ML101330268

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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)
v • d • e


Text

3)"Domnion-Dominion Nuclear Connecticut, Inc.

Millstone Power Station Rope Ferry Road Waterford, CT 06385 MAY 0 6 2010 U.S. Nuclear Regulatory Commission Attention:- Document:Control Desk Washington,: DC.20555

-Serial No.

NSS&LIMLC Docket No.

-License No.10-287 R0

'50423 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 M PS3 COLR: has been revised to*-incorporatethe~following:

-Editorial changes*.to increment the.cycle number'from.1 3to 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 President - Millstone Site

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 CORE OPERATING LIMITS'REPORT I

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 - FN AH (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

3 Figure

-Figure 1 Figure 2 Figure 3

,Figure 4 Figure 5 Figure 6 Figure 7 Figure 8 TECHNICAL REQUIREMENTS,MANUAL

,APPENDIX 8.1 CORE OPERATING LIMITS REPORT List of Figures Title Reactor Core Safety Limit Required Shutdown Margin for MODE 3 Required Shutdown Margin for MODE 4 Required Shutdown Margin for MODE 5 with RCS Loops Filled Required Shutdown Margin for MODE'5 with RCS Loops Not Filled Control Rod Bank Insertion Limits versus Thermal Power Axial Flux Difference Limits as a Function of Rated Thermal Power K(Z) - Normalized FQ(Z) as a Function of Core Height List of Tables Page 8.1-10 8.1-11 8.1-42 8.1-13 8.1-14 8.1!-.15 8.1-16 8.1-17 Table Title Table 1 RAOC W(Z) Function, Millstone Unit 3 - Cycle 14

-12/+9 AFD at 100% RTP Table 2 Base Load W(Z) Function, Millstone Unit 3 - Cycle 14 Table 3 Part Power (74% RTP, 150 MWD/MTU) RAOC"W(Z) Function, Millstone Unit 3 - Cycle 14 Table 4 Bumup Penalty for Incore

.Page 8.1-18 I

8.1-20 1

"8.1-22 8.1-24 I

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 Cycle 14 has been prepared,in accordance with the requirements of Technical Specification 6.9.1.6.a. The Technicalp 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_

1

  • -20 2.2.1.2 K2 Ž 0.025 /!'F

.2.2.1.3 K3 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 T 1 > 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 0F 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/0F. Above 70% RTP, the MTC limit is a linear ramp to 0 Ak/k/0F at 100% RTP.

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

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 *Part Power 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 < FRTP AH 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

.2.14.1 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

FRACTION OF RATED THERMAL POWER 1.2 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 z

z 0

U) 3.0 2.5 2.0 1.5 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 z

z3:

0 X-U),

6.0 5.5 5.0 4.5 4.0 3.5 3.0 2.5 2.0 1.5 1.0 0.5 0.0 0

500 i000 1500 RCS CRITICAL BORON CONCENTRATION (ppm) 2000 2500 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 z

z 0

D-6.0 5.5 5.0 4.5 4.0 3.5 3.0 2.5 2.0 1.5 1.0 0.5 0.0 0

MILLSTONE - UNIT 3 500 1000 1500 RCS CRITICAL BORON CONCENTRATION (ppm)

TRM 8.1-13 2000 2500 LBDCR 08-MP3-029 October 22, 2008

Figure 5 Required Shutdown Margin for MOME 5 with RCS Loops Not Filled z

z 0

CO) 7.0 6.5 6.0 5.5 5.0 4.5 4.0 3.5 3.0 2.5 2.0 1.5 1.0 0.5 0.0 (2200, 6.150)

(1252, 5.523)

(2500, 6.150) 00 0z Ole (0,1.300)

(355, 1.300) 0 500 1000 1500 RCS CRITICAL BORON CONCENTRATION (ppm) 2000 2500 MILLSTONE - UNIT 3 TRM 8.1-14 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 T

160 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

CK, 0~

0.

'0:8

,0.7 06 0.5 0.4 0.3 0.2 0.1 010 14ý!

Elesafion IJD 0.0 Ft IJD 8.0 Ft 0.925 12JD Ft 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 N

0 U-0)

(T3

'0-

-0.

N (oE L_.

0z 1,2 1.1 1.0

-0.7

'0.6 0.5 0.4 0.3

'0.2 0.1 0.0

_')

Elefaon 1D 0.0 Ft 1D 6.0 Ft 0.925 12D Ft 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 Mesh No.

Height*

150 1

12.0000 1.0000 2

11.8333 1.0000 3

11.6667 1.0000 4

11ý5000 1.0000 5

11.3333 1.0000 6

11.1667 1.0000 7

11.0000 1.4306 8

10.8333 1.4028 9

10.6667 1.3828 10 10":5000 1.3605 11 10.3333 1.3349 12 10.1667 1.3083 13 10.0000 1.2833 14 9.8333 1.2585 15 9.6667 l12320 16

'9:5000 1,.2080 17 9.3333 1.197-2 18 9.1667 1.1850 19 9.0000 1.1733 20 8.8333 1.1717 21 8.6667 1.1738 22 8.5000 1.1765 23 8.3333 1.1779 24 8.1667 1.1783 25 8.0000 1.1775 26 7.8333 1.1757 27 7.6667 1.1728 28 7.5000 1.17.15 29 7.3333 1.1691 30 7.1667 1.1656 31 7.0000 1.1610 32 6.8333 1.1r554 33 6.6667 1.1490 34 6.5000 1.1420 35 6.3333 1.1350 36 6.1667 1.1285 37 6.0000 1.1242 38 5.8333 1.1216 39 5.6667 1.1198 40 "5.5000 1.1-205 Distance from bottom of active core (feet)

(MWU/M'[o) 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.4942 1.4769 1.4604 1.4399 1.4T81 1.3944 1.3671 1.3390 1.3109 1.2830 1.2619 1.2472 1.2315 1.2189

,1.2102 1,2025 1.1935 1.1854 1.1816 1.1778 1.1719 1.1653 1.1577 1.1494 1.1403 1.1297 1.1196 1.1141 1.1116 1.1097 1.1078 1.1057 1.1038 1.1036 11000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.4136 1.4043 1-3919 1.3760 1.3595 1.3432 1.3266 1.3093 1.2901 1.2734 1.2629 1.2505 1.2387 1.2304 1.2253 1.2210 1.2145 1.2072 1.2024 1.1968 1.1911 1.1[886 1.1857 1.1806 1.1743 1.1668 1.11582 1.1484

1. 1381 1.1263 1.1128 1.1083 1.1089 1.1105 18600 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3761 1.3722 1.3646 1.3536 1.3403 1.3254 1.3093 1.2920 1.2732 1 ;2530 1.2351 1.2233 1.2181 1.2093 1.2085 1,2145 1.2195 1.2228 1.2248 1.22-54 1.2246 1.2224 1.2189 1.2143 1.2112 1.2067 1.2008 1.1936 1.1854 1.1766 1.1677 1.1589 1.1524 1.1526 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

-12/+9 AFD at 100% RTP I

Burnup Step (MWD/MTU)

Mesh No.

41 42 43 44 45 46 47 48 49 50 51

-'52 53 54 "55 56

'57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 Height*

5.3333

°5. 1667 5.0000 4.8333 4.6667 4.5000 4.3333 4.1667 4.0000 3:8333 3.6667 3-5000 3.3333 3.1667 3.0000 2.8333 2.6667 2.5000 2.3333 2.1667 2.0000 1.8333 1.6667 1.5000 1.3333 1.1667 1.0000 0.8333 0.6667 0.5000 0.3333 0.1667 0.0000 150 1.1-248 1.1315 1.13178 1.1434 1.1488

1. 1'538 1.1584 1.1626 1.1665 1.1701 1.1733 1.1765 1.1811 1.1882 1.1970 1.2052 1.2136 1.2278 1.2445 1.2601 1.2753 J1.2901 1.3039 1.3166 1.3284 1.3390 1.3478 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 5000 1.1052 1.1105 1.11'51 1.1i90 1.1,228 1.1261 1.1293 1.1321 1,1343 1.1377 1.1426 1.1472 1.1516 1.1569 1.1639 1.1709 1.1778 1.1906 1.2044 1.2194 1.2356 1.2511 L2660 1.2798 1.2925 1.3040 1.3139 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 I:u00 1.1135 1.1180 1.1-219 1.,1257
1. 1298 1.1336 1.1371 1.1402 1.1432 1.1455 1.1480
1. r526
1. B574 1.161 8 1.1675 1.1734 1.1799 1.1,925 1.2047 1.2169 12287 1.2399.

1.2504 1.2600 1.2686 1.2759 1.281-5 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 18600 1.1554 1.11'582 1.1603 1.4i617 1.1622 1.1621 1.1614 1.1600 1.15582 1.1560 1.1S534 113506 1.1479 1.1460 1.,1490 1.597 1.1715 1.1831 1.1,946 1.205.9 1.2169 1.2275 1.2373 1.2464 1.2547 1.2617 1.2670 1.0000 1.0000 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 Mesh No.,

Height*

150 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 1.1905 8

10.8333 1.1811

.9 10.6667 1.1750 10 10:5000 1.1686 11 10.3333 1.1616 12 10.1667 1.1541 13 10.0000 1.1461 14 9.8333 1.1378 15 9.6667 1.1339 16 9.5 000 1.1305 17 9.3333 1.1248 18

.9.1667 1.1188 19

.9.0000 1.116'5 20 8.8333 1.1169 21 8.6667 1.1212 22 8'5000 1.1-258

,23 8.3333 1.1304 24 8.1667 1.1329 25 8.0000 1.1360

- 26 7.8333 1.1380 27 7.6667 1.1393 28 7.5000 1.1418 29 7.3333 1.1435 30 7.1667 1.1437 31 7.0000 1.1427 32 6.8333 1.1408 33 6.6667 1.1378 34 6.5000 1.1340 35 6.3333 1.1291 36 6.1667 1.1270 37 6.0000 1.1243 38 5.8333 1.1218 39 5.6667 1.1199 40 5.5000 1.1191 Distance from bottom of active core (feet)

(MWD/MTU)

.5000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2 r85 1.2131 1.20I81 1.2029 1.1975 1.1963

,1.1.893 1.1793 1.1704 1.1670 1.1611 1.i"537 1.1491 1.1465 1.1442 1.1405 1.1338 1.1282 1.1286 1.1301 1.1299 1.1291 1.1276 1.12'52 1.1-221 1.1190 1.1163 1.1138 1.1117 1.1097 1.1078 1.1057 1.1038 1.1024 11000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1860 1.1837 1.1806 1.1763

.1.1,7,28 1.1710 1.1703 1.1696 1.1689 1.1680 1.1635 1.1564 1.1506 1.1490

,1.1487 1.1476 1.1443 1.1409 1.1399 1.1383 1.1368 1.1387 1.1402 1.1397 1.1383 1.1359 1.1324 1.1279 1.1,227 1.1166 1.1094 1.1036 1.1028 1.1014 18600 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

1. 1'518 11.1505 1.1465 1.1424 1.1i378 1.1360 1.J381 1..1383 1.1375 1.1372 1.1345 1.1310 1.1,290 1.1235 1.1300 1.1388 1.1473 1.1'541 1.1599 1.1647 1.1683 1.1708 1.1722 1.1732.

1.1750 1.1754 1.1747 1.17-28 1.1695 1.1656 1.1622 1.1576 1.1524 1.1498 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 Mesh No.

Height*

150 41 5.3333 1.1185 42 5.1667 1.1172 43 5.0000 1.1154 44 4.8333 1.1132 45 4.6667 1.1106 46 4;5000 1.1076 47 4.3333 1.1043 48 4.1667 1.1007 49 4.0000 1.0969

'50 3.8333 1.0929

'51 3.6667 1.0888 52 3.5000 1.0874 53 3.3,333 1.0877 54 3.1667 1.0887 "5'5 3.0000 1.0896 56 2.8333 1.0920

'57 2.6667 1.1027

-58 2-5000 1.1148

'59 2:3333 1.1267 60 2.1667 1.1389 61 2.0000 1.1509 62 1.8333 1.1625 63 1.6667 1.1735 64 1.5000 1.1838 65 1.3333 1.1934 66 1.1667 1.2020 67 1.0000 1.2090 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)

(MWD/MTU)

'5000 1.1008 1.0991 1.0976 1.60957 1.0938 1.0025 1.09.11 1.0895 1.0876 1.0871 1.0874 1.0879 1.0880 1.0880 1.0904 1.0999 1.1143 1.1288

1. 1435 1.1'586 1.17'36 1.1881 1.2018 1.2147 1.2264 1.2369 1.2457 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11=000 1.0993 1.0970 1.0943 1.0916 1.0896 1.0873 1.0849 1.0823 1.0792 1.0782 1.0798 1.0811 1.0817 1.0826 1.0861 1.0938 1.1049 1.1162 1.1272 1.1383 1.1493 1.1599 1.1698 1.1790 1.1872 1.1943 1.1998 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 18600 1.1479 1.1452 1.1417 1.1374 1.1325 1.1270 1.1.210 1.1145 1.1077 1.1008 1.0936 1.0862 1.081.2 1.0790 1.0861 1.0937 1.1017 1.1099 1.1180 1.1261 1.1341 1.1418 1.1491 1.1f558 1.1618 1.1670 1.1706 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 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

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