ML101330268

Core Operating Limits Report, Cycle 14

ML101330268
Person / Time
Site:	Millstone
Issue date:	05/06/2010
From:	Jordan A Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
10-287, FOIA/PA-2011-0115
Download: ML101330268 (28)

Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station 3)"Domnion-Rope Ferry Road Waterford, CT 06385 MAY 0 6 2010 U.S. Nuclear Regulatory Commission -Serial No.10-287 Attention:- Document:Control Desk NSS&LIMLC R0 Washington,: DC .20555 Docket No. '50423

-License No. NPF-49

.DOMINION NUCLEAR CONNECTICUT.INC.

MILLSTONE POWER*STAT'I'IONUNIT: 3

COREOPERATING LMITS- RE PO RT, C.YCLEE *14

-n accordance with-the: Millstone Power.Station Unit-3 (MPS3) Technical"Specifications

.(TSs),-Section'6.9.1.6.d., Dominion Nuclear-C-onnedticut,zlnc.,'hereby submits,-as Enclosure I ,:the. Cycle -14'CoreQperating Limits-Report (COLR).

The MPS3 COLR: has been revised to*-incorporatethe~following:

-Editorial changes*.to increment the.cycle number'from .13to 14.

Cycle 14-specific changes-to the W(Z) values.

-Cycle 14-specific changes;,to the' burnup range-forW(Z): values.

'Administrative change related-to:FRTP, AH.

• Clarification of a,footnote- related-to. the -refueling-boron. concentration.

The. COLR has been incorporated :intothe*MPS3.Technical-ýRequirements Manual.

If you -have-any questions-or require .additionalinformation,ý please contact Mr. William-D.

Bartron at (860) 444-4301.

Sincerely, ian Site President - Millstone

Serial No.10-287 Docket No. 50-423 Core Operating Limits.Report, Cycle 14 Page 2 of 2

Enclosures:

(1)

Commitments made in this letter: None.

cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ms. C. J. Sanders NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8B3 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.10-287 Docket No. '50-423 ENCLOSURE I CORE OPERATING LIMITS REPORT, CYCLE 14 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

'TECHNICAL.REOUIREMENTS MA*NUAL

.-APPENDIX.8.1 CORE OPERATING LIMITS REPORT MILLSTONE UNIT 3 CYCLE 14 I CORE OPERATING LIMITS'REPORT MILLSTONE - UNIT 3 i TRM 8.1-1 LBDCR 10-MP3-009 April 13, 2010

TECHNICAL REQUIREMENTS MAINUAL APPENDIX8.1 CORE OPERATING LIMITS REPORT Table of Contents Section Title Page 1.0 Core Operating Limits Report -8.1-4 2.0 Operating Limits 8.4-4 2.1, "Safety Limits (Specification,2.1.1) 8.1-4 2.2 Limiting Safety System Settings (Specification,2.1'1) 8.1:5

.2.3 Shutdown Margin - MODE 1 and.2 (Specification 3/4.1.1.1. 1) 8.-6 2.4 Shutdown Margin -MODE 3, 4 and5.,Lo6o6psFilled (Specification 3/4.1.1.1.2) 8.1-6 2.5 Shutdown Margin -MODE 5 Loops-NotFilled (Specification 3/4.1.1.2) 8.-46 2.6 Moderator Temperature Coefficient(Specification 3/4.1..3) 8.1-6 2.7 "Shutdown Rod Insertion Limit (Specification 3/4.1.3-:5) 8.1-6 2.8 ControlRod Insertion Limits (Specification 3/4.1.3.6) 8.1-6 2.9 Axial Flux Difference (Specification 3/4.2.1.1) 8.1-7 2.10 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3/4.2.2.1) 8.1-7

,2.11 HeatFlux Hot Channel Factor Surveillance - FQ(Z)

(Specification 3/4.2.2.1.2) 8.1-7 2.12 RCS Total Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor - FNAH (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 SetpoinV(Specification 3/4.3.5) 8.1-9 2.15 Refueling Boron Concentration(Specification 3/4.9.1.1) 8.4-9 3.0 Analytical Methods 8.1-25 MILLSTONE - UNIT 3 TRM 8.1-2 LBDCR 08-MP3-029 October 22, 2008

TECHNICAL REQUIREMENTS ,MANUAL

,APPENDIX 8.1 3 CORE OPERATING LIMITS REPORT List of Figures Figure Title Page

-Figure 1 Reactor Core Safety Limit 8.1-10 Figure 2 Required Shutdown Margin for MODE 3 8.1-11 Figure 3 Required Shutdown Margin for MODE 4 8.1-42

,Figure 4 Required Shutdown Margin for MODE 5 with RCS Loops Filled 8.1-13 Figure 5 Required Shutdown Margin for MODE'5 with RCS Loops Not Filled 8.1-14 Control Rod Bank Insertion Limits versus Thermal Power 8.1!-.15 Figure 6 Axial Flux Difference Limits as a Function of Rated Thermal Power 8.1-16 Figure 7 K(Z) - Normalized FQ(Z) as a Function of Core Height 8.1-17 Figure 8 List of Tables Table Title .Page Table 1 RAOC W(Z) Function, Millstone Unit 3 - Cycle 14 8.1-18 I

- 12/+9 AFD at 100% RTP Table 2 Base Load W(Z) Function, Millstone Unit 3 - Cycle 14 8.1-20 1 Table 3 Part Power (74% RTP, 150 MWD/MTU) RAOC"W(Z) Function, Millstone Unit 3 - Cycle 14 "8.1-22 I Table 4 Bumup Penalty for Incore 8.1-24 MILLSTONE - UNIT 3 TRM 8.1-3 LBDCR 10-MP3-009 April 13, 2010

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Millstone Unit 3 Cycle 14 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operatinig Limits Report (COLR) for Millstone Unit 3 CycleThe 14 has been prepared ,in Technicalp accordance with the requirements of Technical Specification 6.9.1.6.a.

Specifications affected by this report are listed below.

2.1.1 .Safety Limits 2.2.1 LimitingiSafetY)System Settings 3/4..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 NucleaFEnthalpy Rise Hot ChannelFactor 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 NRC-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 10-MP3-009 April 13, 2010

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING-LIMITS REPORT 2.2 -Limiting Safety System Settings (Specification-2.2.1) 2.2.1 Overtemperature AT 2.2.1.1 Kl_*-201 2.2.1.2 K2 Ž 0.025 /!'F

.2.2.1.3 K 3 Ž0.00113/psi 2.2.1.4 T1 Ž8 seconds 2.2.1:5 T2 *3 seconds 2.2.1.6 T4 Ž>20 seconds 2.2.1.7 T5 -< 4*seconds 2.2.1.8 T' isloop specific indicated Tavg atRATED THERMAL POWER,

<587. I OF 2.2.1.9 P' is nominal pressurizer pressure, Ž-22050psia 2.2.1.10 f, (AI) 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 - qb between -18% and +10%, fl(AI) > 0, where qt and qb 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 percent that the magnitude of qt - qb exceeds -18%, the AT Trip Setpoint shall be automatically reduced by _>3.75% of its value at RATED THERMAL POWER.

(3) For eachpercent that the magnitude of qt - qb exceeds +10%, the AT Trip Setpoint shall be automatically reduced by Ž2.14% of its value at RATED THERMAL POWER.

2.2.2 Overpower AT 2,2.2.1 K4 < 1.10 2.2.2.2 Deleted 2.2.2.3 K6 >0.00 15 / OF when T > T" and K6

• 0/ F when T* T" 2..2.2.4 T1 > 8 seconds 2.2.2.5 T2 < 3 seconds MILLSTONE - UNIT 3 TRM 8.1-5 LBDCR 08-MP3-029 October 22, 2008

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT

-2.2:2.6 Deleted 2.2.7 T" is loop specific indicated Tavg at RATED THERMAL POWER,

_<*587.1 0 F 02.3 Shutdown Margin - MODE l and 2 (Specification 3/4.1.1.1.1) 2.3.1 The-SHUTDOWN MARGIN shall beig*reater than or equal to 1.3% Ak/k.

2.4 Shutdown Margin - MODE 3, 4 and's Loops Filled (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.

2.5 Shutdown Margin - MODES 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 yolume control system (CVCS) aligned to preclude reactor coolant system boron concentration reduction.

-2.6 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 2.6.1 The.BOL/ARO/0% - 70% RTP MTC shall be less positive than + 0:5 x 104 Ak/k/0 F. Above 70% RTP, the MTC limit is a linear ramp to 0 Ak/k/0 F at 100% RTP.

2.6.2 The EOL/ARO/RTP MTC shall be less negative than 65 x 104 Ak/k/0 F.

2.6.3 The 300 ppm/ARO/RTP MTC should be less negative than or equal to

- 4.9 x 104 Ak/k/°F, where: BOL stands for Beginning Of Cycle Life ARO stands for All Rods Out 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 3/4.1.315) 2.7.1 The shutdown rods shall be at least r220 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 MILLSTONE - UNIT 3 TRM 8.1-6 LBDCR 08-MP3-029 October 22, 2008

JTECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 1,,,

CORE OPERATING LIMITS REPORT

-,2.8.2 Control bank A shall be at least 20-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)

FRTP FQ(Z)* Q x K(Z) for P > 0.'5 RTP FQ FQ(Z) Q x K(Z) for P< 0.5 where: p = THERMAL POWER RATED THERMAL POWER 2.10.1 FRTPQ = 2.60.

2.10.2 K(Z) is provided in Figure 8.

2.11 Heat Flux Hot Channel Factor Surveillance - FQ(Z) (Specification 3/4.2.2.1.2)

RTP F Q x K(Z)

FQ(,Z):ý Q for P > 0.5 P x W(Z)

RTP F Q x K(Z)

FQ(Z) Q for P-<_ 0.5 0.5 x W(Z) where: p = THERMAL POWER RATED THERMAL POWER MILLSTONE - UNIT 3 TRM 8.1-7 LBDCR 08-MP3-029 October 22, 2008

TECHNICAL REOUIREMENTS-MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.11.1 FRTPQ = 2.60.

2.112.- 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 oT the core. The Cycle 14 burnup dependent RAOC W(Z) values.are validover.the range of'bumup from 0 to 21,900 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 14 burnup dependent BL W(Z) values arevalid over the range of burnup from 0 to,21,900 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 ,14 burnup dependent *PartPower W(Z)'vwlues are valid over 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 42.2.1.4. A 2% factor shall be used outside of the bumuprange'shown in Table 4.

2.12 RCS Total'FlowRate and Nuclear Enthalpy Riseilot Channel Factor - FNAH (Specification 3/4.2.3.1) 2.12.1 The RCS Total FlowRate shall be greater than or equal to 379j200 gpm.

2.12.2 FNAH < FRTPAH X (1 + PFAH'X [1 -_P])

where: p = THERMAL POWER RATED THERMAL POWER 2.12.2.1 FRTPAI = ,1586 for Robust Fuel Assemblies (RFA) and (RFA-2) 2.12.2.2 PFAH = 0.3 for P < 1.0.

MILLSTONE - UNIT 3 TRM 8.1-8 LBDCR 10-MP3-009-April 13, 2010

TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.13 DNB Parameters (Specification 3/4.2.5) 2.13.1 Indicated Reactor Coolant System .Tavg shall be maintained <_"593:5°F.

.2.13.2 Indicated 'Pressurizer .Pressure shall be:maintained >2204psia

• 2.14 Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3:5)**

.2.14.1 The Shutdown Margin Monitor (SMM).minimum count rate and Alarm Ratio Setting to meet LIMITING CONDITION FOR OPERATION (LCO) 3.35 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 3.31'5.b. 1 1:50 0-50 1L25 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 remains valid. The count rate is displayed on the SMM.

2.15 Refueling Boron Concentration (Specification 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 concentration of greater than or equal to -2600 ppm.

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.

Section 2.14 was prepared by Dominion based on boron dilution analyses performed by Westinghouse.

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).

I MILLSTONE - UNIT 3 TRM 8.1-9 LBDCR 10-MP3-009 April 13, 2010

TECHNICALREQUIREMENTSIMANUAL APPENDIX 8.1 CORE OPERATING LIMITS&REPORT Figure 1 Reactor CoreSafety.Limit I

-680

ý660

'640 w

d 620 I--

.U) 0 600 580 560 0 0.2 0.4 0!6 0.8 1 1.2 FRACTION OF RATED THERMAL POWER MILLSTONE - UNIT 3 TRM 8.1-10 LBDCR 08-MP3-029 October 22, 2008

Figure 2 Required Shutdown Margin for MODE 3 4.0 3.5 3.0 2.5 z

2.0 z

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

TRM 8.1-11 MILLSTONE - UNIT 3 LBDCR 08-MP3-029 October 22, 2008

Figure 3 Required Shutdown Margin for MODE 4 6.0 5.5 5.0 4.5 4.0 z

3.5 3: 3.0 z

2.5 0

2.0 X-U),

1.5 1.0 0.5 0.0 0 500 i000 1500 2000 2500 RCS CRITICAL BORON CONCENTRATION (ppm)

TRM 8.1-12 MILLSTONE - UNIT 3 LBDCR 08-MP3-029 OCtober 22, 2008

Figure 4 Required Shutdown Margin for MODE 5 with RCS Loops Filled 6.0 5.5 5.0 4.5 4.0 z

3.5 3.0 z

2.5 0

D- 2.0 1.5 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 08-MP3-029 October 22, 2008

Figure 5 Required Shutdown Margin for MOME 5 with RCS Loops Not Filled 7.0 (2200, 6.150) 6.5 6.0 (1252, 5.523) (2500, 6.150) 5.5 5.0 4.5 z

000z 4.0 Ole z

3.5 3.0 0

2.5 2.0 CO)

(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 8.1-14 MILLSTONE - UNIT 3 LBDCR 08-MP3-029 October 22, 2008

TECHNICAL REOUIREMENTSMANUAL APPENDIX 8.1 CORE OPERATING.LIMITS REPORT Figure 6 Control Rod Bank Insertion Limits versus Thermal Power

-240

-.220

-200.

1,80 160 T

i140 120 V,)

o 100 z

M80 0

60 40 20 0

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

MILLSTONE - UNIT 3 TRM 8.1-15 LBDCR 08-MP3-029 October 22, 2008

I '-

TECHNICAL.REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 7 Axial Flux Difference Limits as a Function of Rated Thermal Power 1;2 1.1 1.'0 0:9

'0:8 0 ,0.7 06 CK, 0.5 0~

0.

0.4 14ý! Elesafion 0.3 IJD 0.0 Ft IJD 8.0 Ft - __ _ ____

0.925 12JD Ft 0.2 0.1 010 0 1 2. 3 4 5 6 7 ý8 9 10 11 12 Core Elevation, (feet)

MILLSTONE - UNIT 3 TRM 8.1-16 LBDCR 08-MP3-029 October 22, 2008

,TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 8 K(Z) - Normalized FQ(Z) as a Function of Core Height 1,2 1.1 1.0 N

0

-0.7 U-0)

'0.6 (T3

'0-

-0. 0.5 N

(o E 0.4 L_.

0 z

_ _') Elefaon 0.3 1D 0.0 Ft 1D 6.0 Ft 0.925 12D Ft

'0.2 0.1 0.0 0 1 2 3 4 5 6 7 ý8 9 10 11 12 Core Elleation (feet)

MILLSTONE - UNIT 3 TRM 8.1-17 LBDCR 08-MP3-029 October 22, 2008

,TECHNICAL REQUIREMENTS -MANUAL APPENDIX 8.1

-CORE OPERATING.LIMITS REPORT Table 1 RAOC'W(Z) Function, Millstone Unit 3 - Cycle 14

-12/+9 AFD at 10%"RTP Burnup Step (MWU/M'[o)

Mesh No. Height* 150 11000 18600 1.0000 1 12.0000 1.0000 1.0000 1.0000 1.0000 2 11.8333 1.0000 1.0000 1.0000 1.0000 3 11.6667 1.0000 1.0000 1.0000 1.0000 4 11ý5000 1.0000 1.0000 1.0000 1.0000 5 11.3333 1.0000 1.0000 1.0000 1.0000 6 11.1667 1.0000 1.0000 1.0000 1.0000 7 11.0000 1.4306 1.4942 1.4136 1.3761 8 10.8333 1.4028 1.4769 1.4043 1.3722 9 10.6667 1.3828 1.4604 1-3919 1.3646 10 10":5000 1.3605 1.4399 1.3760 1.3536 11 10.3333 1.3349 1.4T81 1.3595 1.3403 12 10.1667 1.3083 1.3944 1.3432 1.3254 13 10.0000 1.2833 1.3671 1.3266 1.3093 14 9.8333 1.2585 1.3390 1.3093 1.2920 15 9.6667 l12320 1.3109 1.2901 1.2732 16 '9:5000 1,.2080 1.2830 1.2734 1;2530 17 9.3333 1.197-2 1.2619 1.2629 1.2351 18 9.1667 1.1850 1.2472 1.2505 1.2233 19 9.0000 1.1733 1.2315 1.2387 1.2181 20 8.8333 1.1717 1.2189 1.2304 1.2093 21 8.6667 1.1738 ,1.2102 1.2253 1.2085 22 8.5000 1.1765 1,2025 1.2210 1,2145 23 8.3333 1.1779 1.1935 1.2145 1.2195 24 8.1667 1.1783 1.1854 1.2072 1.2228 25 8.0000 1.1775 1.1816 1.2024 1.2248 26 7.8333 1.1757 1.1778 1.1968 1.22-54 27 7.6667 1.1728 1.1719 1.1911 1.2246 28 7.5000 1.17.15 1.1653 1.1[886 1.2224 29 7.3333 1.1691 1.1577 1.1857 1.2189 30 7.1667 1.1656 1.1494 1.1806 1.2143 31 7.0000 1.1610 1.1403 1.1743 1.2112 32 6.8333 1.1r554 1.1297 1.1668 1.2067 33 6.6667 1.1490 1.1196 1.11582 1.2008 34 6.5000 1.1420 1.1141 1.1484 1.1936 35 6.3333 1.1350 1.1116 1. 1381 1.1854 36 6.1667 1.1285 1.1097 1.1263 1.1766 37 6.0000 1.1242 1.1078 1.1128 1.1677 38 5.8333 1.1216 1.1057 1.1083 1.1589 39 5.6667 1.1198 1.1038 1.1089 1.1524 40 "5.5000 1.1-205 1.1036 1.1105 1.1526 Distance from bottom of active core (feet)

MILLSTONE - UNIT 3 TRM 8.1-18 LBDCR 10-MP3-009 April 13, 2010

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATINGLIMITS REPORT Table 1 (Continued)

RAOCW(Z)'Function, Millstone Unit 3- Cycle 14 I

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

Mesh No. Height* 150 5000 I:u00 18600 41 5.3333 1.1-248 1.1052 1.1135 1.1554 42 °5. 1667 1.1315 1.1105 1.1180 1.11'582 43 5.0000 1.13178 1.11'51 1.1-219 1.1603 44 4.8333 1.1434 1.1i90 1.,1257 1.4i617 45 4.6667 1.1488 1.1,228 1.1298 1.1622 46 4.5000 1.1'538 1.1261 1.1336 1.1621 47 4.3333 1.1584 1.1293 1.1371 1.1614 48 4.1667 1.1626 1.1321 1.1402 1.1600 49 4.0000 1.1665 1,1343 1.1432 1.15582 50 3:8333 1.1701 1.1377 1.1455 1.1560 51 3.6667 1.1733 1.1426 1.1480 1.1S534

-'52 3-5000 1.1765 1.1472 1.r526 113506 53 3.3333 1.1811 1.1516 1.B574 1.1479 54 3.1667 1.1882 1.1569 1.161 8 1.1460 "55 3.0000 1.1970 1.1639 1.1675 1.,1490 56 2.8333 1.2052 1.1709 1.1734 1.597

'57 2.6667 1.2136 1.1778 1.1799 1.1715 58 2.5000 1.2278 1.1906 1.1,925 1.1831 59 2.3333 1.2445 1.2044 1.2047 1.1,946 60 2.1667 1.2601 1.2194 1.2169 1.205.9 61 2.0000 1.2753 1.2356 12287 1.2169 62 1.8333 J1.2901 1.2511 1.2399. 1.2275 63 1.6667 1.3039 L2660 1.2504 1.2373 64 1.5000 1.3166 1.2798 1.2600 1.2464 65 1.3333 1.3284 1.2925 1.2686 1.2547 66 1.1667 1.3390 1.3040 1.2759 1.2617 67 1.0000 1.3478 1.3139 1.281-5 1.2670 68 0.8333 1.0000 1.0000 1.0000 1.0000 69 0.6667 1.0000 1.0000 1.0000 1.0000 70 0.5000 1.0000 1.0000 1.0000 1.0000 71 0.3333 1.0000 1.0000 1.0000 1.0000 72 0.1667 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)

MILLSTONE - UNIT 3 TRM 8.1-19 LBDCR 10-MP3-009 April 13, 2010

"i w TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATINGLIMITS REPORT Table 2 Base Load W(Z) Function Millstone Unit 3- Cycle 14 I Burnup Step (MWD/MTU)

Mesh No., Height* 150 .5000 11000 18600 1 12.0000 1.0000 1.0000 1.0000 1.0000 2 11.8333 1.0000 1.0000 1.0000 1.0000 3 11.6667 1.0000 1.0000 1.0000 1.0000 4 11 '5000 1.0000 1.0000 1.0000 1.0000

'5 11.3333 1.0000 1.0000 1.0000 1.0000

,6 11.1667 1.0000 1.0000 1.0000 1.0000 7 11.0000 1.1905 1.2 r85 1.1860 1.1'518 8 10.8333 1.1811 1.2131 1.1837 11.1505

.9 10.6667 1.1750 1.20I81 1.1806 1.1465 10 10:5000 1.1686 1.2029 1.1763 1.1424 11 10.3333 1.1616 1.1975 .1.1,7,28 1.1i378 12 10.1667 1.1541 1.1963 1.1710 1.1360 13 10.0000 1.1461 ,1.1.893 1.1703 1.J381 14 9.8333 1.1378 1.1793 1.1696 1..1383 15 9.6667 1.1339 1.1704 1.1689 1.1375 16 9.5 000 1.1305 1.1670 1.1680 1.1372 17 9.3333 1.1248 1.1611 1.1635 1.1345 18 .9.1667 1.1188 1.i"537 1.1564 1.1310 19 .9.0000 1.116'5 1.1491 1.1506 1.1,290 20 8.8333 1.1169 1.1465 1.1490 1.1235 21 8.6667 1.1212 1.1442 ,1.1487 1.1300 22 8'5000 1.1-258 1.1405 1.1476 1.1388

,23 8.3333 1.1304 1.1338 1.1443 1.1473 24 8.1667 1.1329 1.1282 1.1409 1.1'541 25 8.0000 1.1360 1.1286 1.1399 1.1599

- 26 7.8333 1.1380 1.1301 1.1383 1.1647 27 7.6667 1.1393 1.1299 1.1368 1.1683 28 7.5000 1.1418 1.1291 1.1387 1.1708 29 7.3333 1.1435 1.1276 1.1402 1.1722 30 7.1667 1.1437 1.12'52 1.1397 1.1732.

31 7.0000 1.1427 1.1-221 1.1383 1.1750 32 6.8333 1.1408 1.1190 1.1359 1.1754 33 6.6667 1.1378 1.1163 1.1324 1.1747 34 6.5000 1.1340 1.1138 1.1279 1.17-28 35 6.3333 1.1291 1.1117 1.1,227 1.1695 36 6.1667 1.1270 1.1097 1.1166 1.1656 37 6.0000 1.1243 1.1078 1.1094 1.1622 38 5.8333 1.1218 1.1057 1.1036 1.1576 39 5.6667 1.1199 1.1038 1.1028 1.1524 40 5.5000 1.1191 1.1024 1.1014 1.1498 Distance from bottom of active core (feet)

MILLSTONE - UNIT 3 TRM 8.1-20 LBDCR 10-MP3-009 April 13, 2010

t;~ii~.

TECHNICALREQUIREMENTS MANUAL

,APPENDIX 8.1

.CORE OPERATINGLIMITS REPORT Table 2 (Continued)

Base Load W(Z) Function Millstone Unit 3 - Cycle 14

-Burnup Step (MWD/MTU)

Mesh No. Height* 150 '5000 11=000 18600 41 5.3333 1.1185 1.1008 1.0993 1.1479 42 5.1667 1.1172 1.0991 1.0970 1.1452 43 5.0000 1.1154 1.0976 1.0943 1.1417 44 4.8333 1.1132 1.60957 1.0916 1.1374 45 4.6667 1.1106 1.0938 1.0896 1.1325 46 4;5000 1.1076 1.0025 1.0873 1.1270 47 4.3333 1.1043 1.09.11 1.0849 1.1.210 48 4.1667 1.1007 1.0895 1.0823 1.1145 49 4.0000 1.0969 1.0876 1.0792 1.1077

'50 3.8333 1.0929 1.0871 1.0782 1.1008

'51 3.6667 1.0888 1.0874 1.0798 1.0936 52 3.5000 1.0874 1.0879 1.0811 1.0862 53 3.3,333 1.0877 1.0880 1.0817 1.081.2 54 3.1667 1.0887 1.0880 1.0826 1.0790 "5'5 3.0000 1.0896 1.0904 1.0861 1.0861 56 2.8333 1.0920 1.0999 1.0938 1.0937

'57 2.6667 1.1027 1.1143 1.1049 1.1017

-58 2-5000 1.1148 1.1288 1.1162 1.1099

'59 2:3333 1.1267 1.1435 1.1272 1.1180 60 2.1667 1.1389 1.1'586 1.1383 1.1261 61 2.0000 1.1509 1.17'36 1.1493 1.1341 62 1.8333 1.1625 1.1881 1.1599 1.1418 63 1.6667 1.1735 1.2018 1.1698 1.1491 64 1.5000 1.1838 1.2147 1.1790 1.1f558 65 1.3333 1.1934 1.2264 1.1872 1.1618 66 1.1667 1.2020 1.2369 1.1943 1.1670 67 1.0000 1.2090 1.2457 1.1998 1.1706 68 0.8333 1.0000 1.0000 1.0000 1.0000 69 0.6667 1.0000 1.0000 1.0000 1.0000 70 0:5000 1.0000 1.0000 1.0000 1.0000 71 0.3333 1.0000 1.0000 1.0000 1.0000 72 0.1667 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)

MILLSTONE - UNIT 3 TRM 8.1-21 LBDCR 10-MP3-009 April 13,-2010

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1

ýCORE OPERATING LIMITS REPORT Table 3 Part Power (74% RTP,.150 MWD/MTU) RAOC W(Z) Function Millstone Unit 3 - Cycle 14 Mesh No Height (ft)* W(z<)

1 12.0000 1.0000 2 11.8333 1.0000 3 11.6667 1.0000 4 11,5000 1.0000

`5 11.3333 1.0000 6 11.1667 1.0000 7 11.0000 h2696 8 10.8333 1.2504 9 10.6667 1.2353 10 10.5000 1.2202 11 10.3333 1.2019 12 10.1667 .1.820 13 10.0000 1.1635 14 9.8333 1.1441 15 9.6667 1.1205 16 95000 1.1099 17 9.3333 1.1043 18 9.1667 1.0972 19 9.0000 1.0908 20 8.83-33 1.0937 21 8.6667 1.0991 22 8.5000 1.1047 23 8.3333 1.1088 24 8.1667 1.1116 25 8.0000 1.1131 26 7.8333 1.1133 27 7.6667 1.1142 28 75000 1.1149 29 7.3333 1.1156 30 7.1667 1.1168 31 7.0000 1.1173 32 6.8333 1.1168 33 6.6667 1.11"55 34 6.5000 1.1133 35 6.3333 1.1111 36 6.1667 1.1093 37 6.0000 1.1083 38 5.8333 1.1086 39 5.6667 1.1103 40 5.5000 1.1146 Distance from bottom of active core (feet)

-MILLSTONE - UNIT 3 TRM 8.1-22 LBDCR 10-MP3-009 April 13, 2010

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

Part Power (74% RTP, 150 MWDIMTU)RAOC'W(Z) Function Millstone Unit 3 - Cycle 14 Mesh No Height (ft)* W(z) 41 5.3333 .1.1216 42 -5.1667 1.1321 43 "5.0000 1.1418 44 4.8333 1.1i508 45 4.6667 1.'597 46 4.5000 1.1681

-47 4.3333 1.175.9 48 4.1667 1.17835 49 4.0000 1.1922

'50 3.8333 1.2009

'51 3.6667 1.2093 "52 375000 1.2169

'53 3.3333 1.2247

°54 3.1667 1.2328 55 3.0000 1.2425

-56 2.8333 1-2578 57 2.6667 1.2793 58 2.5000 1.3003 "59 2.3333 1.3208 60 2.1667 1.3414 61 2.0000 1.3613 62 1.8333 1.3797 63 1.6667 1.3969 64 1.5000 1.4148 65 1.3333 1.4327 66 1.1667 1.4488 67 1.0000 1.4625 68 0.8333 1.0000 69 0.6667 1.0000 70 0.5000 1.0000 71 0.3333 1.0000 72 0.1667 1.0000 73 0.0000 1.0000 Distance from bottom of active core (feet)

MILLSTONE - UNIT 3 TRM 8.1-23 LBDCR 10-MP3-009 April 13, 2010

,1 I TECHNICAL REQUIREMENTS ,MANUAL APPENDIX 8.1 CORE OPERATING-LIMITS REPORT Table 4 Butrnup Penalty for Incore*

Burnup 'Penalty 4659 1.020 4820 1.022 4981 1.,022

'5142 1.022

'5303 1.022

-5465 1.022 5626 1.021

-5787 1.021

'5948 .1.020

'Note: Apenalty of.1.02 shall be ased outside of the bumup range shown in Table 4.

MILLSTONE - UNIT 3 TRM 8.1-24 LBDCR 10-MP3-009 April 13, 2010

JTECHNICAL REQUIREMENTS MANUAL

,APPENDIX 8.1 CORE OPERATING LIMITS REPORT 3.0 Analytical Methods The analytical methods used to determine the core operating limits shail be those previously

-reviewed and approyed by the NRC, specifically those described in the following documents.

3.1 "WCAP-9272-P-A, "WISTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (& Proprietary).

3;2 WCAP-10216-P-A-R1A, "RELAXATION OF-CONSTANT AXIAL OFFSET C,,ONTROL FQ-SURVEILLANCE TECHNICAL SPECIFICATION,"Rev. 1, February 1994 (W Proprietary).

3.3 WCAP-l1294'5-P-A, Volume 1 (Revision 2) and Volumes 2 through 5 (Revision 1), "Code Qualification Document for BestEstimate LOCA Analysis," March 1998 (W Proprietary).

3.4 WCAP- 16009-P-A, "RealisticLarge-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January.2005 (W Proprietary).

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

3.6 WCAP-10054-P-A, "WESTINGHOUSE SMALL BREAK ECCS EVALUATION MODEL 17 USING THE NOTRUMP CODE," August 1985 (W Proprietary).

3.7 WCAP- 10079-P-A, "NOTRUMP - A NODAL TRANSIENT SMALL BREAK AND GENERAL NETWORK CODE," August 1985 (W Proprietary).

3.8 WCAP-12610-P-A, "VANTAGE+ Fuel AssemblyReport," April 1995 (W Proprietary).

3.9 WCAP-8301, "LOCTA-IV Program: Loss-of-Coolant'Transient Analysis," June 1974 (W 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 CondensationModel," July 1997 (3W Proprietary).

3.11 WCAP-8745-P-A, "DESIGN BASES FOR THE THERMAL OVERPOWER AT AND THERMAL OVERTEMPERATURE AT TRIP FUNCTIONS," September 1986 (W Proprietary).

MILLSTONE - UNIT 3 TRM 8.1-25 LBDCR 08-MP3-029 October 22, 2008