<W/4'1".6~11 i

-..... ,:...-.,-_.._,J_~.-.L...,.-..:

160 H1.~-;1o-ci;;

~**""'c<J I ,I

9;Q,Yos:1§§..-1

~I /

0 I

I-5 140 Control Bank C l Cf) 0..

Ll.J I-Cf) 120

/ /

z 0

I- 100

/ V

/

~

Cf) 0 0..

z<{ 80 V

/' /

// I Control Bank D OJ 0

0 60

/ /

O'.'.

~-~,~,,_.,,*~-,;.11

,(}0,-~~,;p_l,,_

d -- , -*,.

V 40

~.,-.1,

/

V 20

,I

/[?M~~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 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 Figure 7-AXIAL FLUX DIFFERENCE Limits as a Function of RATED THERMAL POWER 120.0 l-12, 100 I lg, 1001 100.0 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION

~ 80.0

\

0 o:'.

I w

~

0 0..

~ 60.0 ACCEPTABLE OPERATION

\

o:'.

w I

I- l-30, SDI/ \127,50 0

w

~ 40.0 20.0 0.0

-60 -40 -20 0 20 40 60 FLUX DIFFERENCE(% DELTA I)

MILLSTONE - UNIT 3 TRM 8.1-21 LBDCR 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 Figure 8-K(Z) - Nonnalized F0 (Z) as a Function of Core Height 1.2 1.1 1.0 EI 0.9 -

~

~0.8 0

t5<( 0.7 LL (9

z

~ 0.6

~

a..

63 0.5 i

0 z

0.4 0.3 Km Elevatlon 1.0 0.0 ft 0.2 1---

1.0 6.0 ft 0.925 12.0ft 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 CORE ELEVATION (FEET)

MILLSTONE - UNIT 3 TRM 8.1-22 LBDCR 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 Table 1 Penalty Factors for Flux Map Analysis Burnup (MWD/MTU) Penalty (%)

0-999 5.0 1000-1999 3.5 2000-2999 2.0 3000-3999 2.0 4000-4999 2.0 5000-6999 2.0 7000-8999 2.0 9000-10999 2.0 11000-12999 2.0 13000-14999 2.0 15000-16999 2.0 17000-19999 2.0 20000-EOC 2.0 MILLSTONE - UNIT 3 TRM 8.1-23 LBDCR 20-MP3-009

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 Table 2 Required Normal Operating Space Reductions for FQ(Z) Exceeding Its Non-Equillbrium Limits Required Required Required Negative Required Positive Non-Equilibrium THERMAL BandAFD Band AFD Reduction FQ(Z) Margin POWER Limit Reduction (3/4AFD) (3/4AFD)

Improvement(%) (3/4RTP)

> 0% and$1% $99.0% ~ 1.5% ~ 1.5%

> 1% and$2% $97.0% ~2.5% ~2.5%

> 2% and$ 3% $ 96.0% ~2.5% ~3.5%

>3% $50% NIA NIA

AFD Limits are provided in COLR Figure 7.

MILLSTONE - UNIT 3 TRM 8.1-24 LBDCR 20-MP3-009

IBCHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 21 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 Rod Insertion Limits

3.1.3.6 Control Rod 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-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005 (Westinghouse Proprietary).