ML102240069

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Correction to Previously Submitted Correspondence for Cycle 14 Core Operating Limits Report
ML102240069
Person / Time
Site: Millstone Dominion icon.png
Issue date: 07/29/2010
From: Jordan A
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
10-287A, FOIA/PA-2011-0115
Download: ML102240069 (28)
v • d • e


Text

Dominion Nuclear Connecticut, Inc.Do Millstone Power Station ion Rope Ferry Road Waterford, CT 06385

'JUL 2 9 2010 U.S. Nuclear Regulatory Commission Serial No. 10-287A Attention: Document Control Desk NSS&LIMLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 CORRECTION TO PREVIOUSLY SUBMITTED CORRESPONDANCE FOR CYCLE 14 CORE OPERATING LIMITS REPORT The-purpose of this letter is to correct an error that was inadvertently introduced to the docket for Millstone"Power Station Unit 3 (MPS3). On May 6, 2010, Dominion Nuclear

...Connecticut, Inc. (DNC),submitted the Core Operating Limits Report (COLR) for MPS3 Cycle 14. On June 22, 2010, while referencing the electronic version of the MPS3 Technical Requirements Manual (TRM), DNC discovered that Figure 7 of the COLR (Page 8.1-16) contained a duplicatecopy of the graph contained in Figure 8 (Page 8.1-17). This error was introduced during electronic publishing of the TRM change for the Cycle 14 COLR, which has since been corrected. Controlled hard copies of the TRM, including control room copies, were not affected by this error. -Enclosure I contains the corrected version of the MPS3 Cycle 14 COLR.

We apologize for any inconvenience this may have caused.

-If you have any questions or require additional information, please contact Mr. William D.

- Bartron at (860) 444-4301.

Sincerely, SiteV~ Peident;-

ne M~illstone-S e rden

Serial No. 10-287A

'Docket No. 50-423

, ,Correction to Cycle 14.COLR Page 2 of 2 Epdloures: (1)

Commitmebts Made in this letter: 'None.

,cc: U.S. Nuc'learRegulatory-Comhrission Region I 475 Allendale Road

,King of Prussia, PA 194,06-J 4 15 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

SSeral.No. 287A Doc-ket'No. 50-423 ENCLOSURE 1 CORE OPERATING LIMITS REPORT, CYCLE 14 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

TECHNICAL REQUIREMENTS MANUAL

,APPENDIX 8.1

,,CORE OPERATINGJLIMITS'REPORT

)

'MILLSTONE MNIT.3 CYCLE 14 1:

ýCORE OPERATING LIMITS REPORT:

D,-I MILLSTONE - UNIT3 .TRM 81-1.. LBDCR-10-MP3-009 April 13, 2010

TECHNICAL REOUIREMENTS MANUAL APPENDIX .8.1

.CORE OPERATING LIMITS.REPORT Table of Contents Section Title -Page 1.0 .Core Operating Limits Report 8.1-4 Q,.0 Operating Limits 8.1-4 2.1 Safety Limits (Sperification 2.,i .. ) 8.1-4

  • 2.-2 .Limiting Safety.System Settings (SOpification 2.2.1) 8.1-5

-,2.3 'Shutdown Mar-gin - MODE I and . (Specification 3/4. 1.13.1.1) 8.1-6

-2.4 Shutdown Margin - MODE,3,4-andP5 Loops-Filled (Specification 3/4.1.1.1.:2) 8.1-6

-2.-5 -Shutdown'Margin - MODE5 LoopsýNot Filled (Specification 3/4.1.1 .2) -8.1-6 S26 MOderator Temperature Coeff~ent (Specification 3/4.1.1.3) ý8.1-6 2.7 Shutdown Rod Insertion Limit.(Specification 3/4.1.35) 8.1-6

-2.8 Control Rod Insertion Limits (Specifficatiorn3/4.1.3.6) 8.1-6 A2.9 xial Flux Differenee:(Specificition 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 Heat Flux Hot ChannelFactor Suryeillance - FQ(Z)

,(Specification 3/4.2.2.1.2) 8.1-7 2.12 RCS Total'Flow Rate and Nuclear Enthalpy'kise Hot Channel Factor - FN AH (Specifitcation 3/4.2.3.1I) 8.1-8 2.13 DNB Parameters (Specification 3/4.2.5) 8.1-9 2..14. ShutdownMargin Monitor Alarm Setpoint.(Specification3/4.35) 8.1-9 2.115 RefuelingBoron Concentration-(Speci'fication 3/4.9. .1) 8.1-9 3.0 Analytical Methods 8.1-25 MILLSTONE - UNIT 3 :TRM 8.1-2 LBDCR,08-MP3-029 October 22, 2008

TECHNICAL REOUIREMENTS-MANUAL APPENDIX 8.1 CORE OPERATING LIMITS.REPORT

.J List of Figures Figure Title Page Figure 1 Reactor Core Safety Limit 8.1-10 Tigure 2 Required Shutdown'Margin for MODE 3 8.1-42 Figure 3 RequiredShutdown Margin for MODE-4 Figure 4 Required Shutdown Margin for MODE5 "withRCS Loops Filled 8.1-13 Figure~5 Required Shutdown Margin for MODE5 withRCS Loops.Not Filled 8.1-:14

'8.1-15 Figure 6 Control.Rod Bank InsertionLimits versus Thermal Power Figure 7 .Axial Flux Difference Limits as a Function of Rated Thermal Power 8.1-16 Figure 8 K(Z) -'Normalized FQ(Z) as a Function-of.Core Heright :8.1-17 List of Tables y.) Table 'Title Page Table I RAOC'W(Z) Function, Millstone Unit 3 -Cycle 14 8.1-18 I

-12/+9 AFD at 100,oRTP Table 2 Base Load W(Z) Function, Millstone Unit 3 - Cycle 14 8.1-20 Table 3 Part Power (74% RTP, 150'MWD/MTU) RAOC W(Z) Function, Millstone Unit.3 - Cycle 14 8.1--22 I Table 4 Burnup Penalty for Incore 8.1-24 Qi)

MILLSTONE - UNIT 3 . TRM 8.1-3 LBDCR 10`MP3M09."

April 13, 2010

TECHNICAL REOLUIREMENTS ýMANUAL APPENDIX 8.1 CORE OPERATING. LIMITS REPORT

  • 1 Millstone Unit 3 Cycle 14 I Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR)for Millstone Unit 3 Cycle 14 has beenprepared in I accordance with therequirements of Technicai Specification 6.9.1.6.a. The Technical

'Specifications affected by this report are listed below.

-2.1.1 SafetyLimits 2.2.1 Limiting Safety System Settings 3/4.1.1.1.1 Shutdown.Margin - MODE 1 and 2 314.1.1.1492 Shutdown Margin -MODES 3,4 and5 Loops Filled 3/4.1.1.2. ShutdownMargin - MODE-5 LoopsNot Filled 3./4.1.1.3 Moderator Temperature Coefficient 3/4.1.3:5 Shutdown Rod Insertion Limit 3/4.1.3.6 ControlRod Insertion Limits 3/14.2.1.1 Axial Flux Difference 3/4.2.2.1 Heat Flux Hot Channel Factor 3/4.2.3.1 RCS Total Flow Rate and'NuclearEnthalpy 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 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.

0 MILLSTONE - UNIT 3 TRM 8.1-4 LBDCR !0-MP3-009 April 13, 2010

TECHNICAL REOQUIREMENTS MAýNUAL APPENDIX 8.1 CORE OPERATING LIMITS:REPORT 2.,2 Limiting Safety System-Settings (Specificationg.2.2.1) 22.1 Overtemperature-AT

-2,2.1.1 K 1 *_<1.20 2.2.1.2 K 2 > 0.0251/OF 212.1.3 K 3 >-0.00113/psi

.2.2.1.4 z: 8-seconds

.2.2.1.5 f2 *3 seconds

.2.2.1.6 . 4 >20 seconds 2.2.1.7 - < 4 seconds

.2.2.1.8 T' is loop specific indicatedjTavn at RATED THERMAL POWER,

._587.1 0F

,.2.2.1.9 P' is nominal pressurizer pressure,.'>,2 50 psia

-2.2.1.10 fl(Al) is a function -ofthe 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:

(l) For q, - qb between.-18% and +10%, f1 (AI) > 0, where qt and qb are percent RATED THERMAL'POWER in the upper and lower halves of the core, respectively, and q, + 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 2!3.75% of its value at RATED THERMAL POWER.

(3) For each per-cent that the magnitude of qt - qb.exceeds +/-10%, the AT Trip Setpoint.shall be automatically reduced by. 2.14% of its value at RATED THERMAL POWER.

.2.2.2 Overpower AT 2.2.2.1 K4*< 1.10

-222.2 Deleted 22.2.3 K6 > 0.001O5/°F when T > T" and.K61(_ 0 / 0 F'when'T<_ T"

.2.22.4 -1 Ž8 -seconds 2.2.5 t-

  • 3 'seconds MILLSTONE - UNIT 3 TRM 8.1-5 LBDCR 08-MP3-029

.October 22,2008 I

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERAT!NG LIMITS REPORT

.2.2.2.6 Deleted 2.2.2.7 T" is loop-specific indicated Tayg atRATED THERMAL POWER,

< 587.1W°

.2.3 Shutdown Margin - MODE 1 and2 :(Specification 3/4.1.1.1.1)

..2.3.1 The SHUTDOWN MARGIN-shall be.,greater than or equal to 1.3% Ak/k.

2.4 'Shutdown Margin - MODE 3, 4 and'5 Loops Filled (Specification 3/4.11.1.2)

.2.4.1 The SHUTDOWN MARGIN shall bergreater than orequal to the limits shown inFigures 2, 3 and 4.

235 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 f*igure 4 with the chemical and volume 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 0-4 Ak/k/!F. Above 70% RTP, the'MTC limit is a linear ramp to 0 Ak/k/°F at S-100% RTP.

2.6.2 The EOL/ARO/RTP MTC shall be less negative than - 5.65 x 10-4 Ak/k/ 0 F.

2.6,.3 The 300 ppm/ARO/RTP MTC 'should be less.negative than or equal to

- 4.9 x 10-4 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 3/4.1.3:5) 2.7..1 The"shutdown rods'shall be at least220 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 2Figure 6, and MILLSTONE - UNIT 3 TRM 8.1-6 LBDCR 08-MP3-029 October 22, 2008

TECHNICAL REOUIREMENTS ýMANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT

-2.8:22 Control bank A shall be at.least,2-20'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.

1.10 Heat Flux Hot ChanneF Factor - FQ(Z) (Specffication 3/4.2.2.1)

RTP FQ FQ(_):ý* xxK(Z) for P > 0.5

'P FRTP FQ(Z) - 0*. x K(Z) for P-_* 0.5 where: p = THERMAL POWER RATED THERMAL POWER 2.30.1 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 x K(Z)

FQ(Z)_< Q forP>0.5 P.XW(4Z)

RTP FQFQZ) forP <0.5 F -(Z)*

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 REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.11.1 FRTPQ = 2.60.

.2.11.2 K(Z) is provided inFigure 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 14 burnup dependent RAOC W(Z) values are valid over therange of bumup from 0 to 21,900IMWDIMTU.

.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 bumup dependent BL'W(Z) values are valid overfthe 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 I are at the top of the core. The Cycle ,14 burnup dependent Part Power W(Z) values are valid over the range of burnup from 0 to .150 MWD/MTU.

-2.1,1.6 -- The factors in Table 4.shall be used for surveillance requirements 4.2.2.1.2 and 4.2.2.1.4. A .2%,factor shall b1 used outside of the burnup range shown in Table 4.

2.12 RCS Total Flow Rate and.NuclearEnthalpy'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.

VN T

.2.12.2 F AH "< FRAH x (1 + PFAHX [1 -P1) where: p = THERMAL POWER RATED THERMAL POWER 2.12.2.1 FR7PAH = 1.586 for Robust FuelAssemblies (RFA).and (RFA-2)

-2.12.2.* PFAH = 0.3 for P < 1.0.

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

TECHNICAL REQUIREMMNTS MANUAL APPENDIX 8.1 CORE OPERATING:LWS REPORT 2.13 DN`B Parameters (Specification 3/4.2-5)

,2.13.1 Indicated Reactor Coolant System Tag shall be maintained < 593'5-EF 2.13.2 Indicated Pressurizer Pressure -shall bermaintained >_2-204 psia e 2.14 'ShutdownMargin Monitor Alarm Setpoint (Specification 3/4.3.5)**

2.14.1 The Shutdown Margin Monitor,(SMM) minimum countrate and Alarm Ratio Setting to meet.LIMITTING 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 1.750 1.0 1-22 5 0.6

  • 3.3.5.b.1 1.50 0.50 1.25 0.35 3.3.5.b.2 1.50 0.35

/ .12.5 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 rateis displayed on the SMM.

2.15 Refueling Boron Concentration (Specification 3/4.9.1.1) 2.15.1 The boron concentration of allfilledlportions 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

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

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 1 Reactor Core Safety Limit 680

-660

.640 UL

@k*

0 orf2 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 2.2,2008

TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 2 Required Shutdown Mafrgin for MODE 3 C)o c::o C-E 00 0

0 C3, 0/

.U) tr) U, _=

(Ni

('tv o/) Nie9tvI/w NmocanfHs 0 MILLSTONE - UNIT 3 TRM 8.1-11 ,LBDCR 08-MP3-029 October2-2, 2008

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 3 Required Shutdown Margin for MODE 4 C:1 C'4 j-ý 0

0 0 0 CD, U')

tf)

U C)ý Uo C) t C)ý t? to Co W) c) to to tO 3- 'T () CI), CI C~J~ C) C:)

(MjV %) NIOUiVLI~ NMAOOfLnHS MILL'STONE - UNIT 3 TRM 8.1-12 LBDCR 08-MP3-029 October 22, 2008

TECHNICAL REQUIREMENTSMANUAL APPENDIX 8.1 CORE OPERATING LIMITS-REPORT Figure 4 Required Shutdown Mairgin for MODE5 With RCS Loops Filled C:

C=)

C>,

Ca-0a-C 00 0

0y-.

0 0

( N...",,

C--

(D LL3 U'

0 un CD (AV ?/) NPDSýVUIA NMOtJLn.Hs 0 MILLSTONE - UNIT 3 TRM 8.1-13 LBDCR 08-MP3-029 October,22, 2008

TECHNICAL REQUIREMENTS MANUAL

'APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure'5 Required Shutdown Margin for MODE 5 with RCS .Loops"Not Filled C,4 C>

C>

0-CD c~ U) C: u) = f C:ý u) Cý LQ Cý u) C)ý u) C?

to Lo (I )

C13 CcJ ( - - C -CZ)

(M'V %)'NIOUVWj' NmoaiIOHs MILLSTONE - UNIT 3 TRM 8.1 14.. - LBDCR 08-MP3-029 October.22, 2008

TECHNICAL REOUIREMENTS MANUAL

,AP?ENDIX 8.1 CORE OPERATING LIMITS -REPORT Figure 6 Control Rod B3ank Insertion Limits versus Thermal Power

-240 220

-200 a14 0o LI-o 100 C.

z M 80 00 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

TECHNICAL.REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 7 Axial Flux Difference Limits as a Function of Rated Thermal Power 1 2__0 100 * ,0_* .I o.o 80 L

a, 0

0~

(K. ) a, 9-I-

41)

.4-.

PS 40

.2O 50 -40 -30 -20 -10 0 10 20 30 40 -50 60 Fliqx Difference, % D~elta-I MILLSTONE - UNIT 3 TRM 8.1-16 LBDCR 08-MP3-029 October,22, 2008

,TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT "2

'Figure 8 K(Z) - NormaliZed FQ(Z) as a Function of Core Height 12 1.1 Sno in.

0,i A3.7

'0,5

( S0.3 10.2 12)

.0 1D 6.0Ft 0.2 O.M5 I2D Ft I 0.1

.0_0 0 1 2 3 4 15 B6 7 8 9 10 11 1.2 Core Elevation, (feet)

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

ITECtNICAL REQUIREMENTS MANUAL APPENDIX 8.1

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

-12/+9 AFD-at 100%.RTP lBurnup *t tep (MWD/MTU)

Mesh N .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 11.3333 1.0000 1.0000 1.0000 1.0000 6 11.1667 .1.0000 1.0000 1.0000 10000 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 1.4181 113595 1.3403 12 -10.1667 1.3083 1.3432 132_54 1.3944

.13 110.0000 1.2833 1.3671 1.3266 1.3093 14 9.8333 1.2585 1.3390 1.3093 1.2920 15 9.6667 i.2320 1.3109 1.2901 1.2732 16 9.5000 1.2080 12830 1.2734 12530 17 9.3333 1.1972 1.2619 1.2629 1.2351

18 9.1667 1.1850 1.2505 1.2233 1.2472 19 9.0000 1.2387 1.21-81 1.1733 1.23.15

,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 1.2254 27 7.6667 1.1728 1.1719 1.1911 1.2246

-28 1.2224

ý7.5000 1.1715 1.1653 1.1886

29. 1.2189 7.3333 .1.1691 1.1577 1.1857 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 1.1554 1.1,297 1.1668 1.2067 33 6;6667 1.1490 1.1196 1.1582 1.2008 34 6.5000 1.1420 1.1141 .1.1484 1.1936

-35 6.3333 1.1350 1.1i16 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 1.1'524 40 5.5000 1.1205 1.1036 1.1105 1.1526 Distance from bottom of active core (feet):

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

TECHNICAL REQUIREMENTS MANUAL

-APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 1 (Continued)

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

-12/+9 AFD at 10Y0% RTP Burnup- Step (MWPIMTU)

Mesh No. Height* 150 5000 11000 18600 41 5.3333 1.1248 1.,1 052 1.1135 1.1'554 42 5.1667 1.1315 1.1105 1.11[80 1.1582 43 5.0000 1.1378 1.1219 1.1603 44 4.8333 1.1434 1.1190 1.1257 1.1617 45 4.6667 1.1488 .1.1-228 1.1298 1.1622 46 4.5000 1.1538 1.1-26.1 1.1336 1.1,621 47 4.3333 1.1'584 1.11293 1.1371 1.1614 48 4.1667 1.1626 1.1321 1.1402 1.1,600 49 4.0000 1.1665 1.1343 1.1432 1.1582 50 3.8333 1.1701 1.1-377 1.1455 1.1560 51 3.6667 1.1733 1.1426 1.1480 1.1'534 52 315000 1.1765 1.1472 1.1526 1.1506

'53 %3.3333 1.1811 1.1516 1.1574 1.1479

'54 3.1667 1.1882 1.1i569 1.1618 1.1460 55 3.0000 1.1970 1.1639 1.1675 .1.1490

'56 2.8333 1.2052 J1.1709 1.1734 1.1597 57 .2.6667 1.2136 1.1778 1.1799 1.1715

() 58 59

.2.5000

.2.3333 1.2278 1.2445 1,.1.906 J1.2044 1.1925 1.2047 1.1831 1.1946 60 2.1667 1.2601 1.2194 1.2169 1,2059 61 2.0000 1.2753 1.2356 1.2287 1.2169 62 1.8333 1.2901. 1.2511 1.2399 1.2275 63 1.6667 1.3039 1.2660 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 1.28015 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 0.50X) 1.0000 .1.0000 1.0000 1.0000 71 0.3333 1.0000 1.0000 1.6000 1.0o000 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 Aprl 13, 2010

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATINMG LI1ITS REPORT Table 2 Base Load W(Z),Function Millstone Unit 3 - CycleJ14 I Burnup Step (MWD/MTU)

Mesh No. Height* 150 5000 11000 18600 1 12.0000 1.0000 1.0600 1.0000 1.0000 11.8333 1.0000 1.0000 1.0000 1.0000 3 11.6667 1.0000 1.0000 1.0000 1.0000 4 1175000 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,.2185 1.1860 1.1518 8 10.8333 1.1811 1.2131 1.1837 1.1505 9 10.6667 1.1750 1.2081 1.1806 1.1465 10 10.5000 1.1686 1.2029 1.1763 1.1424 11 10.3333 1.1.6.16 1.1975 1.1728 1.1378 12 10.1667 1.1541 1.1963 1.1710 1.1360 13 10.0000 1.1461 1,1893 1.1703 1.1381 14 9.8333 1.1378 1.1793 1.1696 1.1383 15 -9.6667 1.1339 1.1704 1.1689 1.1375 16 9.5000 1.1305 1.1670 1.1680 1.1.372 17 9.3333 1.1248 1.1611 1.1635 1.1345 18 9.1667 1.1188 1.1537 1.1564 1.1310

@ 19 9.0000 1.11.65 1.1491 1.1506 1.1290 20 8.8333 1.1169 1.1465 1.1490 1.1-235 21 8.6667 1.1212 1.1442 1.1487 1.1300 22 8.5000 1.1258 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 1.1541 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 1.1252 1.1397 1.1732 31 7.0000 .1427 .A221 1.1383 1.1750 32 -6.8333 1.14'%4 11190 1.1359 1.1754 33 6.6667 1.1373 1.1163 1.1324 1.1747 34 6.5000 1.1340 1.1138 1.1279 1.1728 35 6.3333 1.1291 1.1117 1.1227 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

TECHNICAL REOUMWMENTS MANUAL

..APPE IX 8.1 CORE OPERATING LP.MTS REPORT Table 2 (Continued)

.Base Load W(Z) Function Millstone Unit.3 - Cycle 14 Burnup Step Mesh No. Height* 150 '15000 18600 LO00 41 5.3333 1.1185 1.3008 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 1.0957 1.0916 1.1374 45 4.6667 1.1106 1.0938 1.0896 1.1325 46 4.5000 1.1076 1.0925 1.0873 1.1270 47 4.3333 1.1043 1.0911 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 3.3333 1.0877 1.0880 1.0817 .1.0812

-54 3.1667 1.0887 1.0880 1.0826 1.0790 55 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 (k_-') 59 2.3333 1.1267 1.1435 1.1272 1.1180 60 2.1667 1.1389 1.1586 1.1383 1.1261 61 2.0000 1.1509 1.1736 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 1.1558 65 1.3333 1.1934 1.2264 1.1872 1.1618 66 1.1667 1.2020 112369 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 11.0000 1.0000 1.0000 1.0000 70 0.5000 1L0000 1.0000 1.0000 1.0000 71 0.3333 1.0000 1.co00 1.0000 1.0000 72 0.11567 L.c,0 1.0000 1.0000 1.0000 73 0.0000 1.0030 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 APPENJnIX 8.1

. COREOPERATING LIMITTS REPORT Table 3 Part.Power (74% RTP, 1'50 MWD/MTU) RAOC W(Z).Function

'Millstone Unit 3 - cycle 14 I

,Mesh No 1

Height (ft)* W(z) 12.0000 1.O00 2 1U1.8333 1.0000 3 11.6667 1.0000 4 11.5000 J.10000 5 11.3333 1.0000 6 11.1667 1.0000 7 11.0000 1.2696 8 10.8333 1.2504 9 10.6667 1.2353 10 10"5000 12.202 11 10.3333 1.2019 12 10.1667 1.1820 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 K ..) 19 9.0000 1.0908 20 8.8333 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

ý27 7.6667 1.1142 28 7.5000 1.1149

.29 7.3333 1.1156 30 7.1667 1.1168

  • 3I 7.0000 1.1173 32 6.8333 1.1168 33 6.6667 1.1 155 34 6.5000 *11133 35 6.3333 1,11111 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 LMIITS REPORT TableW3 (Continued)

Part Power (74% RTP, 150 MWD/MTU).RAOCW(Z)TFunction Millstone Unit 3 - Cycle 14 I Mesh No Height (ft)* W(z) 41 5.3333 1.1.216 42 5.1667 1.1321 43 ,5.0000 1.1418 44 4.8333 1.1508 45 4.6667 1.1r597 46 4.5000 1.1681 47 4.3333 .1.1759 48 4.1667 1.1835 49 4.0000 1.1922 50 3.8333 1,2009 51 3.6667 1.2093 52 3'5000 1L2169 53 3.33 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

0) 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 1.46925 68 0.8333 1.0000 69 0.66671 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) i/"0 MILLSTONE - UNIT 3 TRM 8.1-23 LBDCR .10-MP3-009 April 13, 2010

.TECHNICAL REQUIREMENTS&MANUAL

..APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 4

,Burnup Penalty for Incore*

Bumup 'Ponalty 4659 1.020 4820 1.022 4981 1.022 5142 1.022 5303 1.022

.5465 1:022 "5626 1.021

  • '787 .1.021

'5948 1.020 Note: A penalty of 1.02 shall be used outside of the bumup;range sho~wn in Table 4.

(

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

'~V.

TECHNICAL.REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 3.0 Analytical Methods The analytical methods used to determine the core operating limits shall be those p7r-eviously

reviewed and approved by the'NRC, specifically those described in the 6followixig documents.

.3.1 WCAP--9272-P-A, "WESTINGHOUSE RELOADISA-FETYý-EVALUATION METHODOLOGY,".July 1985 (WProprietary).

3.2 'WCAP-10216-P-A-RIA, "RELAXATION OF CONSTANfT-AXIAL OFFSET

,CONTROL FQ SURVEILLANCE TECHNICAL SSPECiFICATIONt*"'Rev. 1, February 1994 &WProprietary).

3.3 WCAP-12945-P-A, Yolume l(Revision,2) and Volumes.2 through 5 (Revision 1), "Code

-Qualification Document for Best -Estimate LOCA Analysis,"lMarch 1998 (W Proprietary).

3.4 WCAP-16009-P-A, "Realistic Large-Break LOCAEvaluation Methodolggy Using the Automated Statistical Treatment of Uncertainty'Method (ASTRUM)," January-,2005

(&W Proprietary). 5 WCAP-11 946, "SafetyfEvaluation Supporting a MoreN-egative EOL Moderator Temperature Coefficient Technical Specification for the.Millstone Nuclear Power Station Unit 3," September 19'88 (W Proprietary).

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

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

3.8 WCAP-12610-P-A, "VANTAGE+ Fuel Assembly'Report," April 1.995 (W Proprietary).

3.9 WCAP-8301, "LOCTA-IV Program: Loss-of-Coolant Transient Analysis," June 1974

(&W Proprietary).

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

3.1.1 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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