ML042100447
| ML042100447 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/19/2004 |
| From: | Scace S Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 04-359 | |
| Download: ML042100447 (18) | |
Text
- -
Dominion-Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road Waterford, CT 06385 AL 19 ag U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
MPS Lic/MAE Docket No.
License No.04-359 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION UNIT 3 STARTUP TEST REPORT FOR CYCLE 10 Pursuant to Section 6.9.1.1 of the Millstone Unit 3 Technical Specifications, Dominion Nuclear Connecticut, Inc. hereby submits the enclosed Startup Test Report for Cycle 10.
There are no regulatory commitments contained within this letter.
If you have any questions or require additional information, please contact Mr. David W.
Dodson at (860) 447-1791, extension 2346.
Very truly yours, St~ephtn E.ace, Director Nuclear Station Safety and Licensing
-TC-a-z('0
Serial No.04-359 Startup Test Report For 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.04-359 Docket No. 50-423 Startup Test Report Cycle 10 Millstone Power Station 3 Dominion Nuclear Connecticut, Inc. (DNC)
Serial No.04-359 Page 1 Table of Contents Paaqe List of Tables.......................................
2 List of Figures.......................................
2 1.0
SUMMARY
3
2.0 INTRODUCTION
3 3.0 FUEL DESIGN........................................
4 4.0 LOW POWER PHYSICS TESTING........................................
4 4.1 Critical Boron Concentrations........................................
4 4.2 Isothermal/Moderator Temperature Coefficients...................
5 4.3 Control Rod Reactivity Worth Measurements....................... 6 5.0 POWER ASCENSION TESTING
....................................... 7 5.1 Power Distribution, Power Peaking and Tilt Measurements.7 5.2 Boron Measurements........................................
9 5.3 Reactor Coolant System Flow Measurement.......................9
6.0 REFERENCES
10
Serial No.04-359 Page 2 List of Tables Table Paqe 1
Summary of Boron Endpoint Results............................................. 5 2
IsothermaVModerator Temperature Coefficient Results.................. 5 3
Control Bank Integral Worth Results............................................. 6 4
Summary of Measured Axial Offset and INCORE Tilt............
......... 8 5
Comparison of Measured F0 to FQ RTP limit..................
.............. 8 6
Comparison of Measured F,&h to F,&h limit for each Fuel Type.........
8 List of Figures Figure Paae 1
Cycle 10 Core Loading Pattern.............................
............... 11 2
INCORE Power Distribution - 30%............................................
12 3
INCORE Power Distribution - 50%............................................
13 4
INCORE Power Distribution - 75%............................................
14 5
INCORE Power Distribution - 100%............................................
15
Serial No.04-359 Page 3 1.0
SUMMARY
Low Power Physics Testing and Power Ascension Testing for Millstone Unit 3 Cycle 10 identified no unusual core response or reactivity anomalies.
All measured core parameters were determined to be within their acceptance criteria. All Technical Specification surveillance requirements were met.
2.0 INTRODUCTION
The Millstone Unit 3 Cycle 10 fuel reload was completed on April 23, 2004. The attached core map (Figure 1) shows the final core configuration. Cycle 10 uses a low leakage loading pattern (L3P) consisting of 72 new Region 12 fuel assemblies, 81 Region 11 once-burned fuel assemblies, and 40 Region 10 twice-burned fuel assemblies. 64 of the 72 feed fuel assemblies, all 76 once-burned fuel assemblies, and all 40 twice-bumed assemblies are of the Westinghouse 17x17 Robust Fuel Assembly (RFA) design. 8 of the feed fuel assemblies are Next Generation Fuel (NGF) Lead Test Assemblies (LTAs).
The 72 Region 12 assemblies are comprised of 16 assemblies enriched to 4.70 weight percent Uranium-235 (w/o U23n,48 assemblies enriched to 4.95 w/o UM, and 8 LTAs enriched to 4.95 w/o U2. The top and bottom regions of all fuel assemblies in the Cycle 10 core are comprised of a 6-inch annular blanket region enriched to 2.6 w/o U235. The fuel assembly locations for the fresh fuel were randomly assigned to prevent power tilts across the core due to systematic deviations in the fresh fuel composition.
Secondary sources and their core locations remain unchanged from Cycle 9.
Every fuel assembly in Cycle 10 contains an insert from the following list of items:
4 secondary sources, 61 RCCAs, and 128 thimble plugs.
Subsequent operational and testing milestones were completed as follows:
Initial Criticality May 6, 2004 Low Power Physics Testing completed May 6, 2004 Main Turbine Online May 8, 2004 30% Power Testing completed on May 10, 2004 75% Power Testing completed on May 13,2004 100% Power Testing completed on May 18,2004
Serial No.04-359 Page 4 Cycle 10 operation is accomplished with a core loading of 193 Westinghouse manufactured fuel assemblies. The Safety Analysis is provided by Westinghouse and the Nuclear Design Report was generated by Millstone personnel.
3.0 FUEL DESIGN The Robust Fuel Assembly (RFA) design comprises 185 out of the 193 assemblies in the Cycle 10 core. This fuel design differs from the previous fuel design in that it incorporates the Westinghouse protective bottom grid (P-Grid),
thicker walled control rod guide tubes and instrument tube, and modifications to the mixing vane grids and Intermediate Flow Mixer (IFM) grids. The P-Grid improves the fuel assembly's resistance to debris and thus debris related failures. The thicker walled guide and instrument tubes make the fuel assembly more resistant to bowing and twisting, thereby further reducing the possibility of an incomplete rod insertion event. The modifications to the mixing vanes grids and IFMs improve the fuel assembly thermal performance and increase the margin to fuel-related design limits.
The final 8 assemblies in the Cycle 10 core are Next Generation Fuel (NGF)
These LTAs, designated Region 12C, have several mechanical differences between them and the RFA assemblies. The LTAs have an Integral Top Nozzle, enhanced structural and IFM grids, two additional IFM grids per assembly, and utilize a tube-in-tube design for the thimbles.
The LTAs also have reduced pressure drop Debris Filter Bottom Nozzles (DFBNs), optimized ZirloTm cladding, and have had the plenum spring used on an RFA replaced by a spring clip.
4.0 LOW POWER PHYSICS TESTING
\\
The low power physics testing program for Cycle 10 was completed using the Westinghouse Dynamic Rod Worth Measurement (DRWM) Technique described in Reference 6.6. This program consisted of the following: Control and Shutdown Bank Worth measurements, Critical Boron Endpoint measurements for All Rods Out (ARO),
and ARO Moderator/isothermal Temperature Coefficient measurements.
Low power physics testing was performed at a power level below the point of nuclear heat to avoid nuclear heating reactivity feedback effects.
4.1 Critical Boron Concentrations The critical boron concentration was measured for the All Rods Out configuration. The test results are provided in Table 1 along with the design predictions. The measured values include corrections to account for differences
Serial No.04-359 Page 5 between the measured critical rod configuration and the ARO configuration. The acceptance criteria of +1 000 percent milliRho (pcm), equivalent to +161 parts per million Boron (ppm), were met for the ARO configuration.
Table 1 Summary of Boron Endpoint Results Measured Predicted M-P Acceptance (ppm)
(ppm)
(ppm)
Criteria (pm)
All Rods Out 2086 2110
-24
+ 161 (ARO) 4.2 IsothermaVModerator Temperature Coefficients Isothermal Temperature Coefficient (ITC) data was measured at the All Rods Out configuration. A controlled heat-up and cool-down of the RCS was performed and the reactivity change was measured. These measurements were corrected for ARO conditions and the averages of the corrected results are presented in Table 2.
The ARO Moderator Temperature Coefficient (MTC) of -0.40 pcmtPF was calculated by subtracting the design Doppler Temperature Coefficient (-1.77 pcmt'F) from the measured ARO Isothermal Temperature Coefficient of -2.51 pcmIPF, and then adding in a correction factor (AITC=+0.34) to account for current core conditions versus predicted core conditions for the given Doppler Temperature Coefficient. The Technical Specification Limit of MTC < +5.0 pcm/0F at ARO Hot Zero Power (HZP) was met. As shown in the data presented in Table 2, all temperature coefficient acceptance criteria were met.
Table 2 Isothermal/Moderator Temperature Coefficient Results Measured Corrected M-P Acceptance (pcmf'F)
Predicted (pcmf'F)
Criteria (pcm/0F)
(pcm/0F)
ARO ITC
-2.51
-2.53
+0.02 NA ARO MTC
-0.40 NA NA MTC < +5.0
Serial No.04-359 Page 6 4.3 Control Rod Reactivity Worth Measurements The integral reactivity worths of all RCCA Control and Shutdown Banks were measured using the Dynamic Rod Worth Measurement Technique (DRWM).
Data for measured and predicted individual bank worths as well as the sum of the worths of all banks are presented in Table 3. The DRWM rod worth acceptance criteria is defined as: the sum of the measured worths (M) of all banks shall be greater than or equal to 90% of the sum of their predicted worths (P).
Table 3 Control Bank Integral Worth Results Measured Predicted M-P
% Difference (pcm)
(pcm)
(pcm)
M-P Control Bank A 793.4 788.6 4.8 0.6 Control Bank B 550.9 545.3 5.6 1.0 Control Bank C 794.7 790.2 4.5 0.6 Control Bank D 562.4 542.5 19.9 3.7 Shutdown 466.7 451.7 15.0 3.3 Bank A Shutdown 1054.5 1044.6 9.9 0.9 Bank B Shutdown 390.9 378.7 12.2 3.2 Bank C Shutdown 388.3 371.4 16.9 4.5 Bank D Shutdown 58.0 58.6
-0.6
-1.0 Bank E Totals 5059.8 4971.6 88.2 1.8 The measured results of the individual bank worths and the total control bank worth showed excellent agreement with the predicted values. The acceptance criteria for the sum of the measured rod worths (greater than or equal to 90% of the sum of the predicted worths) were met.
Serial No.04-359 Page 7 5.0 POWER ASCENSION TESTING 5.1 Power Distribution, Power Peaking and Tilt Measurements The core power distribution was measured through the performance of a series of flux maps during the power ascension in order to ensure compliance with Technical Specifications. The results from the flux maps were used to verify compliance with the power distribution technical specifications.
A low power flux map, at approximately 30% rated thermal power (RTP), was performed to determine if any gross neutron flux abnormalities existed. At the 30% power plateau flux map, data necessary to perform an INCORE to EXCORE calibration via the single point methodology was obtained. Due to indications from the EXCORE detectors subsequent to the 30% map indicating a QPTR greater than 1.02, another flux map was necessary before exceeding 50% RTP to ensure proper core power balance. Per Technical Specification Surveillance 4.3.1.1, Table 4.3-1 Functional Unit 2 Note 6, a flux map at approximately 75%
power was performed for INCORE to EXCORE comparison and no calibration was necessary. Once hot full power equilibrium conditions were reached, a fourth flux map was performed to verify core power distributions were within the design limits.
Table 4 presents a summary of the Measured Axial Flux Difference (AFD) and calculated INCORE Quadrant Tilt (of either upper or lower) for the flux maps performed during the power ascension.
Presented in Tables 5 and 6 are comparisons of the most limiting measured Heat Flux Hot Channel Factor (Fa) and Nuclear Enthalpy Rise Hot Channel Factor (F:h), including uncertainties, to their respective limits from each of the flux maps performed during the power ascension. The most limiting F0 is based on margin to the limit, which varies as a function of core height.
As can be seen from the data presented in Tables 5 and 6, all acceptance criteria were met and no abnormalities in core power distribution were observed during power ascension.
Serial No.04-359 Page 8 Table 4 Summary of Measured Axial Flux Difference and INCORE Tilt Power Bumup Rod AFD INCORE
(%RTP) (MWD/MTU)
Position
(/)
Tilt
~(steps) 30.0 20 216 5.440 1.0119 46.0 33.4 219 4.805 1.0132 74.3 62.0 219 3.838 1.0116 99.3 267.1 216 0.051 1.0096 Table 5 Comparison of Measured Fo to F0 RTP limit Power Bumup Measured F0 F7 0KP steady
(%RTP) (MWD/MTU) state limit 30.0 20 2.226 4.973 46.0 33.4 2.013 4.983 74.3 62.0 1.878 3.354 99.3 267.1 1.778 2.531 Table 6 Comparison of Measured Fish to FXh limit for each Fuel Type Power Bumup Type 1 Type 1 Type 2 Type 2
(%RTP)
(MWD/IMTU)
(NGF)
Limit (RFA)
Limit 30.0 20 1.441 1.827 1.497 1.912 46.0 33.4 1.406 1.755 1.484 1.836 1.
74.3 62.0 1.402 1.626 1.477 1.702 99.3 267.1 1.381 1.513 1.472 1.583
Serial No.04-359 Page 9 Presented in Figures 2, 3, 4 and 5 are measured Power Distribution Maps showing percent difference from the predicted power for the 30%, 50%, 75%,
and 100% power plateaus. From these data it can be seen that there is good agreement between the measured and predicted assembly powers.
5.2 Boron Measurements Hot full power all rods out boron concentration measurements were performed after reaching equilibrium conditions.
The measured All Rods Out, Hot Full Power, equilibrium xenon, boron concentration was 1432.5 ppm with a predicted value of 1442 ppm. The predicted to measured difference was +56.3 pcm which met the acceptance criteria of + 1000 pcm.
5.3 Reactor Coolant System Flow Measurement The Reactor Coolant Flow rate was determined using a secondary calorimetric heat balance for each loop using the steam generators as the control volumes.
The following parameters were measured:
- Reactor Coolant System Pressure
- Hot Leg Temperatures
- Cold Leg Temperatures
- Feedwater Temperatures
- Feedwater Flow Rates
- Feedwater Pressure
- Steam Generator Pressure Steam generator blowdown was not isolated during the data acquisition period.
Per Technical Specification Surveillance 4.2.3.1.2, the Reactor Coolant System Flow was measured prior to operation above 75% rated thermal power. The measured flow at approximately 75% rated thermal power was 399,260 gallons per minute (gpm) with a minimum required flow of 371,920 gpm. The reactor coolant system flow measurement was re-performed after reaching 100% rated thermal power. The measured flow at 100% power was 399,290 gpm with a minimum required flow of 371,920 gpm. All acceptance criteria were met.
Serial No.04-359 Page 10
6.0 REFERENCES
6.1 SP 31008, Rev. 002-04, "Low Power Physics Testing (IPTE)" performed for Cycle 10.
6.2 EN 31015, Rev. 000-02, 'Power Ascension Testing of Millstone Unit 3."
6.3 Nuclear Design and Core Physics Characteristics of the Millstone Generating Station Unit 3, Cycle 10.
6.4 ANSI/ANS 19.6.1 (1997) 'Reload Startup Physics Tests for Pressurized Water Reactors."
6.5 Design Change Record M3-03-002, "Reload Design for Millstone Unit 3 Cycle 10."
6.6 WCAP-13360-P-A, Revision 1, 'Westinghouse Dynamic Rod Worth Measurement Technique."
6.7 Millstone Unit 3 Cycle 10 Reload Safety Evaluation, Revision 0, dated March 2004.
6.8 Millstone Automated Work Order M3-03-05195 for Cycle 10 Fuel Offload Reload Activities.
6.9 NEU-04-30, Letter from W. R. Rice (Westinghouse) to Hugh McKenney, "Millstone Unit 3 DRWM report for Cycle 10," dated May 26, 2004.
6.10 Letter from V. L. Rooney (USNRC) to J. F. Opeka, "Safety Evaluation for Topical Report, NUSCO-1 52, Addendum 4, 'Physics Methodology for PWR Reload Design,' TAC No. M91815," July 18,1995.
Serial No.04-359 Page 1 1 FIGURE 1 CORE WADING PATTERN MILLSTONE UNIT 3 -
CYCLE 10 R
P N
M L
K J
H G
F E
D C
I I I I I I I 1
103 I
10B I
1.1A 1
103 1.0B1 I
72 165 I 161 I L31 144 1761 64 I
_4 4
_1 B
A 1
10B 43 1OA X33 12B m18 12B K31 12C K66 12B K36 12B 138 12C 168 12B K20 1OA X22 I10B X42 1
2 IC12A18 113 j11 136 11220.2 103 12B 123 112 1111 113 11A 12A 123 12B31 103 1391121 144 K03 L20 L72 L51 L44jL37 M06 145 j26 148 I
3 10A 136 12B 130 11B L58 11A L19 113 L48 123 M51 113 L43 12B 154 113 L70 11k Ll1 113 L46 12B e48 1OA 106 4
9oo 103 123 12A 11A 12A 113 11A 11B 11A 113 12A 11A 12A 123 103 160 127 K08 L04 114 L77 L23 L52 L32 L76 X15 L34 102 117 K59 103 12C 11A 113 113 12B 11A 12B 11A 12B 11 113 11A 12B 103 175 169 L05 L65 L79 K56 L09 162 L26 163 L74 L54 L39 132 162 ICB 12B 113 123 11A 11A 12A 11A 12A 11A 11A 12B 113 12C 103 145 K41 L73 X50 L24 L12 1I1 L14 K04 L06 LOS K64 L61 170 K49 11A1 123 113 13 2113 11k ILI 111 123 11B 113 113 123 11A L17 142 L68 L57 L49 K52 L33 L27 L41 K59 L63 L62 L50 K39 L07 103 12C 113 12B 11A 11k 12A 11k 12A 11A 11A 12B 113 12B 10B 163 171 L60 K60 L40 L18 1ll L16 K12 L15 L36 M57 L56 140 141 103 123 11k 11B 113 123 112 11 123 11B 113 11A 12C 103 166 135 L02 L66 L78 158 L35 K53 L28 155 L80 L45 L30 165 174 10B 12B 12A 11A 12A 113 11A 11B llA 113 12A 11A 12A 12B 103 157 128 109 L25 110 L75 L13 L64 L1O L81 105 L38 107 119 155 5
6 7
-S 9
10 11 10A 112 12B M37 11B L67 11A L29 113 L53 12B 149 1l1 L71 12B M61 113 L42 11A L03 113 L59 12B 129 10A 1o1 10B 1
12311231121111k 1113I1la1I1311Il1112A 12B 12B 10B 137 K2&
M43 101 LO L69 L55 I L47 L21 113 134 1251 47 12
_~
13 14 103 140 10 123 12B 122 12C K72 12B K33 123 M47 12C X67 123 M46 128 K23 10A2 103 126 I 38 103 156 103 173 103 146 1lk L22 103 151 103 167 103 158 15 00 LEGEND F7R Region Identifier tDJ Fuel Axeonbly Identifier REGION ASSEMBLIES ENRXC2MZNT 10L 203 1l1 1l1 12A 123 12C a
32 41 40 16 48 8
4.40 4.80 4.20 4.70 4.70 4.95 4.95
Serial No.04-359 Page 12 FIGURE 2 INCORE Power Distribution -
30%
MILLSTONE UNIT 3 -
CYCLE 10 R
P N
M 2
0.525 k0.0I 0.0 L
K J
H G
F E
D C
n I
I I
I I
I7~
.T
-I B
A U.XI 2.6 U.00 1 2.6 U.OJf 9,1.6,,
1.6 U.3y I 2.1 3.704 3.7 1
I
_I 1.106 0.0 1.137 2.5 1.17, 1.7 1.22
~, 1.7, 1.18E 2.0 1.141 2.7 1.135 2.0 0.531 0.4 0.299 0.3
-i 2
0.296 1.062 1.252 1.281 1.1161 1.284
.2 1.286 1.11 1.311
.2 1.07
.2
-0.7 -0.7 -0.8
-0.3 2.1 1.5 1
1.5 1.64 1.0 0
.5 0.7 i
3 0.521
-1.5 i1.254 1'-1.5j 1.271
-0.9 1.115
-0.3 1.177
-0.2 1.405 1.8
- 1.
27
%1. 1.8j 1.404 1.8 1.202 2.0 1.144 1.6 1.29E 1.2 1.269 0.6 0.529 0.8 i
4 0.271 1.117 1.30 1.130 1 1.172 1.065 1.153 1 1.203
.3 1.13
.2 1.109 0.279
-0.4 0.4 0.6 0.4
-0.7
-0.6
-1.1
-0.1 0.0 2.1 2.5 1.7 0.3 0.3
-0.4 0
1.124 1 1.178 1.163 12 1.020 1 1.054 1.341 1.203 1.201 1.10 1.11 0.341
-0.3_ 1.2 0.3_ 0.0
-1.3 t-2.11
-3.4
-2.5
-0.2 1.9 2.0 1.9 0.8 < 0.7
-0.3 0.385 1.177 1.268 1 1.061 1.033 0.963 1.18 14 1.078 1.406 1 1.166 0.370 0.5 1.0 0.1
-0.1
-1.3
-2.2
-3.6
-4.6
-1.7
-0.7 0.1 1.9 1.1 0.8
-0.3 1.203 1 1.241 1.14 1.236 0.955 0.918 0.986 "11.25 1.162
.27 1.28 1.21 0.450 0.2y 0.1
-1.2
-0.8
-1.1
-2.6
-5.4
-5.1
-2.3 S-1.2 0.7 20 1.3 1.2 0.9 0.372 1.15 1.258 1.390 1.087 1.061 1.200 0.981 1.1 1.036 1.08 1.41 1.287 1.179
.38 0.3 0.0
-0.6 0.7 0.9 0.5
-0.4
-2.8,-4.1,
-1.9 1.0 2.2 1.6 1.2 1.0 0.339 1.09 1.07 1.203 1.2 1.326 1.05 1.244 1.026 1.306 1.201.20 1.128 1.125 0.345
-0.9
-1.2
-1.5 2.0 0.8
-0.5
-2.0
-2.8
-0.8 1.9 2.0 2.8 1.3 1.2 0.26 1.097 1.274 1.139 1.344 1.19 1.07 1.14 1.06 1.173 1.34 1.14 1.32 1.12 0.27
-0.7
-0.8
-0.9 1.9 1.8 1.2 0.3 k-0.7
-1.0
-0.5 1.6 1.7 2.3 0.6 0.
- 5
- 6
- 7
- 8
- 9
-10
-11 0.518
-1.3 1.238
-1.9 1.26C
-1.7 1.128 0.2 9 0.3 y 1.39C 0.8 1.248
-0.2 1.37 1.175
-0.5 1.130 1.1 1.29 9, 1.2, 1.277 0.2
-1.3 K1.2,
B-4 I -9 II1 9-9 0.291 ri.04', 1.249rl.29A 1.0941 1.2751r1.26A 1.2521 1.06811.278 1.27C
-2.0 k-2.l
-2.0 k-0.2,
-0.3 0.6 k0.3,
-1.01 -2.31 -0.5 0.6 1.069
-0.1 0.526
-12
-0.6 1
13 14 0.511
-3.4 1.060
-4.8 1.072
-3.5 i1 6 k 0.0 J 1.202 0.0 1.149
-0.7 1.087
-1.7
/0. 522
< 0.6 0.294
-1.0 4
-
.9 I
4 -
B-I 9
I 40.251
<,7.7,,
0.3251 0.381 rO.44I I 0.3661 0.3321 0.,
-4.7 1 -0.5 K-0.4,
-1.31 -2.91 -1
'I."'
15 A
I -
S J. -
I S
D Measured Power
% Difference (M-P)/P
[] Measured Location
Serial No.04-359 Page 13 FIGURE 3 XKCORE Power Distribution -
466%
MILLSTONlE UtNIT 3 -
CYCLE 10 R
P N
M
- 3 0.52
-0.31 -O.4 L
K J
H G
F E
D C
I I
I I
a I
I
--- I V_1J 1
-IrZ a l=
B A
.Z8u 1.1 1.1 K 1.1, U.4b 1.1 1.5 u.oq
, 1.7,
u.z2 2.2 I-1 I
I 4-I 44.
-4
- 44.
1.084 1.106
.20
1.178 1.133 1.125 0.539 0.304 1.084
-0.4 1.106 1.0 1.15E 1.5 1.201
,,1.5,,
1.17E 2.5 1.13' 3.4 1.125 2.9 0.53E 1.7 0.304 0.7 2
0.30 1.04 1.23 1.257 1.11 1.274 1.286 1.14 1.315 1.26 1.054 03@
0.0 0.0 0.0
-0.5 2.5 1.7 1.7 2.6 5.1 3.3 1.6 0.8
-0.3,
-a,.
.~
4 3
0.532 0.4
.24e
, 0.3, 1.261 0.1 1.114
-0.4 1.180
-0.3 1.39S 1.8 11.401 2.3 1.215 2.8 1.161 3.2 1.286 2.1 1.243 1.1 0.530 0.8 i
4 0.27 1.103 1.29 1.139 1.30 1.179 1.079 1.163 1.08 1.208 1.3 1.143 1.27 1.094 0.276
-1.1 0.9 1.9 1.2
-1.0
-1.0
-1.7
-0.9 1.5 2.8, 2.2 \\ 0.6 0.6
-0.4 0.3 1.108 1.10 1.185 1.17 1.04 1.24 1.070 1.344 1.210 1.212 1.104 1.10 0.349
-1.
1.1 0.7>
0.3
-1.5
-2.7,,
-4.2 \\-3.61
-1.5 1.1 1.6 2.5 1.3 \\ 1.0
-0.3 0.389 1.158 1.261 1.37 1.078 1.054 11.1 0.991 1.202 1.06 1.090 1.406 1 1.156 0.380
-0.5 0.8 0.6 0.1
-1.6
-2.9
-4.4
-5.5
-2.9
-1.9
-0.7 2.3 1.5 1.3 0.0 1.184 1.242 1 1.250 0.982 0.948 1.011 1 1.171 1.27
.2
.2 0.457
-0.
0.1
-0.
-0.7 3.4
-6.4
-6.4
-3.6
-2.I -0.3 2.1 2.0 1.5 0.4 0.379 1.14 1.25 1.378 1.1 1.080 1.213 1.004 1.17 1.050 1.09 1.39 1.2 1.162 0.39
-0.3 0.1 0.0 0.3 0.2
-0.6
-2.0
-4.3
-5.5
-3.3 0.2 1.8 1.8 1.1 <0.5 0.345 1.08 1.08 1.194 1.20' 1.323 1.06 1.252 1.04 1.308 1.205 1.19 1.11 1.091 0.347
-1.4
-1.4
-0.9 0.9 1.0
-0.5
-1.7
-3.2
-4.1
-1.7 1.3 1.9
-0.5
-0.3
.2 1.068 1.239 1.127 1.341 1.197 1.09 1.15 1.083 1.189 1.34 1.149 1.307 1.083 0.27
-1.8
-1.8
-1.9 0.8 1.7 0.6
-0.3
-1.5,
-1.4
-0.2
- 2.
2.1 2.7
-0.9
-0.7
- 5
- 6
- 7
- 8
- 9
-10
-11 0.521
-1.0 1.226
-0.3 1.255
-0.4 1.137 1.1 I.19) 1<11.3,/
1.38E 0.9 1.247
-0.3 I.36)
\\:-05,--
1.18C
-0.3 1.142 2.1 1.283 1<12.3y 1.253 0.9 0.522
-1.5 12 13 0.296
-1.7
\\-1.7J 1.225
-1.4 1.28)
<,0.8.,
1.101 0.7 1.271 1.4 0.25,
~,.2, 1.24f
-0.6 1.072
-1.7 1.265 0.2 1.247 1.4 1.049 0.3
-4.
1-4 4.-t4 4.-
4.44.
6.29
0.521 40.29f 0.52
-1.7 1.078
-1.4 1.085
-1.0
>1.14'
\\,00 1.185 0.2 1.135
-0.5 1.07~
<72-0, 1.073
-1.4 0.297
-1.3 14 0.344
-1.1 0.38S
-0.5 0.374
-1.6 0.343
-2.0 0.273
-1.4 15 LIJD Measured Power
% Difference (M-P)/P Measured Location
Serial No.04-359 Page 14 FIGURE 4 INCORE Power Distribution - 74%
NILLSTONE UNIT 3 -
CYCLE 10 R
P N
M Fj30g 0.541 k2.7A 2.9 L
K J
H G
F E
a I
I I
I a
I I. -
-
T -
- Y
I -
0.284 2.5 0.35E 2.6 40.38~
< 1.3,
0.461 1.3 0.39r 1.0 I0.35e 2.3, 0.284 2.5 D
C e
0.5291 0.3041_
-0.2 0.71_
I A 1
- 44.
4 4.......4.
4 --
- 4.
4 1.120 1.156 1.19) 1.171 1.134 1.119 1.120 2.9 1.12E 2.7 1.156 1.3 41.1
,<1.2,/
1.171 1.9 1.134 3.5 1.11E 2.4 i
2 0.303 1.051 1.236 1.244 1.10 1.262
.2 1.27
.1 1.301 1 1.055 030 0.3 0.5 0.5
-1.5 1.1 0.7 0fi 1.7 :4 2.2 0.9 1.3 1-3 0.519
-2.1
.21) 1.23S
-1.7 1.101
-1.5 1.166
-1.4 1.389 1.1 I.26' 1.0, 1.397 1.8 1.213 2.6 1.151 2.3 1.276 1.3 1.241 0.9 0.53x 1.3 i
4
-1.7108
.18'10 1.13 0.
0.275 1.099 1.286 1.127 1 1.171 1.082 1.168 1 1.21 1
1.13 1.2 1.087 0.273
-0.7 0.5 1.0 0.2
-1.7
-1.7
-1.5
-0.5
-0.5 1.7, 2.7 1.9
-0.1
-0.1
-1.4 70.3;8 1.114
.10 1.181 1.165 1.29 1.048 1.25 1.079 1.349 1.213 1.205 1.095 11.09 0.345
-0.9 1.6 0.9
-0.1
-2.1
-3.5
-2.7 0.6 1.4 1.8 1.9 0.5 0.3
-1.4 0.396 1.166 1.255 1.36 1.075 1.05 1.19 1.004 1.216 1.07 1.094 1.395
.26 1.14 0.375 1.3 1.5 0.1
-0.3
-1.9
-2.7
-3.6
-4.3
-1.8
-0.9
-0.4 1.5 0.6 0.4
-1.3 1.187 1.23 1.23 1
1.257 0.995 0.963 1.023 1.27 1.17' 2
12 1
0.459 1.1 0.3 1.9
-1.5
-1.7
-2.9
-5.1
-4.9
-2.5
-1.4 0.1 \\ 1.5 1.0 1.3 0.9 0.383 1.1 1.235 1.373 1.10 1.087 1.23 1.020 1.18 1.062 1.10t 1.39 1.26 1.163 0.39 0.8 0.2
-1.4
-0.1 0.4 0.1
-0.5
-2.8
-4.1
-2.2 0.4 1.6 1.1 1.2 1.0 0.346 1.083 1.068 1.202
.21 1.338 1.07 1.26 1.052 1.31 1.201
.192 1.115 1.11t 0.352
-1.1
-1.1
-2.0 1.6 1.6 0.6
-0.8
-2.1
-3.1
-1.3 0.9
- 1.
2.0 1.3 1.1
.2 1.089 1.262 1.135 1.351 1.209 1.102 1.16C 1.08t 1.175 1.33 1.139 1.300 1.095 0.27 0.01 0.1
-0.1 1.5 2.5 1.6 0.5
-1.2
-1.6
-1.3 1.1.2 1
0.2 0.4
-5 6
-7
- 8
- 9
- 10
-11 0.524
-0.4 1.219
-0.9 1.24E
-1.1 1.137 1.1 1.1 1.384 0.9 1.238
-1.0 UEs) 1.167
-1.4 1.127 0.8
>1.2i~
1.262 1.6 0.532 0.4 12 13 0.29 1
1.22
.2 1.099 1.26 1.24 1.235 1.066 1.26 1.25 1.061
-1.7
- 1.
-1.4 0.8 0.5 1.0 -2.
0.3 1.6 1.4 0.29)
<-,1.7, 0.52,
-1.3 1.082
-1.0 1.085
-1.0 41.14) 1.182
-0.1 1.134
-0.6 1.082
-0.6 fO.531 0.303 0.7 14 0.2A
<,-0.7,,
0.345
-0.9 0.39C
-0.3 0.376
-1.1 0.342
-2.3 0.275
-0.7 15 D Measured Power
% Difference (M-P)/P
] Measured Location
Serial No.04-359 Page 15 FIGURE 5 INCORE Power Distribution -
100%
MILLSTONE UNIT 3 -
CYCLE 10 R
P N
M L
K J
I I
I H
G F
I I
I E
D C
I I
B A
0.282 0.7 0.358 0.8 90.0-0.461 0.0 0.39E 0.8 0.36 I 2.10 2.1 4..I-1 I
I
. -
-4.
-4.
-4.
-
4
- 4.
4
- 4. -
r
0.30
0.525 1.074 1.103 1.141 1.164 1.130 1.111 0.528 0.302 40.301
,,-1.3~,
0.525
-1.1 1.07A
-1.1 1.103 0.8 1.141 0.2 1.181
,,0.2_,
1.16' 1.6 1.130 3.2 1.111 1.8 0.528
-1.1 0.302
-1.3 I -
2
-1.1 3.2 1.289-1.12 1.
0.30 1.02 1.202 1.253 1.095 1.249
.2 1.262 1.289 1 1.031 0.
-2.0
-1.81 -1.9
-0.6 0.7 0.5 k0.6, 1.4 K4.21 1.5
-1.1 4.4.1.
.41.
0.52C
-2.6 1.233
-1.5 1.111
-0.5 1.174
-0.4 1.38' 1.1 I.26d
\\ 1.51 1.39E 2.2 1.208 2.5 1.138 1.3 1.253 0.1 1.216
-0.6 0.529
-0.4 _.
3 4
0.281 1.091 1.270 1.121
.3 1.184 1.09 1.182 1 1.208 1.124
.2 1.08C 0.27
-0.4 0.0 0.0
-0.2
-05
-0.5
-0.3 0.6 0.7 1.7 < 1.0 0.7 <-0.6
-0.6
-1.4
.35 1.109 1.179 1.177 1.31 1.07 1.29 1.104 1.362 1.213 1.192 1.089 1.09 0.349 S-0.3 1.3 0.6D 0.1
-0.9
-1.1
-1.6
-0.8 1.0 2.1 1.9 1.1 0.2 0.1
-1.7 0.400 1.158 1.246 1.09 1.084 2
1.038 1.251 1.1 1.113 1.388 1 1.140 0.381 1.0 1.0 0.2 t0.2
-0.6
-0.8 <-1.8
-2.3
-0.1 1.0 1.2 1.5 0.5 0.1
-1.0 0.46 1.17 1.237 1.291 1.035 1.000 1.056 1.30 1.193
.26 1.2 1.1 0.46 0.2D -0.1
-1.3
-05
-0.5
-0.9
-2.5
-2.7
-0.6 0.3 1.5 1.9 1.0 0.7 0.385 1 1.230 1.380 1.116 1.108 1.26 1.052 1.22 1.088 1.1 1.39 1.258 1.154 0.0
-0
-1.0 0.9 1.5 1.4 1.2
-0.9
-2.2 -0.5 1.5 2.0 1.1 0.7 0.8 0.352 1.083 1.067 1.205 1.21 1.357 1.10 1.29 1.078 1.331 1.20 1.19 1.114 1.106 0.35
-0.8
-1.0
-1.8 2.2 2.2 1.7 0.7
-0.5
-1.4
-0.2 1.6 1.6 2.2 1.0 1.1
.2 1.084 1.25 1.139 1.339 1.206 1.108 1.094 1.179 1 1.133 1.291 1.097 0 0.0
-0.2
-0.2 2.1 1.6 1.5 0.8 0.1
-0.5
-0.9 0.8 0.9 1.7 0.2 0.0
-5
- 6
-7
- 8
- 9
-10
-11 0.523
-1.5 1.194
-2.5 1.225
-2.2 1.118
-0.4 1.17
<,-0.3,,
1.37%
0.5 1.239
-0.3 1.36~
,-0.4.,
1.16G
-0.8 1.119 0.3 I1.25b 0.5}
1.232
-0.3 0.5291 -
12 I
-4 4.-I 4
I. -4
- 4.
1-4-4.
0.297
-2.6 I;.01~
1.20,
-2.3 1.26~
<-0.6>
1.082
-0.7 1.24Z
-0.1 I.238 1.223
-1.6 1.05E
-2.7 1.248
-1.0 1.232 0.6
-~
13
-
t 1t
9 -
.t -
t -
I --
- t -
t I -,
40.29E
,,-2.6,,
0.523
-2.1 1.075
-1.5 1.078
-1.6
~1. 14 L-0.3, 1.176
-0.3 1.126
-1.1
/1.05o
<,-3.7, 1.065
-1.9 0.302
-1.0 14 A. -
I 4-4 4
4-I 4-4.
I -
0.348
-1.4 0.394
-0.5 0.45~ 0.379
-1.6 0.342
-3.7 0.276
-1.8 15 D Measured Power
% Difference (M-P)/P L]
Measured Location