ML072480159
| ML072480159 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/22/2007 |
| From: | Price J Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 07-0532 | |
| Download: ML072480159 (14) | |
Text
Dominion Nuclear Connecticut, Inc.
Dominion-Millstone Power Station Rope Ferry Road Waterford, CT 06385 AUG 2 2 2007 U. S. Nuclear Regulatory Commission Serial No.
07-0532 Attention: Document Control Desk NSS&L/DF RO One White Flint North Docket No.
50-423 11555 Rockville Pike License No.
NPF-49 Rockville, Maryland 20852-2738 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 STARTUP TEST REPORT FOR CYCLE 12 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 12.
Should you have any questions about the information provided or require additional information, please contact Mr. David W. Dodson at (860) 447-1791, extension 2346.
Sincerely, J.
rice Si*
ice President - Millstone
Enclosure:
(1)
Commitments made in this letter: None.
cc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 191.06-1415 Mr. J. D. Hughey Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8B3 Rockville, MD 20852-2738
Serial No. 07-0532 Docket No. 50-423 Startup Test Report Page 2 of 2 NRC Senior Resident Inspector Millstone Power Station
Serial No. 07-0532 Docket No. 50-423 ENCLOSURE STARTUP TEST REPORT FOR CYCLE 12 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
Serial No. 07-0532/Enclosure/Page 1 of 11 Table of Contents Paqe 1.0 S U M M A R Y........................................................................................
.. 2 2.0 IN T R O D U C T IO N.................................................................................
2 3.0 F U E L D E S IG N...................................................................................
.. 3 4.0 LOW POWER PHYSICS TESTING 3
4.1 Critical Boron Concentration 3
4.2 Moderator Temperature Coefficient.........................................
4 4.3 Control Rod Reactivity Worth Measurements...........................
4 5.0 POWER ASCENSION TESTING........................................................
5 5.1 Power Distribution, Power Peaking and Tilt Measurements
......... 5 5.2 Boron Measurements................................................................
6 5.3 Reactor Coolant System Flow Measurement............................ 6 6.0 R E FE R E N C E S...................................................................................
.. 7 7.0 F IG U R E S..........................................................................................
.. 7
Serial No. 07-0532/Enclosure/Page 2 of 11 1.0
SUMMARY
Low Power Physics Testing and Power Ascension Testing for Millstone Unit 3 Cycle 12 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 12 fuel reload was completed on May 5, 2007.
The attached core map (Figure 1) shows the final core configuration.
Reference [6.3]
documents that Cycle 12 uses a low leakage loading pattern (L3P) consisting of 76 new Region 14 fuel assemblies, 72 Region 13 once-burned fuel assemblies, and 45 Region 12 twice-burned fuel assemblies. The 76 feed fuel assemblies, 72 once-burned fuel assemblies and 40 out of 45 twice-burned assemblies are the Westinghouse 17x17 Robust Fuel Assembly (RFA) design. Five of the twice-burned fuel assemblies are Westinghouse 17x17 Next Generation Fuel (NGF) Lead Test Assemblies (LTAs).
The 76 Region 14 assemblies are comprised of 36 assemblies enriched to 4.70 weight percent Uranium-235 (w/o U235 ) and 40 assemblies enriched to 4.95 w/o U235.
The top and bottom regions of all fuel assemblies in the Cycle 12 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.
Every fuel assembly in Cycle 12 contains an insert from the following list of items:
61 RCCAs, and 132 thimble plugs.
Subsequent operational and testing milestones were completed as follows:
Initial Criticality May 17, 2007 Low Power Physics Testing completed May 17, 2007 Main Turbine Online May 19, 2007 30% Power Testing completed May 20, 2007 75% Power Testing completed May 21, 2007 100% Power Testing completed May 23, 2007 Startup Test Program completed June 4, 2007
Serial No. 07-0532/Enclosure/Page 3 of 11 3.0 FUEL DESIGN The Robust Fuel Assembly (RFA) design comprises 188 out of the 193 assemblies in the Cycle 12 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 5 assemblies in the Cycle 12 core are Next Generation Fuel (NGF) Lead Test Assemblies (LTAs). These LTAs, designated Region 12C, have several mechanical differences from 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 guide tubes. 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. The central fuel assembly in Cycle 12 location H-08 is an LTA with an approved fuel rod average burnup limit of 71,000 MWD/MTU.
4.0 LOW POWER PHYSICS TESTING The low power physics testing program for Cycle 12 was completed using the procedure in reference [6.1] based on the Westinghouse Dynamic Rod Worth Measurement (DRWM) Technique described in reference [6.4]. 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 Concentration The critical boron concentration was measured for the ARO configuration.
The measured values include corrections to account for differences between the measured critical rod configuration and the ARO configuration.
The review and acceptance criteria of +/-500 and +/-1000 percent milliRho (pcm) respectively were met for the ARO configuration.
Summary of Boron Endpoint Results Measured Predicted M-P Acceptance (ppm)
(ppm)
(ppm)
Criteria (pcm)
All Rods Out (ARO) 2171 2177
-6 (-40 pcm)
+ 1000
Serial No. 07-0532/Enclosure/Page 4 of 11 4.2 Moderator Temperature Coefficient Isothermal Temperature Coefficient (ITC) data was measured at the ARO configuration. Controlled heat-ups and cool-downs were performed and the reactivity change was measured.
These measurements were corrected for ARO conditions and the averages of the corrected results are presented below. They were then compared to the design predictions and review criteria. The review criteria of +2 pcm/
OF to the predictions were met.
The ARO Moderator Temperature Coefficient (MTC) of -0.17 pcm/°F was calculated by subtracting the design Doppler Temperature Coefficient (-1.77 pcm/°F) from the measured ARO Isothermal Temperature Coefficient of -1.94 pcm/°F. The Technical Specification Limit of MTC < +5.0 pcm/°F at ARO Hot Zero Power (HZP) was met.
Isothermal/Moderator Temperature Coefficient Results Measured Corrected M-P Acceptance (pcm/fF)
Predicted (pcm/°F)
Criteria (pcm/°F)
(pcm/°F)
ARO ITC
-1.94
-2.04
+0.10 NA ARO MTC
-0.17 NA NA MTC < +5.0 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). The review criteria is that the measured worth is +15% or 100 pcm of the individual predicted worth, whichever is greater and sum of the measured worths is +8% of the predicted worths. The the measured worths sum of their predicted DRWM rod worth acceptance criteria is defined as: the sum of (M) of all banks shall be greater than or equal to 90% of the worths (P).
Control Bank Integral Worth Results Measured Predicted M-P
% Difference (pcm)
(pcm)
(pcm)
(M-P) / P Control Bank A 717.7 731.9
-14.2
-1.9 Control Bank B 722.9 691.6 31.3 4.5 Control Bank C 762.4 744.3 18.1 2.4 Control Bank D 443.4 449.8
-6.4
-1.4 Shutdown Bank A 407.3 400.0 7.3 1.8 Shutdown Bank B 1170.1 1133.5 36.6 3.2 Shutdown Bank C 400.5 397.6 2.9 0.7 Shutdown Bank D 404.4 396.1 8.3 2.1 Shutdown Bank E 67.8 63.3 4.5 7.1 Totals 5096.5 5008.1 88.4 1.8
Serial No. 07-0532/Enclosure/Page 5 of 11 The measured results of the individual bank worths and the total control bank worth showed excellent agreement with the predicted values. All individual and total worth review criteria were met. The acceptance criteria for sum of the measured rod worths (greater than or equal to 90% of the sum of the predicted worths) was met.
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 as specified in reference [6.2]. 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.
Per Technical Specification Surveillance 4.3.1.1, Table 4.3-1 Functional Unit 2 Note 6, a flux map at approximately 100% power was performed for INCORE to EXCORE calibration. The 100% power map also verified core power distributions were within the design limits.
A summary of the Measured Axial Flux Difference (AFD) and INCORE Tilt for the flux maps performed during the power ascension is provided below. Additional tables provide comparisons of the most limiting measured Heat Flux Hot Channel Factor (FQ) 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 FQ reported is based on minimum margin to the steady state limit that varies as a function of core height.
As can be seen from the data presented, all Technical Specification limits were met and no abnormalities in core power distribution were observed during power ascension.
Summary of Measured Axial Flux Difference and INCORE Tilt Power Burnup Rod AFD (%)
INCORE Tilt
(%RTP)
(MWD/MTU)
Position (steps) 30.0 7.1 216 5.362 1.0049 74.0 26.4 216 4.126 1.0025 99.8 116.1 216 0.756 1.0012
Serial No. 07-0532/Enclosure/Page 6 of 11 Comparison of Measured FQ to FQRTP Limit RTP Power Burnup Measured Fa FQ steady Margin to Transient
(%RTP)
(MWD/MTU) state limit Limit 30.0 7.1 N/A N/A N/A 74.0 26.4 1.907 3.396 33.9 %
99.8 116.1 1.820 2.518 14.8%
Comparison of Measured FAh to FAh Limit for each Fuel Type Power Burnup Type 1 Type 1 Type 2 Type 2
(%RTP)
(MWD/MTU)
(NGF)
Limit (RFA)
Limit 30.0 7.1 0.849 1.827 1.525 1.912 74.0 26.4 0.898 1.628 1.468 1.703 99.8 116.1 0.927 1.511 1.454 1.581 Presented in Figures 2, 3 and 4 are measured Power Distribution Maps showing percent difference from the predicted power for the 30%, 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 1506 ppm with a predicted value of 1502 ppm. The predicted to measured difference was +24 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 74% rated thermal power was 402,334 gallons per minute
Serial No. 07-0532/Enclosure/Page 7 of 11 (gpm) with a minimum required flow of 372,292 gpm. The reactor coolant system flow measurement was re-performed after reaching 100% rated thermal power. The measured flow at 100% power was 400,661 gpm with a minimum required flow of 372,292,gpm. All Technical Specification limits were met.
6.0 REFERENCES
6.1 SP 31008, Rev. 003-01, "Low Power Physics Testing (IPTE)"
6.2 EN 31015, Rev. 002-01, "Power Ascension Testing of Millstone Unit 3" 6.3 Nuclear Design and Core Physics Characteristics of the Millstone Generating Station Unit 3, Cycle 12 6.4 WCAP-13360-P-A, Revision 1, "Westinghouse Dynamic Rod Worth Measurement Technique" 6.5 NEU-07-133, Letter from W. F. Staley (Westinghouse) to Robert Borchert, "Dominion Nuclear Connecticut Millstone Unit 3 Low Power Physics Tests (LPPT)," dated June 28, 2007.
7.0 FIGURES Paqe 1
C ycle 12 Loading Plan.............................................................
8 2
INCORE Power Distribution - 30%............................................ 9 3
INCORE Power Distribution - 74%............................................ 10 4
INCORE Power Distribution - 100%......................................... 11
Serial No. 07-0532/Enclosure/Page 8 of 11 FIGURE 1 CORE LOADING PATTERN MILLSTONE UNIT 3 -
CYCLE 12 R
P N
H L
K J
H G
F E
D C
B A
I I I I I I i 123 123 12C 12B 12B 123 123 En9 1M3 3 72 1 43 346 347 363 123 2
14B 143 143 14B 14B 143 143 12 1121 W-:133 P42 P50 P59 P64 P66 P52 P44
=4 M53 1231143 143 14A 13B 13B 13B 13 113 114A1 14B 14B 12B K59 P3 P72P15 170 342 N67 N3 69 P20 P73 P38 L-7 1
2
-3 123 323 13 13A1 133 1331 13A 1I S322 N47 357 N18 P22 13A 325 13B N49 13B N56 13A 329 14B P76 12B H28 90° 123 143 14L 133 14A 13 141 13A 14 13A 141 13B 141 14B 12B K56 P45 P31 36 1 P32 U03 P06 316 P08 308 P14 351 P35 P46 322 123 143 133 133 13A 14" 131 14A 131 141 131 13B 13B 14B 12B 339 P53 362 350 351 P16 335 P26 H32 P27 N07 363 354 P54 341 12B 14B 138 13A 141 13&
14L 13A 141 131 14 131 135 14B L2C 332 P60 359 N11 P09 N33 P01
=27 P02 315 PLO 324 N41 P69 M69 123 143 133 141 13A 14 131 12C 13A 14A 13A 14A 13B 14B 123 329 P70 72 IP23 330 P24 313 371 N37 P19 N14 P21 361 P67 330 12C 143 13B 131 141 13A 14A 13A 14A 13A 14A 13A 133 142 12B l65 P68 345 310 P11 323 P03 336 P04 326 P05 319 340 P63 M35 12B 143 133 133 13A 14A 13A 14A 13A 1"
13A 133 13B 14B 12B 340 P55 H55 358 N06 P13 31 P30 N21 P18 305 346 373 P49 342 123 143 141 133 141 131 141A 13A 14A 131 141 13B 141A 143 12 320 147 P17 352 P34 304 P12 317 P07 302 P33 366 P29 PP 1 355 6
-7
-8
-9 1
10 11 123B 143
- 131, 13B 313 X171 P651N2013153 13A x28 14A
]P36 13A 13B 13B 13A 143 12B 312 1 N60 A48 I34 I P 321 12 123 Iý 143 143 I 141I J3 348 3
7 P28 N 59 13B 344 13B 364 13: 113: 1&
I 14B 143 12B H38 X68 P25 P62 P40 352 123 123 1+/-4B3 143 362 326 1
P56 14B P61 143 P75 143 143 143 I 123 123 P
I P517 P43 I
M18 44 J
13 14 123 123 H,8 336 12B 331 12 34,5 12C 12:
12B K68 K38 I27 15 00 LEGEND REGION ASSEMBLIES ENRICHMENT R
Region Identifier X.] Fuel Assembly Identifier 123 12C 13A 13B 14A 14B 40 4.95 5
4.95 36 4.00 36 4.95 36 4.70 40 4.95
Serial No. 07-0532/Enclosure/Page 9 of 11 FIGURE 2 INCORE Power Distribution -
30%
MILLSTONE UNIT 3 -
CYCLE 12 R
P N
M I I I r.2; 0.47j
[,-2.2.A -2.3 L
K J
H G
F E
0.210.38 o.
.38 0.
0.3820.377 0.276 0.4 1.9, 1.6,,22 1.1 11 1.1 D
C B
0.49-4028
-2.
1-5 A
4- ~-
1-4
~
4-1.062r".25j 1.223 20-A 12201 1.258 1.070 0.4 K1.5A 1.7 p2.1j 2.0 12.4 10.81
-- 1
-2
-3
-4 0.2651 0.94 1.13 1.312 1.322. 1.33 1.2 37 1.331.36-1. 322 T1.15 0.952'026S*
-2.6
-2.5
-2.7 0.3 0.41 0.8
.0j 1.7 3.2d 0.8 L-2.0
-1.2
,-0.7 6K.48b"1.144 1.05 1.214. 1.20 1.128 1.314 1.12011.25010.24 1.07ý 1.1-0 0.425
,,-2.6,4,-2.7A,-3.0 1-2.6 1-2.6 10.8T 0.2A 1.01 0.6 10.21 -1.1 1-0.9 1-0.2 0.27( 1.052 1.30 1.2 1.25 1.038 1.258 1.057 '1.26 1.057 1.27 1.24 1.31
- 1.
0.28
-1.1
-0.8
-0.9
-1.0
.-2.9
-3.0
-2.6
-1.8
-1.7
-1.0
-1.1
-0.5,,0.6/
0.8 1.4
'0.36) 1.243 '1.3,.
1.256 1.056 1.20 1.01 1.1 1.041 1.2 1.7 1.252 1.342 1.25ý 0.378
-0.3 1.1 2.8 1.1
-1.1
-2.8
-3.0 \\-2.3/ -0.7 0.2 0.7 1.1 1.9,1.8/
1.3 0.384 1.221 1.351 1.14
- 1.
1.039 1.23) 0.947 1.244 '1.04 1.289 1.142 "1.3 1.236 0.38 1.6 2.1 2.7 \\2.4A 0.4
-0.9 ý-2.04 -1.7
-1.2 \\0.0
-0.2 2.5 2.4A 2.8 1.8 "0. 3 1.207 1.31" 1.346 1.09) 1.217 0.95) 0.778 0.951 1.19) 1.067 "1.3 1.31 1.21ý 0.382 2.7,/
2.5 \\2.4, 2.3
_2.1, 0.1 \\-0.6
-1.4
-1.2
-1.6
-0.8,*1.2 2.6 3.2 2.7 0.390 1.23 1.350 1.136 1.312 1.062 1.272 0.959'1.221 1.01 1.27) 1.117 1.336 1.231 0.38 2.6 \\2.4 2.1 2.0 1.6 1.3 1.0
-0.4 \\-3.0
-2.9
-1.4 0.3 1.6 2.9,2.6 0.376 1.243 1.34 1.239'1.07ý 1.23 1.05 1.212 1.03 1.200 1.047 1.2 1.326 1.23 0.371 0.8 0.8 1.7 0.1 \\0.1 0.4 \\1.0,
-0.3
-1.2
-3.1
-2.0
-1.7 0.4 0.8 0.8 0.28) 1.0 1.281 1.2451.
1.076 1.308 '.0 1.309 1.
1.27 1.233 1.314 1.044 0.26 0.0 0.0
-2.1
-0.1 0.51 0.7 1.3 1.3 1.4
-0.7
-1.2
-1.0 0.2
-1.6 f-1.5
-5
-6
-7
-8
-9
-10
-11 0.480 1.142 1.0611 1.240r1.24I 1.131 1.
133 1.232 1225r1.06 1.151 0.48*
-1.2
-2.4
-1.9
-0.4,-0.2, 1.4 1.4 1.5,
-0.51 -1.7
_1.6A -2.0
-3.0 12 0.26ý5V 094N 1.153 1.31 1.2 1
1 1.32 1;W1
.3;.2M.
0.94 0.26
-2.2
-3 94
- 1.
1 1.1
-2.2 T-231 -1.9 K 0.2*
0.2 1.
1.3 1
00.8
-. 9 -20
.4
-4
+-I
+-I 4
-4 4
0.26 0.491 1.040 1.213 T.210 1.187 0.71 k.22
- 1. 1.046
.47 0.2W
". 2.0
-1.3 \\0.8*
0.8 0.71,-0.6A -1.1 i'.6 -3.0
_____13 14
'*o0 o.3 0 0'
0.381 0.71 o.27C
-2.6,4 -1.4 0.5 0.8A 0.3 1 -0.5 1 -1.4 15 LII0 Measured Power
% Difference (M-P)/P Measured Location
Serial No. 07-0532/Enclosure/Page 10 of 11 FIGURE 3 INCORE Power Distribution -
74%
MILLSTONE UNIT 3 -
CYCLE 12 R
P N
MI I L
K J
H G
F E
0.287 0.3WO.39 0. 34 0.384ri.371 0.279 0.0 1.9, 1.3 21;.61 0.3k 0.3A 0.4 DB A
0."7f 0.48,3 1.040fl.2111 1.189T1.1711 1.18411.211 1.043 0.49010.27E 1.4 0.1 \\1.5/
1.1
,1.5*
1.1 1.6 0.1 1-3.2 1 -1.8
-1
-2 3
-4 0.272 0.935 1.122 1.281 1.293 1.302'1.264 1.306 1.
1.28'21.1 0.930'.27 2.2 2.0
-2.4 0.1 01 00 [0.0 0.8 [2. 8
-0.2,-34.0
-1.6 0.0, I:
10.494,110 1.039 1.208 1.210 1.1231.31* 1.128 1.244l 1.230 1.0551 1.140 0.491
,,-2.2A,-2.3)
-2.8
-2.3
-2.3
-0.2,--0.5j 0.3 0.2
-0.5
-1.3 I -0.9 0.2 0.27 1.0 1.272 1.2191.25 1.06 1.2 1.0871.
1.07 1.27 1.2 1.28 1.04 0.289
-0.7
-0.8
-0.9
-1.4
-2.4
-2.5
-2.0
-1.5
-1.5
-1.3
-1.2
-0.4 0.5 0.6 0.7 0.37 1.20 1.32 1.25 1.0821.23 1.062 1.22 1..
1.268 1.10 1.241 1.311 1.21 0.380
-0.3 0.6 2.2, 0.9
-0.7
-2.1
-2.1
,-1.81, -0.2 0.4 1.0 0.8 1.5 1
0.8 0.390 1.191 1.3241.1a 1.323 1.081 712
- 0.
1.2971.09 1.31 1.145 1.
91.19 30.
1.83 1.0223ý2.
1.8 1.7 2.2 2.0 0.8
-0.4 1.2 -1.0
-0.2
- 0.
.5 1.8 1.5 1.8 0.8 0..1 1.181 1.29 1.348 '1.12) 1.257 1.0a 0.825 1.005.1.24 1.101 1.33) 1.2 1.1 0.387 2.6 2.4 2.1/
2.2,2.3j 0.6 K0.0
-0.6
-0.3
-0.6
-0.3 0.8 1.71 2.6 2.4 0.395'1.2 1.322 1.145 1.336 1.103 1.322 1.012 '1.27" 1.063 1.
1.127 1.309 1.200 0.39 2.6 2.2 1.5 1.8 1.8 1.7 1.8 0.4
,,-1.9
-2.0 ý-1.0A 0.2 1.0 2.5 2.6 0.378 1.205 1.309 1.2 71.09 1.271 "1.10ý 1.260 1.084 1.232 1.071 "1.22) 1.3021 0.376 0.3 0.3 1.3
-0.2
-0.1I 0.6 \\,1.9" 0.8
-0.1
-2.5
-1.7
-, 1.5,/ 0.5
- 0.
1.1 r0.28A 1.032 1.249 1.M 1.29 1.096 1.33 1.12 1.33 1.082
.27ý 1.228 1.2 1.021 0.27ý
-0.7,, -0.7
-2.4
-0.3 0.1 0.6 1.8 \\1.9 1.9
-0.9
-0.9
-0.
0.7
-2.0 2.2ý
-5 6
7 8
-9
-10
-11 0.484 1.131 1.050 1.225'1.23 1.139 1.33 1.14 1.229 1.2211.0 1.140 0.4
-- 12 1.7
-1.8
-0.9 \\-0.6O 1.2 1.5
-0.7
-1.3
-1.0A -0.8
-24 0.268r0.92 1.12 1.28,1 1.296 1.30T1.271 1.311 1.3001 1.2811 1.153 0.94!f0.271
-2.9 K-3.01. -2.5 k-0.2 2
0.0 0.7 K 0.91 0.7 0.6 0.1 1 0.3 I -0.6 K-2.5, 13 0.2 0.41 1.024 1.185r..18 1.163 1.1831.19511.036 0.4 0.272
-3.21 -2.6
-1.7
-1.1 0..Sj 0.9 0.6
_-0.5/
-0.3,-.4A -1.4
-14 10;27- -0;368 -0,3860-38.-0,38 -0;371 -0,286
,-2.51
-1.1 0.8 0.8 0.5
-0.3
-0.3 D* Measured Power
% Difference (M-P)/P L] Measured Location
Serial No. 07-0532/Enclosure/Page 11 of 11 FIGURE 4 INCORE Power Distribution -
100%6 MILLSTONE UNIT 3 -
CYCLE 12 R
P N
M 2-0.488 k-1.14,
-1.2 L
K J
H G
F E
0.289 0.3851 '.39A 0.1m 0.385-0.37) 0.282
-0.7 1.0,,0.8,,,
1.0 1..0.3 \\0.31 0.4 D
C B
0.44 0.2784-
-3.3 I-1.41 A
I 1
i i _
a
= i I
1.031r1.205 1.173J1.151j 1.16" 1.1991 1.0331
-0.5 k 1.0/1 0.6 k0.7A 0.4 10.9 1 -0.5 1
-- 1
-2
-3
-4 0.27 0.931 1.1181 1.26 1.274 1.283rl.241 1.28 1.A 13.2W 1.1 0.941'.20*
_I.
-1.9 I-2.4
-0.5 -0.5
-01 L-.
00 1.6li-.
I
-"/ -.
04
.8..-.
5 UN
- 0.
IN
.9 11504
'0.40rl.12A 1.034 1.20411.20ý 1.121[ 1.31;1 1.121 1.2391 1.2191 1.0491 1.13110.49:
ý,-2.0,4,,-2.3,A -2.9 1-2.2 1-2.2 1 0.4 r-0.5j 0.0 0.2
-0.9 1 -'1.8 1 -1.3 1-0.2 0.279 1.028 1.261 1.211 1.26 1.075 1.300 1.103 1.30 1.089 1.27 1.219 1.2 1.02 0.2891
-0.7
-1.0
-1.1
-1.5,-2.1,
-2.1
-1.4
-0.9 \\-0.8/
-0.6
-0.9q
-1.0 0.9
-0.9
-0.7 0.37ý 1'.192 "1.W 1.246 1.090 1.25ý 1.084 1.25 1.107 1.28 1.115 1.238 1.28 1.19 0.379
-0.8 0.3 1.9 0.7
-0.5
-. 6/
-1.2
-0.* 7 0.9 1.0 1.5 0.3 0.4 0.3
-0.6 0.392 1.179 1.310,1.15ý 1.3 1.103 1.31 1.02 1.327 1.11 1
1.1461.3 1
0 1.6 1.5 2.0 2.1_
1.2 0.5
-0.2 0.3 1.0 1.9 1.5 1.8 1.4 1.5
-0.5 0.38) 1.16
.27) 1.34 91. 14) 1.283 1.0 0.851 1.032 1.26 1.119 1.3ý1.
1.179 0.395
\\2.1 1.7 \\1.5 2.4 2.7 1.5 1.1 0.4 0.7 0.1 0.5 0.911.8
.9 3.
0.395 1.18 1.301 1.152 1.35 1.127 1.35 1.03 "1.
1.0 1.31 1.13 1.301 1.19 0.40 1.8
,1.6/
0.9 2.3 2.7 2.7 2.9 1.4
-0.9
-1.2
-0.2 0.4 1.3 2.9 A3.
0.379 1.185 1.2 1.23
.10 1.2 1.12 1.279 1.1 1.248 1.083 1.22 1.296 1.201
-0.5
-0.5 0.0 0.3 0,0.5 1.2 2.5 1.2 0.3
-2.0
-1.2 i-1.
1.0 1.1 1.1 0.28 1.026 1.242 12 "1.29 1.107 1.34 1.1
- 1.
- 1.
- 1.
1.2 1.28
- 1.
0.2
-1.0p
-1.0
-2.3 0.2 s0.4 1.0 2.0 L2.3 2.1
-0.4
-0.5
-0.2 0.9
-1.5
-1.4
-5
-6.
-7
-8
-9
-10
-11 0.8 2.6 1
2.04 -1.21 1.**,1 1.13 1.336.14 1.321-1.221-1.06.
1.144 0.499
-1.8
-2.6 1I-2.4 1-1.1 k*-1.0,A 1.0 I 1.4 \\ 1.31
-,0.2 I-0.8 ]-0.7_4
-0.6 1-2.0 12 t
~ -
i- ____
t
____ r -1 I
0.271r 0.92211.11lr 1.265 1.27,1 1.28411.258 1.294 1.28611.26911.150 0.949r0.275
-3.6
_3.5A-3.1 K-0.8!
-0.7 0.0 W0.3M 0.31 0.5 1 -0.21 0.3 1-0.6 K-2.5y 13 I0.27 0.494 1.01111.164*l.161 1.145 1.164r1.177 1.028fO.4 94 0.277 V-3.j5
-2.9
-2.6
-2.0 [-0.2A -0.1
-0.3 F-1.2j -0.8 1k-0.4A -1.4 14
'027101380-386rO.38d03J I036102
- 2. l - 2.1 1 0. 0 o.A 0 1 o-
.3 7 1 -.23
\\-2.8,
-2.1 0.0 K, 0.0j 0.0
-1.3 I-1.0 15 D-0]
Measured Power
% Difference (M-P)/P Measured Location