ML041460457

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Core Operating Limits Report, Cycle 10
ML041460457
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/11/2004
From: Price J
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
04-291
Download: ML041460457 (24)
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Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station L-.' Dominion-Rope Ferry Road Wlatcrford, CT 06385 a II W U.S. Nuclear Regulatory Commission Serial No.04-291 Attention: Document Control Desk MPS Lic/MAE RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT. INC.

MILLSTONE POWER STATION UNIT 3 CORE OPERATING LIMITS REPORT, CYCLE 10 In accordance with the Millstone Unit 3 Technical Specifications, Section 6.9.1.6.d, Dominion Nuclear Connecticut, Inc., hereby submits, as Enclosure 1, the Cycle 10 Core Operating Limits Report (COLR).

The Millstone Unit 3 COLR has been revised to incorporate changes for Cycle 10 operation. The changes included revisions for Cycle 10 parameter changes, deletion of all reference to Four Loop Operation in accordance with Amendment 217, and addition of items removed from the Technical Specifications in accordance with Amendment 218.

The COLR has been incorporated into the Millstone 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.

Si President - Millstone

-Nod

Serial No.04-291 Core Operating Limits Report, Cycle 10 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 Mr. V. Nerses Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station

Serial No.04-291 Docket No. 50-423 Enclosure 1 Core Operating Limits Report, Cycle 10 Millstone Power Station Unit 3 Dominion Nuclear Connecticut, Inc. (DNC)

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 MILLSTONE UNIT 3 CYCLE 10 CORE OPERATING LIMITS REPORT Millstone - Unit 3 TRM 8.1-1 LBDCR 04-MP3-004 March 25, 2004

TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 Table of Contents Section Title Page 1.0 Core Operating Limits Report 4 2.0 Operating Limits 4 2.1 Limiting Safety System Settings (Specification 2.2.1) 4 2.2 Shutdown Margin- MODE 1 and 2 (Specification 3/4.1.1.1.1) 5 2.3 Shutdown Margin- MODE 3, 4 and 5 Loops Filled (Specification 3/4.1.1.1.2) 5 2.4 Shutdown Margin- MODE 5 Loops Not Filled (Specification 3/4.1.1.2) 6 2.5 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 6

.2.6 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) 6

  • 2.7 Control Rod Insertion Limits (Specification 3/4.1.3.6) 6 2.8 Axial Flux Difference (Specification 3/4.2.1.1) 6 2.9 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3/4.2.2.1) 6 2.10 Heat Flux Hot Channel Factor Surveillance - FQ(Z) (Specification 3/4.2.2.1.2) 7 2.11 Nuclear Enthalpy Rise Hot Channel Factor - FNAH (Specification 3/4.2.3.1) 8 2.12 DNB Parameters (Specification 3/4.2.5) 8 2.13 Shutdown Margin Monitor Alarm Setpoint (Specification 3/4.3.5) 8 2.14 Refueling Boron Concentration (Specification 3/4.9.1.1) 9 3.0 Analytical Methods 21 Millstone - Unit 3 TRNM 8.1-2 LBDCR 04-MP3-004 March 25, 2004

TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 List of Figures Figure Title Page Figure 1 Required Shutdown Margin for MODE 3 10 Figure 2 Required Shutdown Margin for MODE 4 11 Figure 3 Required Shutdown Margin for MODE 5 with RCS Loops Filled 12 Figure 4 Required Shutdown Margin for MODE 5 with RCS Loops Not Filled 13 Figure S Control Rod Bank Insertion Limits versus Thermal Power 14 Figure 6 Axial Flux Difference Limits as a Function of Rated Thermal Power 15 Figure 7 K(Z) - Normalized FQ(Z) as a Function of Core Height 16 List of Tables Table Title Page Table 1 RAOC W(Z) Function, Millstone Unit 3 - Cycle IO- 17 Table 2 Base Load W(Z) Function, Millstone Unit 3 - Cycle 10 19 Millstone -Unit 3 TRM8.1-3 LBDCR 04-MP3-004 March 25,2004

TECHNICAL REbUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. C!YCLE 10 Millstone Unit 3 Cycle 10 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) for Millstone Unit 3 Cycle 10 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.

2.2.1 Limiting Safety System Settings 3/4.1.1.1.1 Shutdown Margin - MODE I 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 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 LImiting Safety System Settings (Specification 2.2.1) 2.1.1 Overtemperature AT 2.1.1.1 K1 < 1.20 2.1.1.2 K2 >0.02456/ 0 F 2.1.1.3 K3 >0.001311 /psi 2.1.1.4 T, > 8 seconds Millstone- Unit 3 TRM 8.1-4 LBDCR 04-MP3-004 March 25, 2004

TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 2.1.1.5 T2 < 3 seconds 2.1.1.6 T4 > 20 seconds 2.1.1.7 T5 < 4 seconds 2.1.1.8 T` is loop specific indicated Tavg at RATED THERMAL POWER, <587.1 OF 2.1.1.9 *P' is nominal pressurizer pressure, > 2250 psia 2.1.1.10 f1(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 -26% and +3%, fi(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 -26%, the AT Trip Setpoint shall be automatically reduced by > 3.55% 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 > 1.98% of its value at RATED THERMAL POWER.

2.1.2 Overpower AT 2.1.2.1 K4 5 1.09 2.1.2.2 K5 > 0.02/ IF for increasing Tavg and Ks < 0 for decreasing Tavg 2.1.2.3 K6 > 0.00 180/ 0F when T > T" and K6 <0/ 0F when T< T" 2.1.2.4 Tr > 8 seconds 2.1.2.5 x2 < 3 seconds 2.1.2.6 T7 > 10 seconds 2.1.2.7 T" is loop specific indicated Tavg at RATED THERMAL POWER,<587.1 0F 2.2 Shutdown Margin- MODE 1 and 2 (Specification 3/4.1.1.1.1) 2.2.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% Ak/k.

2.3 Shutdown Margin- MODE 3,4 and 5 Loops Filled (Specification 3/4.1.1.1.2) 2.3.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 1, 2 and 3.

Millstone - Unit 3 TRM 8.1-5 LBDCR 04-MP3-004 March 25, 2004

TECHNICAL REOUIREMENTS MANUAL

-APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 2.4 Shutdown Margin- MODE 5 Loops Not Filled (Specification 3/4.1.1.2) 2.4.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figure 4 or the limits shown in Figure 3 with the chemical and volume control system (CVCS) aligned to preclude reactor coolant system boron concentration reduction.

2.5 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 2.5.1 The BOL/ARO/0% - 70% RTP MTC shall be less positive than + 0.5 x 104 Ak/kIF.

Above 70% RTP, the MTC limit is a linear ramp to 0 Ak//kPF at 100% RTP.

2.5.2 The EOL/ARO/RTP MTC shall be less negative than - 5.65 x 104 Ak/ktF.

2.5.3 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.

2.6 Shutdown Rod Insertion Limit (Specification 3/4.13.5) 2.6.1 The shutdown rods shall be at least 220 steps withdrawn (inclusive).

2.7 Control Rod Insertion limits (Specification 3/4.1.3.6) 2.7.1 The control rod banks shall be limited in physical insertion as shown in Figure 5, and 2.7.2 Control bank A shall be at least 220 steps withdrawn.

2.8 Axial Flux Difference (Specification 3/4.2.1.1) 2.8.1 The Axial Flux Difference (AFD) limits are provided in Figure 6.

2.8.2 The AFD target band during base load operation is i 5%.

2.8.3 The minimum allowable (nuclear design) power level for base load operation (APLND) is 80% of Rated Thermal Power.

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

Millstone - Unit 3 TRM 8.1-6 LBDCR 04-MP3-004 March 25, 2004

TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 10 FQ(Z) S Qp x K(Z) for P > 0.5 P

FQ(Z) *-Qx K(Z) for P S 0.5

0.5 where

P = THERMALPOWER RATED THERAL POWER 2.9.1 FR1TQ = 2.60.

2.9.2 K(Z) is provided in Figure 7.

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

F (Z) ; FQ X K(Z) for P> 0.5 Q( PXW(Z)

FQ ". xK(Z)

FQ(Z)*< 0.5xW(Z) forPS 0.5 where: P = THERMAL POWER RATED THERAAL POWER 2.10.1 FRrPQ = 2.60.

2.10.2 K(Z) is provided in Figure 7.

Millstone -Unit 3 TRM 8.1-7 LBDCR 04-MP3-004 March 25, 2004

TECHNICAL RiEOQUREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 2.10.3 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 10 burnup dependent RAOC W(Z) values are valid over the range of burnup from 0 to 21,300 MWDIMTU.'

2.10.4 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 10 burnup dependent BL W(Z) values are valid over the range of burnup from 0 to 21,300 MWD/MTU.

2.10.5 A 2% factor shall be used for surveillance requirements 4.2.2.1.2 and 4.2.2.1.4.

2.11 Nuclear Enthalpy Rise Hot Channel Factor - FNAH (Specification 3/4.2.3.1)

FNAH < F7H X (I + PFAH X [1 - P])

Thermal Power where: P =

Rated Thermal Power 2.11.1 FRTP~AR = 1.58 for Robust Fuel Assembly (RFA) and (RFA-2)

Fai,&H =1.51 for NGF Lead Test Assemblies 2.11.2 PFAH = 0.3 for P < 1.0.

2.12 DNB Parameters (Specification 3/4.2.5) 2.12.1 Indicated Reactor Coolant System Ta.g shall be maintained < 591.1 IF.

2.12.2 Indicated Pressurizer Pressure shall be maintained > 2218 psia 2 .

2.13 Shutdown Margin Monitor Alarm Setpolnt (Specification 3/4.3.5)3 l Sections 2.10.3 through 2.10.5 are prepared by Dominion.

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

3 Section 2.13 was prepared by Dominion based on boron dilution analyses performed by Westinghouse.

Millstone - Unit 3 TRM 8.1-8 LBDCR 04-MP3-004 March 25, 2004

TECBNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 2.13.1 The Shutdown Margin Monitor (SMM) minimum count rate and Alarm Ratio Setting to meet LIMITING CONDITION FOR OPERATION (LCO) 3.3.5 shall be as shown below.

Tech. Spec. LCO SMM Alarm Ratio Setting Min. Count Rate (counts/sec) 3.3.5.a 1.50 1.0 1.25 0.6 3.3.5.b.1 1.50 0.50 1.25 0.35 3.3.5.b.2 1.50 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.

2.14 Refueling Boron Concentration (Specification 314.9.1.1) 2.14.1 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. 4 4 This boron concentration bounds the condition of keff< 0.95 (all rods in less the most reactive two rods) and subcriticality (kefr< 1.0 with all rods out) during the Cycle 9/10 refueling outage.

Millstone - Unit 3 TRM 8.1-9 LBDCR 04-MP3-004 March 25, 2004

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TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 Figure 5 Control Rod Bank Insertion LImits versus Thermal Power 240 l- g 240 220 -

23.7%,2201 74.1%.2201 conto Bank B_

200 -

180- - -

z 0.% o1661 E!i/

Z 160 - - - = - -

i10 -/ [Control Bank C t140 - I I -

10 100 -___

80 /

IControl Bank D ORI 60 40 20 0

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

Millstone - Unit 3 TRM 8.1-14 LBDCR 04-MP3-004 March 25, 2004

TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 Figure 6 Axial Flux Difference Limits as a Function of Rated Thermal Power 120-100 _- X UNACCEPTABLE UNACCEPTABLE

~0 OPERATION - -OPERATION 60 60 -

--- L ACCEPTABLE

_OPERATtON ]

-30.50

,~40 20 O - _i . _i-l--1l--fi

-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 Flux Difference, % Delta-l Millstone - Unit 3 TRM 8.1-15 LBDCR 04-MP3-004

  • March 25, 2004

TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 Figure 7 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1.1 1--- 1 - -I-1.0 0.9

,N 0.8 O 0.7 IT 0,

a-

~0.5 f 0.4 z

0.3 1.0 0.0Pt1

- - T 1.0 6.0I T I -

0.2 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 Core _evton, (feet)

Millstone - Unit 3 TRM 8.1-16 LBDCR 04-MP3-004 March 25,2004

TECHNICAL REOUIREMENTS MANUAL APPENDIX 8,1 CORE OPERATING LIMITS REPORT. CYCLE 10 Table 1 RAOC W(Z) Function, Millstone Unit 3 - Cycle 10

-12/+9 AFD at 100% RTP Burnup Burnup Burnup Burnup Mesh Axial* 150 3000 10000 18000 No. Height MWD/MTU MWDIMTU MWDIMTU MWDIMTU 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 1.0000 1.0000 1.0000 1.0000 8 10.8333 1.0000 1.0000 1.0000 1.0000 9 10.6667 1.0000 1.0000 1.0000 1.0000 10 10.5000 1.3432 1.3583 1.3407 1.3248 I1 10.3333 1.3248 1.3506 1.3258 1.3152 12 10.1667 1.3079 1.3470 1.3057 1.3040 13 10.0000 1.2960 1.3400 1.2835 1.2916 14 9.8333 1.2852 1.3277 1.2659 1.2775 15 9.6667 1.2753 1.3124 1.2509 1.2625 16 9.5000 1.2673 1.2971 1.2344 1.2488 17 9.3333 1.2554 1.2792 1.2254 1.2394 18 9.1667 1.2395 1.2599 1.2243 1.2328 19 9.0000 1.2240 1.2430 1.2240 1.2252 20 8.8333 1.2120 1.2301 1.2223 1.2177 21 8.6667 1.2027 1.2210 1.2200 1.2141 22 8.5000 1.1935 1.2141 1.2187 1.2165 23 8.3333 1.1839 1.2064 1.2156 1.2192 24 8.1667 1.1765 1.1991 1.2111 1.2212 25 8.0000 1.1744 1.1954 1.2082 1.2259 26 7.8333 1.1725 1.1913 1.2043 1.2299 27 7.6667 1.1686 1.1854 1.1997 1.2313 28 7.5000 1.1639 1.1785 1.1968 1.2311 29 7.3333 1.1585 1.1706 1.1930 1.2296 30 7.1667 1.1522 1.1619 1.1872 1.2265 31 7.0000 1.1449 1.1525 1.1 802 1.2220 32 6.8333 1.1382 1.1415 1.1720 1.2160 33 6.6667 1.1320 1.1309 1.1625 1.2086 34 6.5000 1.1253 1.1244 1.1521 1.1998 35 6.3333 1.1208 1.1221 1.1404 1.1903 36 6.1667 1.1191 1.1218 1.1283 1.1805 37 6.0000 1.1183 1.1205 1.1182 1.1702 38 5.8333 1.1170 1.1180 1.1149 1.1602 39 5.6667 1.1158 1.1159 1.1146 1.1534

  • Distance from bottom of active core (feet)

Millstone - Unit 3 TRM 8.1-17 LBDCR 04-MP3-004 March 25, 2004

TECHNICAL REfOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 10 Table 1 (continued)

RAOC W(Z) Function Millstone Unit 3 - Cycle 10

-12/+9 AFD at 100% RTP Burnup Burnup Burnup Burnup Mesh Axial* 150 3000 10000 18000 No. Height MWD/MTU MWD/MTU MWD/MTU MWD/MTU 40 5.5000 1.1166 1.1162 1.1153 1.1535 41 5;3333 1.1188 1.1178 1.1159 1.1548 42 5.1667 1.1213 1.1196 1.1171 1.1539 43 5.0000 1.1233 1.1210 1.1189 1.1523 44 4.8333 1.1247 1.1219 1.1206 1.1508 45 4.6667 1.1259 1.1225 1.1218 1.1492 46 4.5000 1.1272 1.1227 1.1226 1.1469 47 4.3333 1.1300 1.1227 1.1232 1.1440 48 4.1667 1.1343 1.1224 1.1235 1.1404 49 4.0000 1.1380 1.1217 1.1241 1.1361 50 3.8333 1.1413 1.1218 1.1264 1.1328 51 3.6667 1.1444 1.1237 1.1306 1.1316 52 3.5000 1.1474 1.1265 1.1349 1.1319 53 3.3333 1.1502 1.1291 1.1383 1.1317 54 3.1667 1.1535 1.1321 1.1418 1.1315 55 3.0000 1.1594 1.1380 1.1487 1.1369 56 2.8333 1.1667 1.1483 1.1596 1.1475 57 2.6667 1.1756 1.1621 1.1730 1.1597 58 2.5000 1.1899 1.1759 1.1864 1.1718 59 2.3333 1.2063 1.1893 1.1995 1.1838 60 2.1667 1.2217 1.2028 1.2126 1.1956 61 2.0000 1.2368 1.2161 1.2253 1.2072 62 1.8333 1.2515 1.2288 1.2375 1.2184 63 1.6667 1.2653 1.2407 1.2489 1.2290 64 1.5000 1.0000 1.0000 1.0000 1.0000 65 1.3333 1.0000 1.0000 1.0000 1.0000 66 1.1667 1.0000 1.0000 1.0000 1.0000 67 1.0000 1.0000 1.0000 1.0000 1.0000 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 8.1-18 LBDCR 04-MP3-004 March 25, 2004

TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 Table 2 Base Load W(Z) Function, Millstone Unit 3 - Cycle 10 Burnup Bumup Burnup Bumup Burnup Mesh . AxialI 150 1200 3000 10000 18000 No. Height MWDIMTU MWDIMTU MWDIMTU MWD/MTU MWDIMTU 1 12.0000 .1.0000 1.0000 1.0000 1.0000 1.0000 2 11.8333 1.0000 1.0000 1.0000 1.0000 1.0000 3 11.6667 1.0000 1.0000 1.0000 1.0000 1.0000 4 11.5000 1.0000 1.0000 1.0000 1.0000 1.0000 5 11.3333 1.0000 1.0000 1.0000 1.0000 1.0000 6 11.1667 1.0000 1.0000 1.0000 1.0000 1.0000 7 11.0000 1.0000 1.0000 1.0000 1.0000 1.0000 8 10.8333 1.0000 1.0000 1.0000 1.0000 1.0000 9 10.6667 1.0000 1.0000 1.0000 1.0000 1.0000 10 10.5000 1.2306 1.2315 1.2348 1.1769 1.1551 11 10.3333 1.2258 1.2267 1.2299 1.1778 1.1546 12 10.1667 1.2207 1.2217 1.2249 1.1753 1.1556 13 10.0000 1.2128 1.2139 1.2174 1.1703 1.1579 14 9.8333 1.2039 1.2050 12085 1.1637 1.1576 15 9.6667 1.1962 1.1970 1.1999 1.1583 1.1559 16 9.5000 1.1905 1.1904 1.1919 1.1566 1.1545 17 9.3333 1.1808 1.1801 1.1804 1.1555 1.1506 18 9.1667 1.1682 1.1673 1.1672 1.1536 1.1463 19 9.0000 1.1581 1.1574 1.1578 1.1521 1.1453 20 8.8333. 1.1528 1.1521 1.1524 1.1523 1.1408 21 8.6667 1.1506 1.1496 1.1493 1.1 542 1.1364 22 8.5000 1.1474 1.1463 1.1459 1.1562 1.1403 23 8.3333 1.1428 1.1415 1.1408 1.1 563 1.1465 24 8.1667 1.1388 1.1371 1.1356 1.1555 1.1520 25 8.0000 1.1377 1.1353 1.1328 1.1562 1.1592 26 7.8333 1.1361 1.1334 1.1302 1.1561 1.1661 27 7.6667 1.1346 1.1316 1.1279 1.1554 1.1713 28 7.5000 1.1362 1.1326 1.1280 1.1565 1.1752 29 7.3333 1.1375 1.1335 1.1281 1.1 568 1.1777 30 7.1667 1.1369 1.1327 1.1269 1.1553 1.1790 31 7.0000 1.1353 1.1309 1.1249 1.1526 1.1791 32 6.8333 1.1329 1.1287 1.1229 1.1489 1.1780 33 6.6667 1.1294 1.1258 1.1211 1.1440 1.1757 34 6.5000 1.1247 1.1223 1.1196 1.1382 1.1723 35 6.3333 1.1210 1.1196 1.1187 1.1 313 1.1676 36 6.1667 1.1191 1.1182 1.1181 1.1237 1.1625 37 6.0000 1.1183 1.1171 1.1167 1.1171 1.1586 38 5.8333 1.1171 1.1156 1.1145 1.1149 1.1556 39 5.6667 1.1156 1.1138 1.1122 1.1146 1.1531

  • Distance from bottom of active core (feet)

Millstone - Unit 3 TRM 8.1-19 LBDCR 04-MW3-004 March 25, 2004

TECHNICAL REOUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 Table 2 (continued)

Base Load W(Z) Function Millstone Unit 3 - Cycle 10 B BMW BMW BUMP iash Adai* 150 1200 3000 10000 18000 w Heit MWVV)T MVMTU MAOU MrAWU hVolU 40 5.5000 1.1149 1.1128 1.1108 1.1140 1.1512 41 53333 1.114 1.1117 1.1092 1.1137 1.1488 42 5.1667 1.1124 1.1098 1.1070 1.1137 1.1454 43 5.0000 1.1104 1.1076 1.1042 1.1133 1.1414 44 4.8333 1.1081 1.1051 1.1013 1.1123 1.1372 45 4.6667 1.1053 1.1020 1.0979 1.1111 1.1330 46 4.5000 1.1023 1.0988 1.0943 1.1095 *1.1280 47 4.3333 1.0989 1.0960 1.0926 1.1076 1.1226 48 4.1667 1.0953 1.0937 1.0923 1.1055 1.1166 49 4.0000 1.0917 1.0913 1.0920 1.1033 1.1099 50 3.8333 1.0907 1.0904 1.0913 1.1006 1.1042 51 3.6667 1.0927 1.0915 1.0908 1.0981 1.1035 52 3.5000 1.0943 1.0928 1.0917 1.0982 1.0981 53 3.3333 1.0949 1.0934 1.0923 1.0988 1.0953 54 3.1667 1.0959 1.0943 1.0929 1.1003 1.0926 55 3.0000 1.0997 1.0986 1.0981 1.1033 1.0938 56 2.8333 1.1052 1.1048 1.1055 1.1110 1.1001 57 26667 1.1112 1.1113 1.1129 1.1237 1.1100 58 2.5000 1.1176 1.1183 1.1211 1.1365 1.1198 59 23333 1.1268 1.1283 1.1323 1.1489 1.1293 60 2.1667 1.1392 1.1413 1.1465 1.1616 1.1389 61 2.0000 1.1513 1.1541 1.1605 1.1741 1.1485 62 1.8333 1.1628 1.1663 1.1738 1.1862 1.1577 63 1.6667 1.1738 1.1779 1.1866 1.1976 1.1665 64 1,5000 1.0000 1.0000 1.0000 1.0000 1.0000 65 1M33 1.0000 1.0000 1.0000 1;0000 1.0000 66 1.1667 1.0000 1.0000 1.0000 1.0000 1.0000 67 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 68 0.8333 1.0000 1.0000 1.0000 1.0000 1.0000 69 0.6667 1.0000 1.0000 1.0000 1.0000 1.0000 70 0.5000 1.0000 1.0000 1.0000 1.0000 1.0000 71 0.3333 1.0000 1.0000 1.0000 1.0000 1.0000 72 0.1667 1.0000 1.0000 1.0000 1.0000 1.0000 73 0.0000 1.0000 1.0000 1.0000 1.0000 1.0000

  • [)arm from bottom of active core (feet)

Millstone - Unlt 3 TRM 8.1-20 LBDCR 04-MP3-004 March 25,2004

I TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 10 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 (E Proprietary).

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

3.3 WCAP-9561-P-A, ADD. 3, Rev. 1, "BART A-1: A COMPUTER CODE FOR THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS-SPECIAL REPORT:

THIMBLE MODELING W ECCS EVALUATION MODEL," July 1986 (E Proprietary).

3.4 WCAP-10266-P-A, Addendum 1, Rev. 2-P-A, "THE 1981 VERSION OF THE WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE,"

March 1987 E Proprietary).

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

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

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

3.8 WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Report," April 1995 (I Proprietary).

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

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

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

Millstone - Unit 3 TRM 8.1-21 LBDCR 04-MP3-004 March 25,2004

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