ML16165A489

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Core Operating Limits Report, Cycle 18
ML16165A489
Person / Time
Site: Millstone Dominion icon.png
Issue date: 06/07/2016
From: Stanley B
Dominion, Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML16165A489 (30)


Text

Dominion Nuclear Connecticut, Inc.

Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dom.com *- JUN*o 7 2016 U.S. Nuclear Regulatory Commission Serial No.16-220 Attention: Document Control Desk NSS&L/MLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT. INC.

MILLSTONE POWER STATION UNIT 3 CORE OPERATING LIMITS REPORT, CYCLE 18 In accordance with the Millstone Power Station Unit 3 (MPS3) Technical Specifications (TSs), Section 6.9.1.6.d, Dominion Nuclear Connecticut, Inc., hereby submits, as Enclosure 1, the Cycle 18 Core Operating Limits Report (COLR).

The MPS3 COLR has been revised to incorporate the following:

1) Editorial changes to increment the cycle number from 17 to 18.
2) Editorial changes to Item 2.13 "DNB Parameters" to match the wording of TS 3.2.5. -- -- --... -~
3) Cycle 18-specific changes to the W(Z) values.
4) Cycle 18-specific changes to the burn up penalties for in core (Fa(Z)) surveillance.

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

If you have any questions or require additional information, please contact Mr. Thomas G.

Cleary at (860) 444-4377.

Sincerely,

~:st;-

B. L. Stanley Director, Nuclear Station Safety and Licensing - Millstone

Enclosures:

(1)

Commitments made in this letter: None.

Serial No.16-220 Docket No. 50-423 Core Operating Limits Report, Cycle 18 Page 2 of 2 cc: 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 NRC Senior Resident Inspector Millstone Power Station

Serial No.16-220 Docket No. 50-423 ENCLOSURE 1 CORE OPERATING LIMITS REPORT, CYCLE 18 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT MILLSTONE UNIT 3 CYCLE18 CORE OPERATING LIMITS REPORT MILLSTONE - UNIT 3 TRM 8.1-1 LBDCR 16-MP3-001

TECHNICAL REQUIRE:rv.IENTS MANUAL APPENDJX 8.1 CORE OPERATING LIMITS REPORT Table of Contents Section Title 1.0 CORE OPERATING LIMITS REPORT .......................................................................8.1-4 2.0 Operating Limits ..........................................................................................................8.1-4 2.1 Safety Limits (Specification 2.1.1) .......................................................................... 8.1-4 2.2 Limiting Safety System Settin*gs (Specification 2.2.1) ............................................ 8.1-5 2.3 SHUTDOWN MARGIN - MODE 1 and 2 (Specification 3/4.1.1.1.1) ...................... 8.1-6 2.4 SHUTDOWN MARGIN- MODE 3, 4 and 5 Loops Filled (Specification 3/4.1.1.1.2)8.1-6 2.5 SHUTDOWN MARGIN - MODE 5 Loops Not Filled (Specification 3/4.1.1.2) ........ 8.1-6 2.6 Moderator Temperature Coefficient (Specification 3/4.1.1.3) ................................. 8.1-6 2.7 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) ......................................... 8.1-7 2.8. Control Rod Insertion Limits (Specification 3/4.1.3.6) ............................................ 8.1-7 2.9 AXIAL FLUX DIFFERENCE (Specification 3/4.2.1.1) ............ :.. :***** ....................... 8.1-7 2.1 o Heat Flux Hot Channel Factor- F (Z) (Specification 3/4.2.2.1) ............................ 8.1-7 0

2.11 Heat Flux Hot Channel Factor Sunreillance - FQ(Z) (Specification 3/4.2.2.1.2) ..... 8.1-8 2.12 RCS Total Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor.- FNj,H (Specification 3/4.2.3.1) ......................................................................................... 8.1-8 2.13 DNB Parameters (Specification 3/4.2.5) ................................................................ 8.1-9 2.14 Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3.5) .......................... 8.1-9 2.15 Refueling Boron Concent~ation (Specification 3/4.9.1.1) ..................................... 8.1-1 O 3.0 Analytical Methods ....................................................................................................8.1-2_6 MILLSTONE - UNIT 3 TRM 8.1-2 LBDCR 16-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX-8.1 CORE OPERATING LIMITS REPORT List of Figures Figure 1 Reactor Core Safety Limit.. ................................................................................. 8.1-11 Figure 2 Required SHUTDOWN MARGIN for MODE 3 ............................ '. ....................... 8.1-12 Figure 3 Required SHUTDOWN MARGIN for MODE 4 ....................................................8.1-13 Figure 4 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Filled ............... 8.1-14 Figure 5 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Not Filled ......... 8.1-15 Figure 6 Control Rod Bank Insertion Limits versus THERMAL POWER .......................... 8.1-16 Figure 7 AXIAL FLUX DIFFERENCE Limits as a Function of RATED THERMAL POWER8.1-17 Figure 8 K(Z) - Normalized Fo(Z) as a Function of Core Height.. ..................................... 8.1-18 list of Tables Table Table 1 RAOC W(Z) Function, Millstone Unit 3- Cycle 18-12/+9 AFD at 100% RTP.8.1-19 Table 2

  • Base Load W(Z} Function Millstone Unit 3 - Cycle 18 ........................ :............. 8.1-21 Table 3 Part Power (74% RTP, 150 MWD/MTU) RAOC W(Z) Function Millstone Unit 3 -

Cycle 18 ..............................................*...........................................................8.1-23 Table 4 Burn up Penalty for In core Millstone Unit 3 - Cycle 18 .................................... 8.1-25 MILLSTONE - UNIT 3 TRM 8.1-3 LBDCR 16-MP3-001

TECHNICAL REQUJREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LTh1ITS REPORT Millstone Unit 3 Cycle 18 I .

CORE OPERATING LIMITS REPORT 1.0 CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT (COLR) for Millsto~e Unit 3 Cycle 18 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

  • Safety Limits 2.2.1 Limiting Safety System Settings 3/4.1.1.1.1 SHUTDOWN MARGIN - MODE 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 - MODE 5 Loops Not Filled 3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Rod Insertion Limit 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 Alarm Setpoint 3/4.9.1.1 REFUELING Boron Concentration 2.0 Operating Limits The cycle-specific parameter limits for the specifications listed in Section 1.0 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.

2.1 Safety Limits (Specification 2.1.1) 2.1.1 Reactor Core 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 16-MP3-001

IBCHNICAL REQUIRElVIENTS MANUAL APPENDIX 8.1 CORE OPERATING Lilv.JITS REPORT 2.2 limiting Safety System Settings (Specification 2.2.1) 2.2.1 Overtemperature LiT 2.2.1.1 K1 ::;; 1.20 2.2.1.2 K2 ~ 0.025 I °F 2.2.1.3 K3 ~ 0.00113 I psi 2.2.1.4 i-1 ~ 8 seconds 2.2.1.5 i-2 ::;; 3 seconds 2.2.1.6 i-4 ~ 20 seconds 2.2.1.7 i-5 ::;; 4 seconds 2.2.1.8 T' is loop specific indicated Tavg at RATED THERMAL POWER, ::;; 587.1°F 2.2.1.9 P' i~ nominal pressurizer pressure, ~ 2250 psia 2.2.1.10 f 1(Lil) 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(Lil) ~ 0, where qt and% are percent RATED THERMAL POWER in the upper and lower halves of the core, respectively, and qt+ qb is the total THERMAL POWER in percent RATED THERMAL POWER; (2) For each pe*rcent that the magnitude of qt..:.%

exceeds -18%, the LiT 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 LiT Trip Setpoint shall be automatically reduced by~ 2.14% of its value at RATED THERMAL POWER.

2.2.2 Overpower LiT 2.2.2.1 K4 ::;; 1.10 2.2.2.2 Deleted MILLSTONE - UNIT 3 TRM 8.1-5 LBDCR 16-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LilvlITS REPORT 2.2.2.3 K6 ;;::: 0.0015 / °F when T > T" and~:::; 0 I °F when T:::; T" 2.2.2.4 't 1 ;;::: 8 seconds 2.2.2.5 't2 :::; 3 seconds 2.2.2.6 Deleted 2.2.2.7 T" is loop specific indicated Tavg at RATED THERMAL POWER,:::; 587.1°F 2.3 SHUTDOWN MARGIN - MODE 1 and 2 (Specification 3/4.1.1.1.1) 2.3.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3%

Lik/k.

2.4 SHUTDOWN MARGIN - MODE 3, 4 and 5 loops Fi!ied (Specification 3/4.1.1.1.2) 2.4.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 2, 3 and 4. 1 2.5 SHUTDOWN MARGIN - MODE 5 loops Not Filled (Specification 3/

4.1.1.2) 2.5.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figure 5 or the limits shown in Figure 4 with the chemical and volume control system (CVCS) aligned to preclude reactor coolant system boron concentration reduction. 1 2.6 Moderator Temperature Coefficient (Specification 3/4.1.1"3) 2.6.1 The BOL/AR0/0% .: 70% RTP MTG shall be less positive than + 0.5 x 1o-4 Lik/k/°F. Above 70% RTP, the MTG limit is a linear ramp to O Lik/k/°F at 100% RTP.

2.6.2 The EOL/ARO/RTP MTG shall be less negative than - 5.65 x 10-4 Lik/k/°F.

2.6.3 The 300 ppm/ARO/RTP MTG should be less negative than or equal to - 4.9 x 1o-4 Lik/k/°F, where: BOL stands for Beginning Of Cycle Life ARO stands for All Rods Out 1The SHUTDOWN MARGIN requirements in Figures 2, 3, 4 and 5 are based on cycle-specific boron dilu-tion analyses performed by Dominion.

MILLSTONE - UNIT 3 TRM 8.1-6 LBDCR 16-MP3-001

TECHNICAL REQUIREJv.IENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT HZP stands for Hot Zero Power

. EOL stands for End Of Cycle Life RTP stands for RATED THERMAL POWER.

2.7 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) 2.7.1 The shutdown rods shall be at least 220 steps withdrawn (inclusive).

2.8 Control Rod Insertion limits (Specification 3/4.1.3.6) 2.8.1 The control rod banks shall be limited in physical insertion as shown in Figure 6, and 2.8.2 Control bank A shall be at least 220 steps withdrawn.

2.9 AXIAL FLUX DIFFERENCE (Specification 3/4.2.1.1) 2.9.1 The AXIAL FLUX DIFFERENCE (AFD) limits are provided in Figure 7.

2.9.2 The AFD target band during base load operation is +/- 5%.

2.9.3 The minimum allowable (nuclear design) power level for base load operation (APLND) is 80% of RATED THERMAL POWER.

2.10 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3/4.2.2.1)

JITP ,

F Q(Z) ::; . ; x K(Z) for P > 0.5 JITP.

Q F Q(Z)::; ""'Q.5 x K(Z) for P ::; 0.5 where: THERMAL POWER p =RATED THERMAL POWER 2.10.1 FRTP Q =2.60.

2.10.2 K(Z) is provided in Figure 8.

MILLSTONE - UNIT 3 TRM 8.1-7 LBDCR 16-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.i CORE OPERATING LIMITS REPORT 2.11 Heat Flux Hot Channel Factor Survemance - FQ(Z) (Specification 3/

4.2.2.1.2)

Ji-;P xK(Z)

FQ(Z) ~ Px W(Z) for P > 0.5 Ji-;P xK(Z)

F Q(Z) ~ 0.5 x W(Z) for P ~ 0.5 where: p = THERMAL POWER RATED THERMAL POWER 2.11.1 FRTP Q =2.60.

2.11.2 K(Z) is provided in Figure 8.

2.11.3 W(Z) values for RAOC operation are provided in Table 1. Note that the W(Z) values at Axial Mesh 1 are at the top of the core. The Cycle 18 burnup dependent RAOC W(Z) values are valid over the range of burnup from 0 to 21,600 MWD/MTU.

2.11.4

  • W(Z) values for Base Load (BL) operation are provided in Table 2.

Note that the W(Z) values at Axial Mesh 1 are at the top of the core.

The Cycle 18 burnup dependent BL W(Z) values are valid over the range of burnup from 0 to 21,600 MWD/MTU.

2.11.5 W(Z) values for Part Power operation are provided in Table 3. Note.

that the W(Z) values at Axial Mesh 1 are at the top of the core. The Cycle 18 burnup dependent Part Power W(Z) values are valid over 1*

the range of burnup from 0 to 150 MWD/MTU.

2.11.6 The factors in Table 4 shall be used for surveillance requirements 4.2.2.1.2 and 4.2.2.1A. A 2% factor shall be *used outside of the burnup range shown in Table 4.

2.12 RCS Total Flow Rate an.d Nuclear Enthalpy Rise Hot Channel Factor -

FNAH (Specification 3/4.2.3.1) 2.12.1 The RCS Total Flow Rate shall be greater than or equal to 379,200 gpm.

2.12.2 FNAH ~, FRTPAH X (1 + PFLiH X [1 - P])

MILLSTONE - UNIT 3 TRM 8.1-8 LBDCR 16-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT where: p = THERMAL POWER RATED THERMAL POWER 2.12.2.1 FRTPL\H =1.586 for Robust Fuel Assemblies (RFA) and*

(RFA-2) 2.12.2.2 PFL\H =0.3 for P < 1.0.

2.13 DNB Parameters (Specification 3/4.2.5)

The following' DNB-related parameters shall be maintained within the limits specified below:

2.13.2 Pressurizer Pressure shall be maintained ;::: 2204 psia 2 .

2.14 Shutdown Margin Monitor Alar!ll Setpoint (Specification 3/4.3.5) 3 2.14.1 The Shutdown Margin Monitor (SMM) minimum count rate and Alarm Ratio Setting to meet Limiting Condition for Operation (LCO) 3.3.5 shall be as shown below..

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 I 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 remains valid. The count rate is displayed on the SMM.

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

3 Section 2.14 is based on cycle-specific boron dilution analyses performed by Dominion.

MILLSTONE - UNIT 3 TRM 8.1-9 LBDCR 16-MP3-001

TECHNICAL REQUIREMENTS MANUAL

  • APPENDIX 8.1 CORE OPERATING Lil\t.1ITS REPORT 2.15 Refueling Boron Concentration (Specificatiori 3/4.9.1.1) 2.15.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling cavity -shall be maintained at a boron concentra_tion of greater than or equal to 2600 ppm. 4 4 This boron concentration bounds the condition of keff::; 0.95 (all rods in less the most reactive two rods) and subcriticality (keff::; 1.0 with all rods out).

MILLSTONE - UNIT 3 TRM 8.1-10 LBDCR 16-MP3-001

TECHNICAL REQUJREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 1 Reactor Core Safety Limit UNACCEPTABLE OPERATION 660 640 u..

(.9 2000 PSIA .... . .... ..

w ...........

0 c:i 620

~

1840 PSIA '...._ ....._ '

\.

1- .......... ' -\

Cf)

(.) ...........

oc ......... '"

600 "\..

\

\

\

ACCEPTABLE OPERATION 0 0.2 0.4 0.6 0.8 1 1.2 FRACTION OF RATED THERMAL POWER MILLSTONE - UNIT 3 TRM 8.1-11 LBDCR 16-MP3-001

Figure 2 Required SHUTDOWN MARGIN for MODE 3 4.0 3.5 12050, 3.ooo I 12500, 3.000

  • 1 3.0

~

P""

~

z

-<]

-=

CJ 2.5

/'

/

~

E 2.0

~

z

~

g1- 1.5 -~

/

c en 10"1.300 I 1100, 1.300 I 1.0 0.5 0.0 0 500 1000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm)

- TRM 8.1-12 MILLSTONE - UNIT 3 LBDCR 16-MP3-001

Figure 3 Required SHUTDOWN MARGIN for MODE 4 6.0 5.5 5.0 11324. 4.500 I 12500. 4.500 I

- ~

<I 4.5

/

--z

?fl. 4.0

~ 3.5 7

~ /~

<C

!: 3.0
z 3:. 2.5

/

0 c

I- 2.0

l I /

/

c 10. 1.300 Cl) 1.5 /

/

1355, 1,300 I 1.0 0.5 0.0 0 500 1000 1500 2000 . 2500 RCS CRITICAL BORON CONCENTRATION (ppm)

TRM 8.1-13

  • MILLSTONE- UNIT 3 LBDCR 16-MP3-001

~----- -- - - -- --- -- - ----- *- -- -----* --*-- *---* -- --*- - -- ------ - -~-

Figure 4 Required SHUTDOWN MARGIN for MODE 5 with RCS loops !Fined ilQi ~======;i=======J======9:=======i;=======-

I -f 5.,5 ~=----......._.,..._**"""--**"'"'-~-"""*....."""**"""**......"""----""'--'="'-**-"""'-*.,...,.,.,,_....9"""

____ ,,,,. __ ---"""**--~--,,,~=-~--==4'<===~-~-

_=;=_=;==.-!

I to+--.....~-~---~---.......,*-~-~-~--~-~------ .......~-~------~---*--~---....,,..-~-~--~---~---.......--~.......-+~===--='--~-----,,__~---.........~--~

0 *1;cyoij 1SQO*

RCSCR~~pt, 60R:ONJ CONCENJTRAllONl ~ppm~

TRM 8.1-14 MILLSTONE - UNIT 3 LBDCR 16-MP3-001

Figure 5 Required SHUTDOWN MARGIN for MODE 5 with RCS Loops Not !Filled 7.0 (2200, 6.150) 6.5 6.0 (1252, ~.523) (2500, 6.150) 5.5

~ 5.0

/

?fl.

- 4.5

/ -

z=-

Cl 4.0 /. "

~

<(

e 3.5 / -

z 3: 3.0 /

0 c

I=-

2.5 /

I: 2.0 /

"' ,,/

(0, 1.300) 1.5 1.0 (355, 1.300) 0.5 0.0 0 500 1000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm)

TRM 8.1-15 MILLSTONE - UNIT 3 LBDCR 16-MP3-001

---~-------- ------ ---*---* ---*- ----------------------------- ------ -

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 6 Control Rodi Bank Insertion limits versus THERMAL POWER 240 I 23.7%. 2201 174.1%.220 I 220

/ V*

/ IControl Bank BI /

200

/

v /

v i~

180 Vr0.0%, 1661 v 1100.0%. 164 I v

/ #

160 c*

rE Vccontro1 sank c I

$: 140 I/

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(I) 0 c.

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i::::

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80 v

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~

v,Control Bank DI 60 v*

/ /

I 0.0%, 51 I

/

/

40 20

/

v v[28~0%. 01

,I 0 '

0 10 20 30 40 50 60 70 80 90 100 RATED THERMAL POWER(%)

MILLSTONE - UNIT 3 TRM 8.1:*16 LBDCR 16-MP3-001

1ECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Fngure 7 AXIAL FLUX DIFFERENCE limuts as a Function of RATED THERMAL POWER 120 I -12, 1 oo I I 9,100 I 100

~

~

~ 80 --

UNACCEPTABLE

-OPERATION \ UNP..CCEPTABLE OPERATION ,_____

I~

J b

~

~

~

0 i!l.,

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E 60 I

J ACCEPT ABLE OPERATION*

~

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i,.,

'11

.c I-

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+I

~

a: 40 20 0 I 50 -40 -30 -20 -10 0 10 20 30 40 50 60 Flux Difference, % Delta~!

MILLSTONE - UNIT 3 TRM 8.1-17 - LBDCR 16-MP3-001

TECHNICAL REQUIREJ\1ENTS MANUAL APPENDIX 8.1 CORE OPERATJNG LIMITS REPORT

!Figme 8 .K(Z) a Norrma~ozedl FQ(Z) as ai Function of Core Height 1.2 1.1 1.0 0.9 ----

~

N

"--" 0.8

~

0 uro 0.7 LL D) c 0.6

s::

ro Cl) o_

TI 0.5 Q.l N

ro E

,_ 0.4 0

z l47J Ele.talion 0.3 1D 0.0 Ft 1D 6.0 Ft o.ms 12D Ft 0.2 0.1 0.0 0 1 2 3 4 5 6 7 8 g 10 11 12 Core Elevation, (fuet)

MILLSTONE - UNIT 3 TRM 8.1-18 LBDCR 16-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LTh1ITS REPORT Table 1 RAOC W(Z) Function, Millstone Unit 3 - Cycle 18

-12/+9 AFD at 100% RTP Burnup Step (MWD/MTU)

Mesh No. Height* 150 3000 10000 18000 1 12.0778 1.0000 1.0000 1.0000 1.0000 2 11.9100 1.0000 1.0000 1.0000 1.0000 3 11.7423 1.0000 1.0000 1.0000 1.0000 4 11.5745 1.0000 1.0000 1.0000 1.0000 5 11.4068 1.0000 1.0000 1.0000 1.0000 6 11.2390 1.0000 1.0000 1.0000 1.0000 7 11.0713 1.3602 1.3804 1.4268 1.3239 8 10.9035 1.3481 1.3708 1.4224 1.3165 9 10.7358 1.3308 1.3535 1.4140 1.3045 10 10.5680 1.3111 1.3343 1.4012 1.2921 11 10.4003 1.2906 1.3140 1.3844 1.2781 12 10.2325 1.2724 1.2932 1.3656 1.2611 13 10.0648 1.2558 1.2757 1.3449 1.2511 14 9.8971 1.2394 1.2584 1.3221 1.2469 15 9.7293 1.2223 1.2398 1.2983 1.2403 16 9.5616 1.2048 1.2236 1.2770 j

1.2363 17 9.3938 1.1874 1.2088 1.2601 1.2327 18 9.2261 1.1694 1.1934 1.2470 1.2255 19 9.0583 1.1482 1.1780 1.2342 1.2156 20 8.8906 1.1361 1.1661 1.2233 1.2039 21 8.7228 1.1364 1.1601 1.2166 1.2005 22 8.5551 1.1396 1.1565 1.2126 1.2047 23 8.3873 1.1431 1.1533 1.2085 1.2105 24 8.2196 1.1459 1.1505 1.2038 1.2152 25 8.0518 1.1481. 1.1502 1.2033 1..2187 26 7.8841 1.1494 1.1508 1.2033 1.2212 27 *1.7163 1.1498 . 1.1504 1.2013 1.2222 28 7.5486 1.1491 1.1489 1.1979 1.2219 29 7.3809 1.1476 1.1464 1.1933 1.2201 30 7.2131 1.1452 .1.1429 . 1.1873 1.2171 31 7.0454 1.1417 1.1385 1.1801 1.2127 32 6.8776 1.1382 1.1331 1.1718 1.2069 33 6.7099 1.1357 1.1268 1.1624 1.1999 34 6.5421 1.1329 1.1214 1.1520 1.1932 35 6.3744 1.1296 1.1172 1.1408 1.1867 36 6.2066 1.1255 1.1136 . 1.1289 1.1795 37 6.0389 1.1202 1.1084 1.1180 1.1710 38 5.8711 1.1163 1.1058 1.1097 1.1619

  • Distance from bottom of active core (feet)

Note: Surveillance exclusion zone is 8% top, 8% bottom.

MILLSTONE - UNIT 3 TRM 8.1-19 LBDCR 16-MP3-001

IBCHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 -

CORE OPERATING LIMITS REPORT Table 1 (Continued)

RAOC W(Z) Function, Millstone Unit 3 - Cycle 18

-12/+9 AFD at 100% RTP Burnup Step (MWD/MTU)

Mesh No. Height* 150 3000 10000 18000 39 5.7034 1.1157 1.1071 1.1052 1.1541 40 5.5356 1.1204 1.1125 1.1.049 1.1524 41 5.3679 1.1289 1.1185 1.1064 1.1522 42 5.2001 1.1357 1.1236 1.1076 1.1523 43 5.0324 1.1420 1.1283 1.1085 1.1516 44 4.8647 1.1481 1.1326 1.1100 1.1502 45 4.6969 1.1537 1.1365 1.1129 1.1479 46 4.5292 1.1589 1.1400 1.1154 1.1450 47 4.3614 1.1636 1.1430 1.1174 1.1416 48 4.1937 1.1679 1.1458 1.1193 1.1376 49 4.0259 1.1719 1.1482 1.1210 1.1327 50 3.8582 1.1754 1.1503 1.1229. 1.1305 51 3.6904 1.1786 1.1521 1.1279 1: 1317 .

52 3.5227 1.1823 1.1536 1.1327 1.1333 . '

53 3.3549 1.1878 1.1567 1.1372 1.1336 54 3.1872 1.1956 1.1639 1.1414 1.1341 55 3.0194 1.2035 1.1766 1.1453 1.1368 56 2.8517 1.2097 1.1919 1.1505 1.1456 57 2.6839 1.2160 1.2067 1.1586 1.1582 58 2.5162 1.2300 1.2211 1.1688 1.1712 59 2.3485 . 1.2484 1.2373 1.1797 1.1839 60 2.1807 1.2657 1.2566 1.1902 1.1966 61 2.0130 1.2826 1.2758 '1.2005 1.2091 62 1.8452 1.2993 1.2942 1.2105 1.2211 63 1.6775 1.3152 1.3119 1.2200 1.2327 64 1.5097 1.3300 1.3285 1.2287 1.2434 65 1.3420 1.3436 1.3437 1.2365 1.2532 66 1.1742 1.3555 1.3570 1.2430 1.2617 67 1.0065 1.3645 1.3673 1.2472 1.2675 68 0.8387 1.0000 1.0000 1.0000. 1.0000 69 0.6710 1.0000 1.0000 1.0000 1.0000 70 0.5032 1.0000 1.0000 1.0000 1.0000 71 0.3355 1.0000 1.0000 1.0000 1.0000 72 0.1678 1.0000 1~0000 1.0000 1.0000 73 0.0000. 1.0000 1.0000 1.0000 1.0000

  • Distance from bottom of active core (feet)

Note: Surveillance exclusion zone is 8% top, 8% bottom.

MILLSTONE - UNIT 3 TRM 8.1-20 LBDCR 16-MP3-001

TECHNICAL REQUIB.ElvIENTS MANUAL APPENDIX 8.1 CORE OPERATING LJJY.1ITS REPORT Table 2 Base Load! W(Z) Function Millstone Unit 3 ~ Cycle 18 Bumup Step (MWD/MTU)

Mesh No. Height* 150 3000 10000 18000 1 12.0778 1.0000 1.0000 1.0000 1.0000 2 11.9100 1.0000 1.0000 1.0000 1.0000 3 11.7423 1.0000 1.0000 1.0000 1.0000 4 11.5745 1.0000 1.0000 1.0000 1.0000 5 11.4068 1.0000 1.0000 1.0000 1.0000 6 11.2390 1.0000 1.0000 1.0000 1.0000 7 11.0713 1.1831 \ 1,2070 1.2291 1.1767 8 10.9035 1.1783 1.2077 1.2302 1.1702 9 10.7358 1.1708 1.2009 1.2281 1.1645 10 10.5680 1.1623 1.1942 1.2227 1.1602 11 . 10.4003 1.1539 1.1887 1.2154 1.1574 12 10.2325 1.1489 1.1819 1.2078 1.1574 13 10.0648 1.1473 1.1736 1.2029 1.1580 14 9.8971 1.1457 1.1651 1.1967 1.1574 15 9.7293 1.1418 1.1575 1.1864 1.1549 16 9.5616 1.1383 1.1502 1.1761 1.1525 17 9.3938 1.1330 1.1417 1.1642 1.1488 18 9.2261 1.1245 1.1315 1.1485 1.1425 19 9.0583 1.1185 1.1225 1.1330 1.1337 20 8.8906 1.1164 1.1124 1.1183 1.1232 21 8.7228 1.1163 1.1058 1.1127 . 1.1239 22 8.5551 1.1171 1.1060 1.1163 1.1324 23 8.3873 1.1186 1.1071 1.1201 1.1416 24 8.2196 1.1205 1.1082 1.1241* 1.1493 25 8.0518 1.1248 1.1120 1.1273 1.1562 26 7.8841 1.1296 1.1169 1.1298 1.1624

. 27 7.7163 1.1337 1:1207 1.1314 1.1674 28 7.5486 1.1367 1.1234 1.1321 1.17.12 29 7.3809 1.1385 1.1251 1.1320 1.1739 30 7.2131 1.1393 1.1259 1.1310 1.1755 31 7.0454 1.1391 1.1257 1.1294 1.1759.

32 6.8776 1.1378 1.1247 1.1267 1.1752 33 6.7099 1.1357 1.1228 1.1233 1.1733 34 6.5421 1.1329 1.1203 1.1212 1.1709 35 6.3744 1.1296 1.1173 1.1196 1.1687 36 6.2066 1.1254 1.1136 1.1172 1.1666 37 6.0389 1.1203 1.1088 1.1143 1.1636 38 5.8711 1.1154 1.1044 1.1102 1.1593

  • Distance from bottom of active core (feet)

Note: Surveillance exclusion zone is 8% top, 8% bottom.

MILLSTONE - UNIT 3 TRM 8.1-21 LBDCR 16-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 2 (Continued)

Base Load W(Z) Function Millstone Unit 3 - Cycle 18 Burnup Step (MWD/MTU)

Mesh No. Height* 150 3000 10000 . 18000 39 5.7034 . 1.1123 1.1015 1.1056 1.1541 40 5.5356 1.1105 1:0990* 1.1037 1.1504 41 5.3679 1.1095 1.0972 1.1034 1.1480 42 5.2001 1.1083 1.0964 1.1022 1.1456 43 5.0324 1.1066 1.0954 1.1006 1.1423 44 4.8647 1.1046 1.0939 1.0987 1.1382 45 4.6969 1.1022 1.0922 1.0964 *1.1~34 46 4.5292 1.0995 1.0903 1.0940 1.1281 47 4.3614 1.0966 1.0881 1.0913 1.1221 48 4.1937 1.0934 1.0858 1.0885 1.1157 49 4.0259 1.0900 1.0845 1.0856 1.1090 50 3.8582 1.0864 1.0843 1.0828 1.1019 51 3.6904 1.0828 1.0848 1.0826 1.0947 52 3.5227 1.0799 1.0853 1.0840 1.0878 53 3.3549 . 1.0780 1.0852 1.0854 1.0811 54 3.1872 1.0777 1.0852 1.0867 1.0797 55 3.0194 1.0826 1.0893 1.0877 1.0809 56 2.8517 1.0928 1.0998 1.0903 1.0862 57 2.6839 1.1040 1.1145 1.0982 1.0954 58 2.5162 1.1156 1.1296 1.1097 1.1049 59 2.3485 1.1274 1.1447 1,1210 1.1142 60 2.1807 1.1392 1.1600 1.1325 1.1237 61 2.0130 1.1510 1.1752 1.1439 1.1333 62 1.8452 1.1625 1.1901 1.1551 1.1426 63 1.6775 1.1736 . 1.2044 1.1657 1.1516 64 1.5097 1.1840 1.2177 1.1756 1.1601 65 1.3420 1.1935 1.2300 1.1847 1.1679 66 1.1742 1.2016 1.2407 1.1923 1.1745 67 1.0065 1.2076 1.2488 1.1976 1.1789 68 0.8387 1.0000 1.0000 1.0000 1.0000 69 0.6710 1.0000 1.0000 1.0000 1.0000 70 0.5032 1.0000 1.0000 1.0000 1.0000 71 0.3355 1.0000 1.0000 1.0000 1.0000 72 0.1678 1.0000 1.0000 1.0000 1.0000 73 0.0000 1.0000 1.0000 1.0000 1.0000

  • Distance from bottom of active core (feet)
  • Note: Surveillance exclusion zone is 8% top, 8% bottom.

MILLSTONE - UNIT 3 TRM 8.1-22 LBDCR 16-MP3-001 .

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 3 Part Power (74% RTP, 150 MWD/MTU) RAOC W(Z) Function Millstone Unit 3 - Cycle 18 Mesh No Height (ft)* W(z) 1 12.0778 1.0000 2 11.9100 1.0000 3 11.7423 1.0000 4 11.5745 . 1.0000 5 11.4068 1.0000 6 11.2390 1.0000 7 11.0713 1.2272 8 10.9035 1.2102 9 10.7358 1.1918 10 10.5680 1.1742 11 10.4003 1.1566 12 10.2325 1.1424 13 10.0648 1.1307 14 9.8970 1.1190 15 9.7293 1.1066 16 9.5616 1.0937 17 9.3938 1.0808 18 9.2261 1.0669 19 9.0583 1.0498 20 8.8906 1.0419 21 8.7228 1.0482 22 8.5551 1.0584 23 8.3873 1.0706 24 '

i 8.2196. 1.0802.

25 8.0518 1.0869 26 7.8841 1.0928 27 7.7163 1.0977 28 7.5486 1.1016 29 7.3808 1.1048 30 7.2131 1.1072 31 7.0454 . 1.1084 32 6.8776 1.1097 .

33 6.7099 1.1120 34 6.5421 1.1140 35 6.3744 1.1154 36 6.2066 1.1161 37 6.0389 1.1157 38 5.8711 1.1165

  • Distance from bottom of active core (feet)

Note: Surveillance exclusion zone is 8% top, 8% bottom.

MILLSTONE - UNIT 3 TRM 8.1-23 LBDCR 16-MP3-001

  • TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 3 (Continued)

Part Power (74% RTP, 150 MWD/MTU) RAOC W(Z) Function Millstone Unit 3 - Cycle 18 Mesh No Height (ft)* W(z) 39 5.7034 1.1207 40 5.5356 1.1301 41 5.3679 1.1433 42 5.2001 1.1548 43 5.0324 1.1657 44 4.8646 1.1765 45 4.6969 1.1868 46 4.5292 1.1965 47 4.3614 1.2061 48 4.1937 1.2151 49 4.0259 1.2237 50 3.8582 1.2320 51 3.6904 1.2398 52 3.5227 1.2481 53 3.3549 1.2583 54 3.1872 1.2711 55 3.0194 1.2841 56 2.8517 1.2955 57 2.6839 1.3067 58 2.5162 1.3263 59 2.3485 . 1.3508 60 2.1807 1.3740 61 2.0130 1.3967 62 1.8452 1.4196 63 1.6775 t.4416 64 1.5097 1.4627 65 1.3420 1.4827 66 1:1742 1.5012 67 1.0065 1.5173 68 0.8387 1.0000 69 0.6710 1.0000 70 0.5032 1.0000 71 0.3355 1.0000 72 0.1677 1.0000 73 0.0000 1.0000

  • Distance from bottom of active core (feet)

Note: Surveillance exclusion zone is 8% top, 8% bottom.

MILLSTONE - UNIT 3 TRM 8.1-24 LBDCR 16-MP3-001

TECHNICAL REQUIREMENTS :MANUAL APPENDIX 8.1 CORE OPERATJNG LIMITS REPORT Table 4 Burnup Penalty for !ncore Millstone Unit 3 - Cycle 18

  • Bumup (MWD/MTU) Penalty 150 . 1.020 471 1.027 632 1.031 793 1.033 954 1.033 1450 1.020 8350 1.020 8669 1.024 8829 1.027 8990 1.025 9151 1.024 9500 1.020.
  • Note: A Penalty of 1.02 shall be used outside of the burnup range shown in Table 4.

MILLSTONE - UNIT 3 TRM 8.1-25 LBDCR 16-MP3-001

TECHNICAL REQUIBEMENTS MANUAL APPENDJX 8.1 CORE OPERATING LIMITS REPORT 3.0 Analytical Methodls 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.

3.1 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,"

July 1985 (Westinghouse Proprietary). (Methodology for Specifications 2.1.1.1-Departure from Nucleate Boiling Ratio, 2.1.1.2-Peak Fuel Centerline Temperature, 3.1.1.3-Moderator Temperature Coefficient, 3.1.3.5-Shutdown Bank Insertion Limit, 3.1.3.6-Control Bank Insertion Limits, 3.2.1-AXIAL FLUX DIFFERENCE, 3.2.2-Heat Flux Hot Channel Factor, 3.2.3-Nuclear Enthalpy Rise Hot Channel Factor, 3.1.1.1.1, 3.1.1.1.2, 3.1.1.2-SHUTDOWN MARGIN, 3.9.1.1-Boron Concentration.)

3.2 WCAP-10216-P-A-R1A, "Relaxation of Constant Axial Offset Control FQ Surveillance Technical Specification," Rev. 1, February 1994 (Westinghouse Proprietary). (Methodology for Specifications 3.2.1-AXIAL FLUX DIFFERENCE [Relaxed Axial Offset Control] and 3.2.2-Heat Flux Hot "channel Factor [W(Z) surveillance requirements for FQ Methodology].)

3.3 WCAP-12945-P-A,*Volume 1 (Revision 2) and Volumes 2 through 5 (Revision 1), "Code Qualification Document for Best Estimate LOCA Analysis," March 1998 (Westinghouse Proprietary. (Methodology for*

Specifications 3.2.2-Heat Flux Hot Channel Factor.)

3.4 WCAP-16009-P-A, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncerta.inty Method *

(ASTRUM)," January 2005 (Westinghouse Proprietary). (Methodology for Specifications 3.2.2-Heat Flux Hot Channel Factor.)

3.5 WCAP-11946, "Safety Evaluation Supporting a More Negative EOL Moderator Temperature Coefficient Technical Specification for the Millstone Nuclear Power Station Unit 3," September 1988 (Westinghouse Proprietary).

3.6 WCAP-10054-P-A, "Westinghouse Small Break ECCS Eval1,1ation Model Using the NOTRUMP Code," August 1985 (Westinghouse Proprietary).

(Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor.)

3. 7 WCAP-10079-P-A, "NOTRUMP - A Nodal Transient Small Break and General Network Code," August 1985 (Westinghouse-Proprietary).

(Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor.)

3.8 WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Report," April 1995 (Westinghouse Proprietary). (Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor.)

MILLSTONE - UNIT 3 TRM 8.1-26 LBDCR 16-MP3-001

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 3.9 WCAP-8301, "LOCTA-IV Program: Loss-of Coolant Transient Analysis,"

June 1974 (Westinghouse Proprietary).

3.10 WCAP:.10054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model," July 1997 (Westinghouse Proprietary).

3.11 WCAP-87 45-P-A, "Design Bases for the Thermal Overpower L\T and Thermal Overtemperature L\T Trip Functions," September 1986 (Westinghouse Proprietary). (Methodology for Specifications 2.1.1 and 2.2.1.)

3.12 WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO'," July 2006 (Westinghouse Proprietary). (Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor.)

MILLSTONE - UNIT 3 TRM 8.1-27 LBDCR 16-MP3-001