ML11215A129

Startup Test Report for Cycle 21

ML11215A129
Person / Time
Site:	Millstone
Issue date:	07/26/2011
From:	Macmanus R Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
11-394
Download: ML11215A129 (15)

Text

'0'Dominion Dominion Nuclear Connecticut, Inc.

Millstone Power Station Rope Ferry Road Waterford, CT 06385 JUL236 20ff U. S. Nuclear Regulatory Commission Serial No.11-394 Attention: Document Control Desk NSS&L/WEB RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 STARTUP TEST REPORT FOR CYCLE 21 Pursuant to Section 6.9.1.3 of the Millstone Power Station Unit 2 Technical Specifications, Dominion Nuclear Connecticut, Inc. hereby submits the enclosed Startup Test Report for Cycle 21.

Should you have any questions about the information provided or require additional information, please contact Mr. William D. Bartron at (860) 444-4301.

Very truly yours, R. K. MacManus Director - Nuclear Station and Licensing

Enclosure:

(1)

Commitments made in this letter: None.

cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 C. J. Sanders Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08B3 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station (PjgiL

Serial No.11-394 Docket No. 50-336 ENCLOSURE STARTUP TEST REPORT FOR CYCLE 21 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No. 11-394/Enclosure/Page 1 Table of Contents

1.

SUMMARY

2. INTRODUCTION 3

3. LOW POWER PHYSICS TESTING RESULTS 3 3.1 Unrodded Critical Boron Concentration 4 3.2 Moderator Temperature Coefficient 4 3.3 Control Element Assembly Rod Worth Parameters 5 3.4 Rodded Critical Boron Concentration 15 3.'5 Control Rod Drop Time Measurements 5

4. POWER ASCENSION TESTING RESULTS '5 4.1 Power Peaking, Linear Heat Rate and Incore Tilt Measurements -5 4.2 Critical Boron Measurements 6 4.3 Hot Zero Power (HZP) to Hot Full Power (HFP) Critical Boron Difference 7 4.4 Flux Symmetry Measurements 7 4.5 Moderator Temperature Coefficient 7 4.6 Reactor Coolant System Flow 8 4.7 Core Power Distributions 9 4.8 Reactor Coolant System Radiochemistry 9

5. REFERENCES 10

6. FIGURES 10 6.1 Cycle 21 Core Loading Map 11 6.2 69% Core Power Distribution Map 12 6.3 100% Core Power Distribution Map 13 May 2011

'Serial No. 11-394/Enclosure/Page 2

SUMMARY

The refueling outage preceding the Cycle 21 startup was approximately 30 days, starting on April 2,2011 and ending on May 03, 2011.

The results of the Millstone 2, Cycle 21 low power physics testing and power ascension testing programs were in good agreement with the core design predictions. All measured parameters were within the review and acceptance criteria of the tests. All Technical Specification Limiting Conditions of Operation (LCOs) were met.

Implementation of the Startup Test Activity Reduction (STAR) Program for Millstone 2 Cycle 21 has been accomplished in accordance with the steps outlined in WCAP- 16011 -A-P, Rev. 0 for (1) core design, (2) Control Element Assembly (CEA) lifetime, and (3) fuel fabrication. The STAR Applicability requirements for refueling have been accomplished for CEA coupling verification and startup testing. The application of the STAR Program allowed for the elimination of control rod worth measurements from the startup physics testing.

May 2011

Serial No. 11-394/Enclosure/Page 3

2. INTRODUCTION The Millstone 2 Cycle 21 fuel loading was completed on April 20, 2011. The attached core map (Figure 6.1) shows the final core loading. The subsequent operation/testing milestones were completed as follows:

Initial Criticality May 02, 2011 Low Power Physics Testing Complete May 02, 2011 Turbine On-Line May 03, 2011 30% Power Testing Complete May03,2011 69% Power Testing Complete May 04, 2011 100% Power Testing Complete May 10,2011 The Millstone 2 Cycle 21 core is comprised of 217 AREVA manufactured fuel assemblies.

3. LOW POWER PHYSICS TESTING RESULTS Low Power Physics Testing was conducted at a power level of approximately 4 x 10-2 % power.

May2011

Serial No. 11-394/Enclosure/Page 4 3.1 Unrodded Critical Boron Concentration The Critical Boron Concentration (CBC) measured with CEA Group 7 at 142 steps withdrawn and a reactor coolant system (RCS) temperature of 529.0°F was 1646 ppm.

Adjusted to the prediction conditions of Group 7 at 180 steps withdrawn and an RCS temperature of'532°F yields an adjusted, measured CBC of 1661 ppm.

Adjusted, measured unrodded CBC = 1661 ppm Predicted unrodded CBC = 1654 ppm Difference - 7 ppm (61 pcm)

Review Criteria is +/- 50 ppm of the predicted CBC.

Acceptance Criteria is +/- 1000 pcm of the predicted CBC.

Review and Acceptance Criteria met? Yes.

3.2 Moderator Temperature Coefficient The Isothermal Temperature Coefficient (ITC) measurements were performed at a boron concentration of 1646 ppm, an average RCS temperature of 530.5°F, and CEA Group 7 at 142 steps.

The measured ITC at these conditions was +1.40 pcm/°F.

Adjusted to the prediction conditions for an RCS boron concentration of 1654 ppm and an RCS temperature of532°F yields an adjusted, measured ITC of+1.42 pcm/°F.

Adjusted, measured ITC +1.42 pcm/°F Predicted ITC +2.20 pcm/°F Difference = -0.78 pcm/°F Review Criteria is +/- 2 pcm/°F of the predicted ITC.

Review Criteria met? Yes.

May 2011

Serial No. 11-394/Enclosure/Page5 The Moderator Temperature Coefficient (MTC) was determined by-subtracting the predicted Doppler Temperature Coefficient at the test conditions from the adjusted, measured ITC. The MTC at these conditions was +0.286 x 104 Ap/0 F. The Millstone 2 Technical Specifications require the MTC be less positive than

+0.7 x 10-4 Ap/°F for power levels less than 70% power.

Technical Specification limit met? Yes.

3.3 Control Element Assembly Rod Worth Parameters CEA Rod Worth Parameters were not measured as allowed by WCAP-16011-P-A, "Startup Test Activity Reduction Program."

3.4 Rodded Critical Boron Concentration The CBC measured with CEA Group A inserted was not performed during Cycle 21 startup testing due to application of the STAR Program.

3.5 Control Rod Drop Time Measurements The Millstone 2 Technical Specifications require that all CEAs drop in less than or equal to 2.75 seconds to the 90% inserted position, with RCS conditions at greater than or equal to 5 15°F and full flow (all reactor coolant pumps operating).

Control rod drop time testing was done at an RCS temperature of 530°F with all four reactor coolant pumps operating. The average control rod drop time was 2.20 seconds to 90% insertion, with the fastest and slowest drop times being 2.08 seconds and 2.27 seconds, respectively.

Technical Specification limits met? Yes.

4. POWER ASCENSION TESTING RESULTS 4.1 Power Peaking, Linear Heat Rate and Incore Tilt Measurements The following core power distribution parameters were measured during the power ascension to ensure compliance with the Technical Specifications:

Total Unrodded Integrated Radial Peaking Factor (FrT) is the ratio of the peak fuel rod power to the average fuel rod power in an unrodded core. This value includes the effect of Azimuthal Power Tilt.

May 2011

Serial No. 11-394/Enclosure/Page 6

• Linear Heat Rate (L-I Rt) is the amount of p'ower being produced per linear length of

-fuel rod.

• Azimuthal Power Tilt is the maximum difference between the powerngenerated in any core quadrant (upper or lower) and the average power of all quadrants in that half (upper or lower) of the-core divided by the average power of all quadrants in that half (upper or lower) of the core.

The measurements of these parameters were:

Power Level FrT Peak Linear Heat Rate Incore Tilt 66% 1.593 9.10 KW/ft 0.0041 100% 1.550 12.77 KW/ft 0.0048 The corresponding technical specification limits for all power levels for these parameters are:

• Fr'T < 1.69 (Note - larger values of FrT are permissible at less than 100% power)

• Peak Linear Heat Rate _<15.1 KW/ft

• Azimuthal Power Tilt _<0.02 Technical Specification limit for FrT met? Yes.

Technical Specification limit for LHR met? Yes.

Technical Specification limit for Tilt met? Yes.

4.2 Critical Boron Concentration Measurements CBC measurement was performed at 100% power at equilibrium xenon conditions.

The CBC measured at 100% power with CEA Group 7 at 180 steps withdrawn and an RCS cold leg temperature of 544.3'F was 1198 ppm. The cycle average exposure at the time of this measurement was 215 Megawatt Days per Metric Ton Uranium (MWD/MTU).

Adjusted to the prediction conditions of 100% power at an All Rods Out (ARO) condition and an RCS cold leg temperature of 545 'F yields an adjusted, measured CBC of 1199 ppm.

Adjusted, measured 100% power CBC = 1199 ppm Predicted 100% power CBC = 1198 ppm Difference 1 ppm (8 pcm)

Review Criteria is +/- 50 ppm of the predicted CBC.

May 2011

Serial No. 11-394/Enclosure/Page 7 Acceptance Criteiia is+/- 1000 pcm 6f the predicted CBC.

Review and Acceptance Criteria met? Yes.

4.3 Hot Zero Power (HZP) to Hot Full Power (HFP) Critical Boron Concentration Difference The difference in the adjusted measured CBC performed at HZP and HFP was determined and compared to the design prediction.

Predicted change in CBC from HZP to HFP = 441 ppm Adjusted, measured change in CBC from HZP to HFP = 463)Dm Difference = -22 ppm Review Criteria is +/-_50 ppm of the predicted CBC difference.

Review Criteria met? Yes.

4.4 Flux Symmetry Measurements The core neutron flux'symmetry was measured at approximately 30% power using the fixed incore detector monitoring system. The differences between measured and calculated signals in operable incore detector locations ranged from -0.029 to +0.047.

Review Criteria is +/- 0.10.

Review Criteria met? Yes.

The maximum azimuthal asymmetry in the neutron flux from measurements of the variation in incore detector signals from symmetric incore detectors was 2.60%

Review Criteria is +/- 10%.

Review Criteria met? Yes.

4.5 Moderator Temperature Coefficient The ITC measurements were performed at a power level of 98.95 %, an RCS boron concentration of 1198 ppm, and an average RCS temperature of 570.38°F, and CEA Group 7 at 180 steps.

May2011

Serial No. 11-394/Enclosure/Page '8 The measured ITC at these conditions was -'5.452 pcmr/F.

The predicted ITC was determined for a power level of 100%, an RCS boron concentration of 1,205 ppm, an average RCS temperature of570°F, and at an ARO condition.

The predicted ITC at these conditions was -5.290 pcm!°F.

The predicted ITC adjusted for 98.95% power, an actual RCS boron concentration of 1198 ppm and an RCS temperature of570.380 F yields an adjusted, predicted ITC of-5.402 pcm/°F.

Adjusted, Predicted ITC = -5.402 pcm/IF Measured ITC = -5.452 pcm/°F Difference = 0.050 pcm/°F Review Criteria is +/- 2 pcm/0 F of the predicted ITC.

Review Criteria met? Yes.

The MTC was determined by subtracting the predicted Doppler Temperature Coefficient at the test conditions from the measured ITC. The MTC at these conditions was -0.422 x 10-4 Ap/°F. The Millstone 2 Technical Specifications require the MTC be less than or equal to +0.4 x 10-4 Ap/0 F for power levels greater than 70%

power.

Technical Specification limit met? Yes.

4.6 Reactor Coolant System Flow The RCS flow rate was measured using the secondary calorimetric method, in which the RCS flow rate is inferred by performing a heat balance around the steam generators and RCS to determine reactor power, and measuring the differential temperature across the reactor core to determine the enthalpy rise.

The measured RCS flow rate at 100% power was 385,974 gallon per minute (GPM).

When 13,000 GPM is subtracted from the measured flow rate to account for measurement uncertainties, the Minimum Guaranteed Safety Analysis RCS Flow Rate is 372,974 GPM. This value is used to satisfy the technical specification surveillance requirement.

May 2011

Serial No. 11-394/Enclosure/Page 9 The Millstone 2 Technical Specifications require the RCS flow rate to be greater than 360,000 GPM.

Technical Specification limit met? Yes.

4.7 Core Power Distributions The core power distribution measurements were inferred from the signals obtained by the fixed incore detector monitoring system. These measurements were performed at 66% power and 100% to determine if the measured and predicted core power distributions are consistent.

The core power distribution map for 66% power, cycle average exposure of 10 MWD/MTU, non-equilibrium xenon conditions is shown in Figure 6.2. This map shows that there is good agreement between the measured and predicted values.

The core power distribution map for 100%, cycle average exposure of 24 MWD/MTU, non-equilibrium xenon conditions is shown in Figure 6.3. This map also shows that

• there is good agreement between the measured and predicted values.

The review criteria for these measurements are:

1. The difference between the measured and predicted Relative Power Densities (RPDs) for core locations with an operable incore detector is less than 0.1.

2. The Root Mean Square (RMS) deviation for radial and axial power distributions between the measured and predicted values is less than 0.05.

Review Criteria met? Yes, for both 66% and 100% power.

4.8 Reactor Coolant System Radiochemistry RCS radiochemistry analysis during the power ascension testing program and during subsequent power operation indicate activity levels with Iodine- 131 values of about 2.36 x 104 pCi/ml. These RCS activity levels show that all failed fuel assemblies have been discharged from the core.

May 2011

Serial No. 11-394/Enclosure/Page 10

5. REFERENCES 5.1 EN 21004K, "Cycle 21, Low Power Physics Test" 5.2 EN 21004J, "Cycle 21, Power Ascenision Testing" 5.3 ETE-NAF-2011-0060, Rev. 0, Attachment A, "Millstone Unit 2, Cycle ,21 'Startup and Operations Report," April 2011 (Areva NP, Inc. Proprietary).

5.4 SP 21010, "CEA Drop Times"

'5.5 WCAP-16011-P-A Revision 0. "Startup Test Activity Reduction Program," February 2005 5.6 ETE-NAF-2011-0056, Rev 0, "Application of the'Startup Test Activity Reduction (STAR) Program for Cycle 21," May 1, 2011

6. FIGURES 6.1 Cycle 21 Core Loading Map 6.2 66% Core Power Distribution Map 6.3 100% Core Power Distribution Map May 2011

"Serial No. 11-394/Enclosure/Page 11 I-8 1Y-0 [12Y-43-i1 -4Y-24 1Y-17 I Y-46

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K-il K-i3 K-iS K-16 - Y-34 K-i 7 K-5 K-6 K-9 K-11 K-13 Y-49 K-15 Y-39 K(-16 K-17 Y-60 Y-29 Y-56 AA-31 AA-15 AA-15 Y-49 Y-39 Y-34 Y-56 AA-10 AA-10 114 133

-9 ~- 9-9-9-9-9 114 133 9~9~9~9~ Y-67 N-i 8 N-4 N-A N-5 N-6 N-7 W-9 N-1i1 N-1 3 N-1 5 N-16 V-17 VV-18 Y-62 Y-62 AA-03 AA-19 AA-55 Z-55 Z-59 Z-50 AA-58 AA-22 AA-06 Yz67 115 158 172 166 126

~9~9~9~91-4 -9 9~9~9 - 9~9~9~9 AA-26 1-18 - Y-61 1-19 1-3 V-3 V-4 V-5 V-6 V-7 1-9 /-1-1 V-13 V-15 V-16 V-17 V-18 V-19 Y-68 Y-68 AA-27 AA-27 Z-07 Z-21 Z-43 AA-35 Y-26 AA-39 Z-46 Z-20 Z-02 AA-26 Y-61 128 177 165 130 183 185 T-2 T-3 T-4 T-5 -6 T-7 T-9 T-1i1 T-13 T-15 T-16 T-17 [18 T-19 -20 Y-35 AA-07 -Z-03 Z-35 AA-63 Z-16 Y-08 AA-46 Y-01 Z-09 AA-66 Z-34 Z-06 AA-02 Y-59 154 132 125 136 S-2 S-3 S-4 S-5 S-6 S-7 S-9 S-11 S-13 S-15 S-16 S-17 S-18 S-19 -20 Y40 AA-23 Z-17 AA-67 Z-40 Z-64 AA-75 Z-29 AA-78 -Zý65 -Z-39 AA-62 Z-24 AA-18 Y-32 168 192 190 182 R-2 R-3 R-4 R-5 R-6 R-7 R-9 R-11 R-13 R-15 R-16 R-17 R-18 R-19 R-20 Y-50 AA-59 Z-47 Z-10 Z-66 AA-43 Y-13 AA-50 Y-12 AA-42 Z-63 Z-15 Z-42 AA-54 Y-55

'-1 110 119 116 171 184 163 162 P'-21 Y-21 Y-20 N-2 N-3 N-4 N-5 N-6 N-7 N-9 N-11 N-13 N-15 N-16 N-17 N-18 N-19 N-20 AA-16 Z-51 AA-40 Y-02 AA-79 Y-09 AA-71 Z-26 AA-70 Y-16 AA-74 Y-07 AA-34 Z-54 AA-09 MI-1 161 137 103 104 164 105 \4-21 Y-44 Y-45 L-2 L-3 L-4 L-5 L-6 L-7 L-9 L-11 L-13 L-I5 L-16 L-17 L-18 L-19 L-20 AA-32 Z-60 Y-27 AA-47 Z-30 AA-51 Z-27 W-67 Z-25 AA-49 Z-32 AA-45 Y-25 Z-58 AA-30 K-1 169 174 181 193 173 K-21 Y-47 Y-42

-2 J-3 J-4 J-5 J-6 J-7 J-9 J-11 J-13 J-15 J-16 J-17 -18 J-19 J-20 AA-11 Z-56 AA-36 Y-05 AA-76 Y-14 AA-72 Z-28 AA-69 Y-11 AA-77 Y-04 AA-38 Z-49 AA-14 112 129 117 109 156 108 21 Y-1 8 Y-23 G-2 G-3 G-4 G-5 G-6 G-7 G-9 G-1I G-13 is-15 G-16 G-17 G-18 G-19 G-20 Y-53 AA-56 Z-44 Z-13 Z-61 AA44 Y-10 AA-52 Y-15 AA-41 Z-68 Z-12 Z-45 AA-57 Y-52 178 134 189 175 186 122 159 F-2 F-3 F-4 F-5 F-6 F-7 F-9 F-i1 F-13 F-I5 P-16 F-17 F-18 F-19 F-20 Y-30 AA-20 Z-22 AA-64 Z-37 Z-67 AA-80 Z-31 AA-73 Z-62 Z-38 AA-65 Z-19 AA-21 Y-38 167 188 187 170 E-2 E-3 E-4 8E-5 E-6 E7 E-9 E-11 E-13 E-15 E-16 E-17 E-18 E-19 E-20 Y-57 AA-04 Z-08 Z-36 AA-68 Z-11 Y-03 AA-48 Y-06 Z-14 AA-61 Z-33 Z-01 AA-05 Y-33 135 106 127 121 D-3 D-4 D-5 3-6 D-7 D-9 3-11 3-13 )-15 )-16 3-17 3-18 3-19 Y-63 AA-28 Z-04 Z-18 Z-48 AA-37 Y-28 AA-33 Z-41 Z-23 Z-05 AA-25 Y-66 111 179 160 124 180 157 Y-64 C-4 C-5 C-6 2-7 C-9 ý--11  :-13 ---15 2-16 '-17 Y-65 Y-65 AA-08 AA-24 AA-60 Z-52 Z-57 Z-53 AA-53 AA-17 AA-01 Y-64 118 176 191 155 123 B-5 5]-6 B-7 3-9 3-11 3-13 3-15 3-16 B-17 Y-36 Y-37 Y-51 AA-13 AA-29 AA-12 Y-54 Y-31 Y-58 113 r Y-22 [ Y-41 r Y -4 120 10 -8[-12 8[1119NORTH Y-1N OT Figure 6.1 Millstone Unit 6 No. 2 Cycle 21 Core Loading Map May 2011

Serial No. 1-394/Enclosure/Page 12

(-5

(-6

(-7

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(-155 K-1

(-16 K-16

(-17 0.541 1.219 0288 0.551 1.229 0.294

-0.003 -0.010 -0.006 N-18 INOP ~

f~N 17 fvV-18 N--4 N-A N-5 N-6 N-7 N-9 N-11 N-13 NW-15 0.412 1.257 N-1 6 INO r-17 r-18 0.419 1.252

-0.007 0.005 U . U ' - U .- U - U.- U - ' -

7 U1-4

- .1-5 - -

1-6 7 /-9 1-11 /-13 - 1-15 1-16 1-17 `/-18 J-19 J73 0.978 1.285 0.413 0.989 1.294 0.419

-0.011 -0.0098 -0.006 T-2 T-3 T-4 T-5 T-6 T-7 T-9 T-11 T-13 -15 T-16 17 T-18 T-19 T-20 0.286 0.985 1,304 0.294 0.992 1.330

-0.008 -0ý007 -0.026 S-2 S-3 -4 S-5 S-6 S-7 S-9 S-11 S-13 S-15 S-16 S-17 S-18 S-19 S-20 1.226 1.213 0.416 1.238 1.188 0.417

-0.012 0.025 -0.001 R-2 R-3 R-4 R-5 R-6 R-7 R-9 R-11 R-13 R-15 R-16 R-17 R-1 8 R-19 R-20 1.198 1.192

'-1 1.198 1.183 '-21 0.000 0009 N-2 N-3 NA- -5 N-6 N-7 N-9 N-1i1 N-13 N-15 N-16 N-17 N-18 N-19 N-20 1.148 0.936 0.995 4-1_ 1.103 0.926 0,992 A-21 0.045 0.010 0.003 L-2 L-3 L-4 L-5 L-6 L-7 L-9 L-11 L-13 L-15 L-16 L-17 L-18 L-19 L-20 0.979 1.204 1.212 0.981

(-I 0.989 1.188 1.188 0.989 <-21

-0.010 00.16 0.024 -0008 J-2 J-3 J-4 J-5 J-6 J-7 J-9 J-1l J-13 J-15 -16 J-17 J-18 J-19 J-20 0.945 1.078

-f-1 0.926 1.053 1-21 0.019 0.025 G-2 G-3 G-4 G-5 G-6 G-7 G-9 G-1lI -13 G-15 -16 G-17 G-18 G-19 G-20 0.943 INOP 0 928 0.015 F-2 F-3 A-4 -5 F-6 F-7 F-9 F-11 F-13 F-15 F-16 F-17 F-18 F-19 F-20 1.246 1.210 1.222 1.252 1.188 1.238

-0006 0.022 -0.016

-2  :-4 E-3

-5 E-6 E-7 E-9 E-i1 E-13 E-15 E-16 E-17 E--18 E-19 E-20 0.286 0 294

-0 008

)-11 )-13 )-15 )-16 3-17 )-18 )-19 0.410 1.303 1.193 0.983 0.419 1.297 1.198 0.989

-0.009 0.006 -0.005 -0.006

>-5 >-6 -7 ]-9 3-11 C-13 C-15 C-16 C-17 C-18 1.232 1.196 1.246 0.419 1.238 1,195 1.252 0.419

-0.006 0.001 -0.006 0.000 3-5 3-6 3-7 3-9 3-11 I8-13 IB-15 IB-16 I8-17 0.283 0.542 0.547 0.294 0.546 0.551 F0.361

-0.011 -0.004 -0.004 Key

[-14

[8 -1 Core Location

[ [100.363I

-0.002

[A12 05231 Measured RPD 0.515 Calculated RPD Difference Root Mean Square Deviation for all Core Locations = 0.013 Figure 6.2 66% Core Power Distribution Map All Rods Out, Non-Equilibrium Xenon, 10 MWD/MTU May 2011

Serial No. 11-394/Enclosure/Page 13

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/-18 1-19 V-3

\-3 V-A V-4 /-5 /-6 /-7 /-9 /-11 /-13 V-15 V-16 /-17 /-18 /-19 0.985 1.177 0.406 0.997 1.186 0.415

-0.012 -0.009 -0.009 T-2 T-3 A4 T-5 -6 F-7 [9 T-11 -13 T-15 T-16 T-17 I18 T-19 T-20 0.287 1.010 1.288 0.294 1.018 1.309

-0.007 -0.008 -0.021 S-2 S-3 S-4 S-5 S-6 S-7 S-9 6-11 -13 S-15 S-16 S-17 S-18 S-19 S-20 1.187 1.260 0.416 1.197 1.237 0.418

-0.010 0.023 -0.002 R-2 R-3 R-4 R-5 R-6 R-7 R-9 R-11 R-13 R-15 R-16 R-17 R-18 R-19 R-20 1.188 1.219 P-1 1.186 1.212 '-21 0.002 0.007 N-2 N-3 N-4 N-5 N-6 N-7 N-9 N-11 N-13 N-15 N-16 N-17 N1-18 N-19 N-20 1.221 0.990 1.019 M-1 1.183 0.986 1.018 0.038 0.004 0.001 L-2 L-3 L-4 L-5 L-6 L-7 L-9 L-11 L-13 L-15 L-16 L-17 L-18 L-19 L-20 (1-21 0.986 1.251 1.258 0.988 K-1 0.997 1.237 1.237 0.997

-0.011 0.014 0.021 -0.009 J-2 J-3 J-4 -5 J-6 J-7 J-9 J-11 J-13 J-15 J-16 J-17 J-18 J-19 J-20 <1-21 1.000 1.128 H-i 0.986 1.103 0.014 0.025 G-2 G-3 GA G-5 G-6 G-7 G-9 G-11 G-13 G-15 G-16 G-17 -18 3-19 G-20 0.997 INOP 0.987 0.010 F-2 F-3 F-4 F-5 F-6 F-7 F-9 F-11 F-13 F-15 F-16 F-17 F-18 F-19 F-20 1.205 1.258 1.187 1.209 1.237 1.197 0004 0.021 -0.010 E-2 E-3 E-4 E-5 E-6 E-7 E-9 E-11 E-13 E-15 E-16 E-17 E-18 E-19 8-20 0.287 0.294

-0.007 D-3 DA D-5 D-6 D-7 D-9 D-11 D-13 D-15 D-16 D-17 D-18 D-19 0.405 1.262 1.185 0.992 0415 1.254 1.186 0.997

-0010 0.008 -0.001 -0.005 CA C-5 C-6 C-7 C-9 C-1I C-13 IC-15 IC-16 C-17 C-18 1.195 1.176 1.207 0.414 1.197 1.173 1.209 0.415

-0.002 S0.003 -0.002 -0.001 4-4-4-4-4-4-4-4 B-5 B-6 B-7 B-9 B-11 1B-13 B-15 B-16 1B-17 0.284 0.542 0.547 0.294 0.547 0.551

-0.010 -0.005 -0.004

- a - - - - - a - a - - - a - a -

Radial 0.362 Root Mean Square Deviation 0.365 for all Core Locations = 0.012 -003Key Axial B-15 0.526 Core Location Measured RPD Root Mean Square Core Average Calculated RPD Deviation = 0.012 Squre oreAveage0.006 Figure 6.3 Difference 100% Core Power Distribution Map All Rods Out, Non-Equilibrium Xenon, 24 MWD/MTU May 2011