ML071350362

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Millstone Power Station Unit 3, Core Operating Limits Report, Cycle 12
ML071350362
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/02/2007
From: Price J A
Dominion Nuclear Connecticut
To:
Document Control Desk, NRC/NRR/ADRO
References
07-0337 LBDCR 07-MP3-015
Download: ML071350362 (26)
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Dominion Dominion Nuclear Connecticut, Inc.Millstone Power Station Rope Ferry Road Waterford, CT 06385 MAY 0 2 2007 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC 20555 Serial No.NSS&L/DF Docket No.License No.07-0337 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 CORE OPERATING LIMITS REPORT. CYCLE 12 In accordance with the Millstone Power Station Unit 3 Technical Specifications, Section 6.9.1.6.d, Dominion Nuclear Connecticut, Inc., hereby submits, as Enclosure 1, the Cycle 12 Core Operating Limits Report (COLR).The Millstone Power Station Unit 3 COLR has been revised to incorporate several changes, including those specific to Cycle 12 operation.

Changes include the following:

  • Revisions to overtemperature AT parameters, overpower AT parameters, and reactor core safety limits* Changes due to incorporation of License Amendment 236 for relocation of cycle specific parameters to the COLR* Editorial changes and clarifications of analytical methods references The COLR has been incorporated into the Millstone Power Station Unit 3 Technical Requirements Manual.If you have any questions or require additional information, please contact Mr. David W.Dodson at (860) 447-1791, extension 2346.Very truly yours, J. laPrice Sit , ce President

-Millstone

Enclosures:

(1)Commitments made in this letter: None.1r262(

Serial No. 07-0337 Docket No. 50-423 Core Operating Limits Report, Cycle 12 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. J. D. Hughey Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8 B 3 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station Serial No. 07-0337 Docket No. 50-423 ENCLOSURE I CORE OPERATING LIMITS REPORT. CYCLE 12 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT MILLSTONE UNIT 3 CYCLE 12 CORE OPERATING LIMITS REPORT MILLSTONE

-UNIT 3 TRM 8.1-1 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIM ITS REPORT Table of Contents Section Title Page 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 Settings (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. t-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) 8.1-6 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 2.10 Heat Flux Hot Channel Factor -FQ(Z) (Specification 3/4.2.2.1) 8.1-7 2.11 Heat Flux 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 -F NAH (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 Concentration (Specification 3/4.9.1.1) 8.1-9 3.0 Analytical Methods 8.1-22 MILLSTONE

-UNIT 3 TRM 8.1-2 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT List of Figures Figure Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 Figure 7 Figure 8 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 8.1-12 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 12-12/+9 AFD at 100% RTP Table 2 Base Load W(Z) Function, Millstone Unit 3 -Cycle 12 Page 8.1-18 8.1-20 1 MILLSTONE

-UNIT 3 TRM 8.1-3 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Millstone Unit 3 Cycle 12 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) for Millstone Unit 3 Cycle 12 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 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 07-MP3-015 April 16, 2007 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 K 1<_ 1.27 2.2.1.2 K 2 > 0.0245 / OF 2.2.1.3 K3 00.00108 / psi 2.2.1.4 u 1 0 seconds 2.2.1.5 t 2 < 4 seconds 2.2.1.6 r 4 > 20 seconds 2.2.1.7 '[5 4 seconds 2.2.1.8 T' is loop specific indicated Tavg at RATED THERMAL POWER,< 587.1OF 2.2.1.9 P' is nominal pressurizer pressure, > 2250 psia 2.2.1.10 fl(AJ) 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 -35% and +3%, fl(Al) _> 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 -35%, the AT Trip Setpoint shall be automatically reduced by _> 1.83% of its value at RATED THERMAL POWER.(3) For each percent that the magnitude of qt -qb exceeds +3%, the AT Trip Setpoint shall be automatically reduced by _> 2.05% of its value at RATED THERMAL POWER.2.2.2 Overpower AT 2.2.2.1 K4_ 1.13 2.2.2.2 K5 _ 0.02/ OF for increasing Tavg and K 5 <_ 0 for decreasing Tavg 2.2.2.3 K 6 > 0.0016/ OF when T > T" and K 6 < 0/ OF when T T" 2.2.2.4 l > 0 seconds MILLSTONE

-UNIT 3 TRM 8.1-5 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 2.2.2.5 Tr 2 < 4 seconds 2.2.2.6 r 7 > 10 seconds 2.2.2.7 T" is loop specific indicated Tavg at RATED THERMAL POWER,< 587.1OF 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% Ak/k.2.4 Shutdown Margin -MODE 3, 4 and 5 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 -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.

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 10-4 Ak/k/°F. Above 70% RTP, the MTC limit is a linear ramp to 0 Ak/k/°F at 100% RTP.2.6.2 The EOL/ARO/RTP MTC shall be less negative than -5.65 x 10-4 Ak/k!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 least 220 steps withdrawn (inclusive).

MILLSTONE

-UNIT 3 TRM 8.1-6 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 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)

F RTP FQ(Z)_ Q x K(Z)P FRTP FQ(Z)< Q x K(Z)0.5 for P > 0.5 for P < 0.5 where: p THERMAL POWER RATED THERMAL POWER 2.10.1 F RTPQ 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)

FRTP x K(Z)FQ(Z) Q P x W(Z)FRTP x K(Z)FQ(Z) ! Q 0.5 x W(Z)MILLSTONE

-UNIT 3 for P > 0.5 forP <0.5 TRM 8.1-7 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT where: p THERMAL POWER RATED THERMAL POWER 2.11.1 FRTPQ = 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 12 bumup dependent RAOC W(Z) values are valid over the range of bLirnup from 0 to 20,500 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 12 burnup dependent BL W(Z) values are valid over the range of bumup from 0 to 20,500 MWD/MTU.*2.11.5 A 2% factor shall be used for surveillance requirements 4.2.2.1.2 and 4.2.2.1.4.*

2.12 RCS Total Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor -F NAl (Specification 3/4.2.3.1) 2.12.1 The RCS Total Flow Rate shall be greater than or equal to 371,920 gpm.2.12.2 FNAH _< FRTP AH x (1 + PFAIH x [1 -P])where: p THERMAL POWER RATED THERMAL POWER 2.12.2.1 FRTPA-I1 1.58 for Robust Fuel Assemblies (RFA) and (RFA-2)F RTP = 1.51 *for NGF Lead Test Assemblies 2.12.2.2 PFAH = 0.3 for P < 1.0.Sections 2.11.3 through 2.11.5 are prepared by Dominion.MILLSTONE

-UNIT 3 TRM 8.1-8 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS 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

< 591.1 'F.2.13.2 Indicated Pressurizer Pressure shall be maintained

_ 2218 psia 2.14 Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3.5)**

2.14.1 The Shutdown Margin Monitor (SMM) minimumn count rate and Alarm Ratio Setting to mneet 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 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 kerff 0.95 (all rods in less the most reactive two rods) and subcriticality (keff:< 1.0 with all rods out) during the Cycle 11/12 refueling outage.MILLSTONE

-UNIT 3 TRM 8.1-9 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 1 Reactor Core Safety Limit 680 660 640 U-b uJ C/)620 600 580 560 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 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 2 Required Shutdown Margin for MODE 3 (Z)0 0 W-0 CD)C/3 Lf)"?) C::! U?LO'c1 (Mv %) N1101VI/'

NmocLuflH-S MILLSTONE

-UNIT 3 TRM 8.1-11 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 3 Required Shutdown Margin for MODE 4 LO C=)E CL z 0 z tU 0 z z 0 0 ca-j 0n 10: 10 Cý 10 10 C) 10 'C) 10 C)ý 1 C)(MiV %) NINVLI~Il Nmoo-LnfHs MILLSTONE

-UNIT 3 TRM 8.1-12 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 4 Required Shutdown Margin for MODE 5 with RCS Loops Filled c::>CD]0 0 C-)0 0 CD, C-)CD U-3 Cý toý U? C= to C: toý c Cc' t co to to cn t cy') (N N ~CD (OW %) NICAIVIA NMAC)3LLOHS MILLSTONE

-UNIT 3 TRM 8.1-13 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUI1REMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 5 Required Shutdown Margin for MODE 5 with RCS Loops Not Filled CD I I 1c[0~0 0 CD)CD)Q-C,, C)ý 10 C)ý 10ý c)ý I C:) 10ý =) 1 C) 10 C) IfQ C (D C 0 co O LO 'r) Id- co c C14 --CD CD (MV %) NI!9VINJ NM0a-LnfHS MILLSTONE

-UNIT 3 TRM 8.1-14 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 6 Control Rod Bank Insertion Limits versus Thermal Power 2410 220 1 0 160 140 0.120 E o 100 60 40 0 0 10 20 30 40 50 60 70 80 90 100 RATED THERMAL POWER (%)MILLSTONE

-UNIT 3 TRM 8.1-15 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 7 Axial Flux Difference Limits as a Function of Rated Thermal Power 1 20 100E 0 0 1~.0 0~E I-'a-, 80 40-60 40 20 -10 0 10 20 30 40 50 60 Flux Difference, % oDelta-I MILLSTONE

-UNIT 3 TRM 8.1-16 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Figure 8 K(Z) -Normalized FQ(Z) as a Function of Core Height ID 0~1 .2 1.0 0[.9 0.8 0.7 06 0.5 6.4 i----i--" -....K~I- EleAon t.0 0.0 Ft 1.0 6.0 Ft i.~1 12.0 Ft 0.2 0.1 06.+ 4 4 + 4- 4 4- 4 0 1 2 3 4 5 6 7 8 9 0 1 1 12 Core Elevation, (feet)MILLSTONE

-UNIT 3 TRM 8.1-17 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 1 RAOC W(Z) Function, Millstone Unit 3 -Cycle 12-12/+9 AFD at 100% RTP Mesh No. Axial* Height 1 2 3 4 5 6 7 8 9 t0 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 12.0000 11.8333 11.6667 11.5000 11.3333 11.1667 11.0000 10.8333 10.6667 10.5000 10.3333 10.1667 10.0000 9.8333 9.6667 9.5000 9.3333 9.1667 9.0000 8.8333 8.6667 8.5000 8.3333 8.1667 8.0000 7.8333 7.6667.7.5000 7.3333 7.1667 7.0000 6.8333 6.6667 6.5000 6.3333 6.1667 6.0000 5.8333 5.6667 Burnup 150 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2770 1.2625 1.2482 1.2350 1.2236 1.2144 1.2070 1.1978 1.1859 1.1734 1.1650 1.1603 1.1553 1.1490 1.1429 1.1387 1.1341 1.1294 1.1265 1.1235 1.1189 1.1131 1.1094 1.1083 1.1075 1.1069 1.1067 1.1061 1.1060 1.1064 Burnup 3000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3179 1.3027 1.2911 1.2781 1.2649 1.2514 1.2368 1.2234 1.2102 1.1956 1.1864 1.1824 1.1787 1.1742 1.1696 1.1659 1.1617 1.1562 1.1500 1.1429 1.1351 1.1269 1.1169 1.1079 1.1053 1.1044 1.1028 1.1022 1.1016 1.1010 Burnup 10000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3471 1.3297 1.3138 1.2972 1.2840 1.2743 1.2656 1.2543 1.2404 1.2266 1.2175 1.2131 1.2094 1.2042 1.1986 1.1948 1.1904 1.1855 1.1823 1.1783 1.1726 1.1657 1.1578 1.1488 1.1389 1.1281 1.1166 1.1058 1.1025 1.1031 Bumup 17000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3340 1.3169 1.2989 1.2802 1.2594 1.2402 1.2279 1.2186 1.2113 1.2064 1.1976 1.1893 1.1896 1.1921 1.1939 1.1976 1.2005 1.2013 1.2008 1.1991 1.1960 1.1917 1.1862 1.1796 1.1717 1.1635 1.1547 1.1452 1.1396 1.1366* Distance from bottom of active core (feet)MILLSTONE

-UNIT 3 TRM 8.1-18 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 1 (Continued)

RAOC W(Z) Function, Millstone Unit 3 -Cycle 12-12/+9 AFD at 100% RTP Mesh No.40 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 Axial* Height 5.5000 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 Burnup 150 MWD/MTU 1.1094 1.1140 1.1190 1. 1236 1.1278 1. 1316 1.1351 1.1383 1.1411 1. 1433 1. 1466 1.1521 1.1587 1.1651 1.1713 1.1797 1.1909 1.2046 1.2192 1.2339 1.2485 1.2627 1.2764 1.2894 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Burnup 3000 MWD/MTU 1.1025 1.1049 1.1073 1.1107 1.1141 1.1171 1.1197 1.1221 1.1241 1.1258 1.1278 1.1303 1.1326 1.1350 1.1376 1.1408 1.1489 1.1635 1.1795 1.1956 1.2118 1.2278 1.2432 1.2579 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Burnup 10000 MWD/MTU 1.1054 1.1083 1.1121 1.1154 1.1181 1.1206 1.1228 1.1247 1.1262 1.1276 1.1287 1.1296 1.1305 1.1324 1.1361 1.1423 1.1519 1.1646 1.1771 1.1894 1.2016 1.2136 1.2250 1.2357 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Bumup 17000 MWD/MTU 1.1384 1.1406 1.1414 1.1423 1.1431 1.1435 1.1433 1.1425 1.1412 1.1391 1.1383 1.1385 1.1405 1.1426 1.1442 1.1455 1.1472 1.1510 1.1595 1.1700 1.1797 1.1895 1.1992 1.2085 1.0000 1.0000 1.0000 1.0000 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 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 2 Base Load W(Z) Function Millstone Unit 3 -Cycle 12 Mesh No.1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 Axial* Height 12.0000 11.8333 11.6667 11.5000 11.3333 11.1667 11.0000 10.8333 10.6667 10.5000 10.3333 10.1667 10.0000 9.8333 9.6667 9.5000 9.3333 9.1667 9.0000 8.8333 8.6667 8.5000 8.3333 8.1667 8.0000 7.8333 7.6667 7.5000 7.3333 7.1667 7.0000 6.8333 6.6667 6.5000 6.3333 6.1667 6.0000 5.8333 5.6667 Burnup 150 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1862 1.1847 1.1838 1.1772 1.1679 1.1590 1. 1514 1.1420 1.1319 1. 1246 1.1193 1.1168 1.1179 1.1197 1. 1203 1.1205 1.1200 1.1189 1.1172 1.1148 1. 1121 1.1104 1.1093 1.1083 1.1074 1. 1070 1.1067 1.1061 1.1058 1.1065 Burnup 700 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2047 1.2012 1.1983 1.1906 1.1807 1.1711 1.1624 1.1523 1.1416 1.1331 1.1276 1.1254 1. 1259 1.1269 1.1274 1.1271 1.1263 1.1249 1.1229 1. 1201 1.1172 1.1152 1.1138 1.1126 1.1116 1.1109 1.1104 1.1100 1.1096 1.1099 Burnup 3000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2418 1.2326 1.2230 1.2124 1.2012 1.1895 1.1775 1.1655 1.1533 1.1413 1.1353 1.1341 1.1326 1.1316 1.1312 1.1301 1.1283 1.1260 1.1231 1.1195 1.1157 1.1125 1.1100 1.1078 1.1059 1.1041 1.1028 1.1022 1.1015 1.1007 Burnup 10000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2455 1.2383 1.2310 1.2243 1.2155 1.2055 1.1966 1.1859 1.1744 1.1661 1.1617 1.1605 1.1602 1.1592 1.1583 1.1598 1.1607 1.1598 1.1580 1.1551 1.1512 1.1464 1.1407 1.1341 1.1265 1.1192 1.1122 1.1047 1.1025 1.1032 Bumup 17000 MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.1953 1.1908 1.1876 1.1855 1.1817 1.1769 1.1730 1.1677 1.1640 1.1655 1.1664 1.1665 1.1704 1.1734 1.1748 1.1775 1.1794 1.1805 1.1829 1.1843 1.1838 1.1820 1.1789 1.1746 1.1690 1.1625 1.1547 1.1453 1.1385 1.1359 I* Distance from bottom of active core (feet)MILLSTONE

-UNIT 3 TRM 8.1-20 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT Table 2 (Continued)

Base Load W(Z) Function Millstone Unit 3 -Cycle 12 Mesh No.40 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 Axial* Height 5.5000 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 Burnup 150 MWD/MTU 1.1079 1.1101 1.1125 1.1145 1.1161 1.1173 1.1182 1.1191 1. 1204 1.1223 1.1246 1. 1274 1.1306 1.1339 1. 1367 1.1384 1. 1429 1.1530 1.1674 1.1832 1.1984 1.2134 1.2280 1.2418 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Burnup 700 MWD/MTU 1.1110 1.1126 1.1143 1.1156 1.1164 1.1170 1.1172 1.1174 1.1181 1.1195 1.1216 1.1241 1.1269 1.1296 1.1320 1.1344 1.1391 1.1481 1.1617 1.1771 1.1922 1.2070 1.2214 1.2351 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Burnup 3000 Burnup 10000 Burnup 17000 MWD/MTU 1.1007 1.1005 1.0998 1.0987 1.0973 1.0956 1.0938 1.0919 1.0906 1.0905 1.0916 1.0934 1.0950 1.0957 1.0967 1.1012 1.1066 1.1123 1.1226 1.1360 1.1501 1.1641 1.1777 1.1905 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 MWD/MTU 1.1035 1.1029 1.1022 1.1011 1.0995 1.0977 1.0967 1.0955 1.0942 1.0945 1.0955 1.0979 1.1001 1.1017 1.1034 1.1064 1.1128 1.1224 1.1320 1.1411 1.1506 1.1622 1.1743 1.1854 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 MWD/MTU 1.1354 1.1346 1.1329 1.1314 1.1297 1.1275 1.1247 1.1214 1.1177 1.1136 1.1094 1.1056 1.1029 1.1000 1.0972 1.0975 1.0995 1.1057 1.1134 1.1215 1.1297 1.1381 1.1464 1.1544 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000* Distance from bottom of active core (feet)MILLSTONE

-UNIT 3 TRM 8.1-21 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS 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 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 (W Proprietary).

3.2 WCAP-10216-P-A-R1A, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION," Rev. 1, February 1994 (W Proprietary).

3.3 WCAP-9561-P-A, "BART-AI : A Computer Code for the Best Estimate Analysis of Reflood Transients," March 1984 (W Proprietary).

3.4 WCAP-9561-NP-A, Addendum 1, "Addendum to Bart-Al: A Computer Code for the Best Estimate Analysis of Reflood Transients," April 1985.3.5 WCAP-956 1-NP-A, Addendum 2, "Addendum to Bart-A1: A Computer Code for the Best Estimate Analysis of Reflood Transients," July 1985.3.6 WCAP-9561-P-A, Addendum 3, Revision 1, "Addendum to Bart-Al: A Computer Code for the Best Estimate Analysis of Reflood Transients (Special Report: Thimble Modeling in Westinghouse ECCS Evaluation Model)," July 1986 (W Proprietary).

3.7 WCAP-10266-P-A, Addendum 1, Revision 2-P-A, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code, Addendum 1: Power Shape Sensitivity Studies," December 1987 (W Proprietary).

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

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

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

3.11 WCAP- 12610-P-A, "VANTAGE+

Fuel Assembly Report," April 1995 (W Proprietary).

3.12 WCAP-8301, "LOCTA-IV Program: Loss-of-Coolant Transient Analysis," June 1974 (W Proprietary).

MILLSTONE

-UNIT 3 TRM 8.1-22 LBDCR 07-MP3-015 April 16, 2007 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT 3.0 Analytical Methods (Continued) 3.13 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 (W Proprietary).

3.14 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 8.1-23 LBDCR 07-MP3-015 April 16, 2007

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