ML053570273
| ML053570273 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/13/2005 |
| From: | Scace S Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 05-804 | |
| Download: ML053570273 (15) | |
Text
Dominion Nuclear Connecticut, Inc.Millstone Power Station Rope Ferry Road Waterford, CT 06385 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 Dominion-DEC 13 2 Serial No.MPS Lic/MAE Docket No.License No.05-804 RO 50-423 NPF-49 STARTUP TEST REPORT FOR CYCLE 11 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 11.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, Ste u nc Sc ce, Director Nuclear Station Safety and Licensing J- 6a (1.51 Serial No.05-804 Startup Test Report For Cycle 11 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.05-804 Docket No. 50-423 Enclosure I Startup Test Report Cycle 11 Millstone Power Station 3 Dominion Nuclear Connecticut, Inc. (DNC)
Serial No.05-804 Enclosure 1 Page 1 Table of Contents Page 1.0
SUMMARY
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2
2.0 INTRODUCTION
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2 3.0 FUEL DESIGN ...................................................
3 4.0 LOW POWER PHYSICS TESTING .................................................
3 4.1 Critical Boron Concentration
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3 4.2 Moderator Temperature Coefficient
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4 4.3 Control Rod Reactivity Worth Measurements
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4 5.0 POWER ASCENSION TESTING ...................................................
5 5.1 Power Distribution, Power Peaking and Tilt Measurements
... 5 5.2 Boron Measurements
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7 5.3 Reactor Coolant System Flow Measurement
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7
6.0 REFERENCES
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8 7.0 FIGURES ...................................................
8 Serial No.05-804 Enclosure 1 Page 2 1.0
SUMMARY
Low Power Physics Testing and Power Ascension Testing for Millstone Unit 3 Cycle 11 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 11 fuel reload was completed on October 14, 2005.The attached core map (Figure 1) shows the final core configuration.
Reference 6.3 documents that Cycle 11 uses a low leakage loading pattern (L3P) consisting of 73 new Region 13 fuel assemblies, 72 Region 12 once-burned fuel assemblies, and 48 Region 11 twice- burned fuel assemblies.
The 73 feed fuel assemblies, 64 of the 72 once-burned fuel assemblies and all 48 twice-burned assemblies are the Westinghouse 17x17 Robust Fuel Assembly (RFA) design. Eight of the once-burned fuel assemblies are Westinghouse 17x1 7 Next Generation Fuel (NGF) Lead Test Assemblies (LTAs).The 73 Region 11 assemblies are comprised of 37 assemblies enriched to 4.00 weight percent Uranium-235 (w/o U 2 3 5 ) and 36 assemblies enriched to 4.95 w/o U 2 3 .The top and bottom regions of all fuel assemblies in the Cycle 11 core are comprised of a 6-inch annular blanket region enriched to 2.6 w/o U 2 3 5.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 11 contains an insert from the following list of items: 2 secondary sources, 61 RCCAs, and 130 thimble plugs.Subsequent operational and testing milestones were completed as follows: Initial Criticality October 27, 2005 Low Power Physics Testing completed October 27, 2005 Main Turbine Online October 27, 2005 30% Power Testing completed on October 28, 2005 75% Power Testing completed on October 30, 2005 100% Power Testing completed on November 07, 2005 Serial No.05-804 Enclosure 1 Page 3 3.0 FUEL DESIGN The Robust Fuel Assembly (RFA) design comprises 185 out of the 193 assemblies in the Cycle 11 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 IFM's improve the fuel assembly thermal performance and increase the margin to fuel-related design limits.The final 8 assemblies in the Cycle 11 core are Next Generation Fuel (NGF)Lead Test Assemblies (LTA's). 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 ZITLOTM 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 11 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 All Rods Out 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.
Serial No.05-804 Enclosure I Page 4 Summary of Boron Endpoint Results Measured Predicted M-P Acceptance (ppm) (ppm) (ppm) Criteria All Rods Out 2160 2156 4 (23 pcm) +/-1000 (ARO) ____4.2 Moderator Temperature Coefficient Isothermal Temperature Coefficient (ITC) data was measured at the All Rods Out 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 of the predictions were met.The ARO Moderator Temperature Coefficient (MTC) of -0.01 pcmPF was calculated by subtracting the design Doppler Temperature Coefficient
(-1.78 pcmPF) from the measured ARO Isothermal Temperature Coefficient of -1.79 pcm/0 F. The Technical Specification Limit of MTC < +5.0 pcmP°F at ARO Hot Zero Power (HZP) was met.Isothermal/Moderator Temperature Coefficient Results Measured Corrected M-P Acceptance (pcmPF) Predicted (pcmPF) Criteria/O(pcmF) (pcmPF)ARO ITC -1.79 -2.18 +0.39 NA ARO MTC -0.01 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 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).
Serial No.05-804 Enclosure I Page 5 Control Bank Integral Worth Results Measured Predicted M-P % Difference (pcm)(pcm) (pcm) (M-P) / P Control Bank A 828.0 836.3 -8.3 -1.0 Control Bank B 606.5 584.8 21.7 3.7 Control Bank C 860.2 870.2 -10.0 -1.1 Control Bank D 505.2 481.7 23.5 4.9 Shutdown 342.9 341.2 1.7 0.5 Bank A Shutdown 1071.0 1047.4 23.6 2.3 Bank B Shutdown 322.4 309.0 13.4 4.3 Bank C Shutdown 330.0 313.9 16.1 5.1 Bank D Shutdown 59.0 56.4 2.6 4.6 Bank E Totals. 4925.2 4840.9 84.3 1.7 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 29% 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 98% power was performed for INCORE to Serial No.05-804 Enclosure 1 Page 6 Once hot full power equilibrium conditions were map was performed to verify core power distributions limits.EXCORE calibration.
reached, another flux were within the design 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 (FAh), including uncertainties, to their respective limits from each of the flux maps performed during the power ascension.
The most limiting FQ is based on margin to the limit which 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 (%RTP) (MWD/MTU)
Position (%) Tilt (steps)29.2 9.0 216 5.027 1.0022..72.0 34.0 216 4.568 1.0021 100.0 343.0 216 1.027 1.0029 Comparison of Measured FQ to FQRTP limit Power Bumup Measured F 0 FQRIP steady Margin to (%RTP)(MWD/MTU) state limit Transient Limit 29.2 9.0 2.156 4.973 N/A 72.0 34.0 1.890 1 3.491 32.2 %100.0 343.0 1.860 2.600 14.1 %
Serial No.05-804 Enclosure 1 Page 7 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 29.2 9.0 1.413 1.827 1.492 1.912 72.0 34.0 1.391 1.637 1.474 1.713 100.0 343.0 1.362 1.510 1.447 1.580 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 1496 ppm with a predicted value of 1478 ppm. The predicted to measured difference was +106 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 72% rated thermal power was 400,244 gallons per minute (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 Serial No.05-804 Enclosure 1 Page 8 398,401 gpm with a minimum required flow of 372,292 gpm. All Technical Specification limits were met.
6.0 REFERENCES
6.1 SP 31008, Rev. 002-06, "Low Power Physics Testing (IPTE)" 6.2 EN 31015, Rev. 001-00, "Power Ascension Testing of Millstone Unit 3" 6.3 Nuclear Design and Core Physics Characteristics of the Millstone Generating Station Unit 3, Cycle 11 6.4 WCAP-13360-P-A, Revision 1, "Westinghouse Dynamic Rod Worth Measurement Technique" 6.5 NEU-05-36, Letter from W. F. Staley (Westinghouse) to Robert Borchert, "Dominion Nuclear Connecticut Millstone Unit 3 Low Power Physics Tests (LPPT)," dated November 11, 2005.7.0 FIGURES Page 1 Cycle 11 Loading Plan 9 2 INCORE Power Distribution
-29% 10 3 INCORE Power Distribution
-72% 11 4 INCORE Power Distribution
-100% 12 Serial No.05-804 Enclosure 1 Page 9 FIGURE 1 CORE LOADING PATTERN MILLSTONE UNIT 3 -CYCLE 11 R P N M L x J H G F E D I I I I I I I 11B I 11B I 11B 11B llB 1. 1A 1B 1 I L66 L55 L76 L58 L81 L40 L45 C B A 1 I 139 139 119 119 11B L52 11B L69 13B N39 13B N47 13B N56 13B N61 13B N63 13B N49 13B N41 11B L47 11B L71-2 11B 11A 13B 13A 12B 12B 12B 12B 12B 13A 113B 11A 11B L62 L22 N69 N11 M18 1429 M36 M37 M20 N18 N70 L17 L63 3 11B L61 13B N55 12B M21 12B M35 13A N21 12B M60 13A N30 12B M57 13A N31 12C M65 12B M426 13B N73 11B L73_ -4 9oo 11B 13B 13A 12C 13A 12A 13A 12A 13A 12A 13A 12B 13A 13B 11B L70 N42 N10 M68 N36 M01 N02 M16 N04 M13 N13 M31 N25 N43 L48 11A 13B 12B 13A 12A 12B 12C 13A 12B 12B 12A 13A 12B 13B 11B L10 N50 M27 N26 M02 M56 M67 N22 M33 -M63 M08 N23 M17 N51 L68 119 139 12B 12B 13A 12B 12B 12A 12B 12C 13A 12B 12B 13B 119 L74 N57 M34 M54 N05 M40 M59 M10 M53 M71 N06 M51 M43 N66 L80 11B 13B 12B 13A 12A 13A 12A 13A 12A 13A 12A 13A 12B 13B 11B L67 N67 M42 N17 M11 N20 M05 N09 M14 N29 M04 N16 M39 N64 L46 11B 13B 12B 12B 13A 12C 12B 12A 12B 12B 13A 12B 12B 13B 11B L79 N65 M45 M61 N07 M70 M62 M15 M52 M41 N01 M49 M44 N60 L78 11B 13B 12B 13A 12A 12B 12B 13A 12C 12B 12A 13A 12B 13B 11A L50 N52 M28 N15 M07 M58 M38 N34 M66 M55 M09 N33 M19 N46 L23 11B 13B 13A 12B 13A 12A 13A 12A 13A 12A 13A 12C 13A 13B 11B L42 N44 N28 M46 N37 M03 NOS M12 N03 M06 127 M72 N24 N38 LS3-5-6-7-8-9-10-11 11B 13B 12B I 12C 13A I 12B9 13A 12B M64 13A N35 12B 1432 12B M25 13B N54 11B L60 L56 1N4621 M24I M69 I N32 1M50 N14 11B 11A 113B j 13A 12B112B 12B 12B 12B9 13A 113B 11A 11B L49 L07 N68 12 14221M48 1M47 M30 1423 N19 N59 L31 L57 12 13 11B L43 11B L72'13B N45 13B N53 13B N58 13B N72 13B 1N71 13B N48 13B N40 119 L44 11B L64 14 11B L65 11k LO8 11B L77 11B L59 11B L75 11B L51 11B L54 15 00 LEGEND REGION ASSEMBLIES ENRICHMENT l R Region Identifier D Fuel Assembly Identifier 11A 11B 12A 12B 12C 13A 13B 8 40 16 48 8 37 36 4.20 4.70 4.70 4.95 4.95 4.00 4.95 Serial No.05-804 Enclosure 1 Page 10 FIGURE 2 INCORE Power Distribution
-29%MILLSTONE UNIT 3 -CYCLE 11 R P N M[4IA4 k-4.li -4.1 L K J H G F E I I I I I I I I D C I I B A.......0.277 1.1 0.362 0.8 0.381-0.3 0.358-0.6.32)0.268 0.4 I I -I -1 I I 00 1.030-3.9 1.234 1.0 1.18E-0.1 1.1 1.1 80 0.3 1.216 1.2 1 1.059 0.1 0.406-2.2 0.167-3.5 1 2 0.17C 0.439 0.976 1.132 1.32411.277 1.29 1.281 1.33 1.138 0.9 0.432 0.16'.-1.7 -2.0 -2.7 -1.4 0.5 1-0.9 2:8 -0.2 k .6 -0.4 _2. -3.6 .75 i 3 0.41 ,<-0.7,.'0.99s w-0.9w 1.188-1.2 1.241-1.4 1.217-1.5 1.273-0.5 1.276-0.2 1.234 0.2 1.251-0.1 1.194-0.7 0.97E-2.5 0.40E-2.9-I-- 4 0.269 1.067 1.146 1.254 1.20 1.209 1.266 1.234/1.26 1.217 1.21 1.257 1.4 i 1.073 0.275 0.7 0.9 0.4 0.2 -1.2 -1.1 -1.6 ; -1.8 -1.7 -0.5 0.1 -0.1 -0.1 0.1 0.4 03 1.23214 1.248 1.224 124 1 .28213 1.291 1.247 1.218 1.244 1.330 1.2 0.360 1.5 2.5 2.8 1.3 0.1 -1.1 -1.5 -1.8.5 .5 -0.6 -0.3 0.7 0.9 0.9 0.3 0.368 1.207 1.319 '1.30 1.300 1.30 23 1.277 1.304 1/.30 1.206 0.368 2.2 2.5 2.7 \ 2.3 0.9 -0.5 -1. -1.6 -1.4 -1.1 -0.8 1.9 1.3 1.4 0.3 0 1.208 1.33 1.286 /1.27 1.248 1.201 1.200 1.206 1 1.249 1 1.32 "1.20 0.385 1.8/ 2.0 1.9, 1.9 1.62 -0.9 -0.8 -0.8 -0.6 1.2 1.5 1.8 0.8 0.373 1 1.30' 1.302 1.303 1.306 1.246 1.209 1 1.301 1.28 1.292 1.300 1.195 0 1.6 1.9 1.6 1.7 1.2 0.3 -0.6 -0.6 .-0.7 -0.2 1.0 1.2 1.5 0.8 0.360 1.22 1.32 1.250 .23 1.264 1.29 1.244 1.288 1.257 1.233 1 1.327 1.210 0.327 0.3 0.6 0.7 1.2 1.3 0.8 -1.0 -0.9 -1.1 0.2 0.8 0.7 1.4 0.7 0.3.2 1.077 1.158 1.274 122 1.231 1.279 1.24 1.279 1.234 1.231 1.268 1.156 1.055 .2 0. 0.5 0.9 1.3 0. 0.7 -0.8 -0.6 -0.6 1.0 1.2 1.3 1.2 -0.3 -0.4-5-6-7-8-9-10-11 0.42C 0.7 1.012 0.9 1.207 0.3 1.253 0.1 i.23'\, 0.01 1.273 1.257-0.4 1 .27)1.246-0.9 1.272 1.1 1.217 1.2 0.964-3.8 0.406-2.2 12-~ 13 0.169 0.44 0.989 1.13 1.30.0 1.2801.30 1.291 1.322 1.1541 1.018 0.442. .16-1.2 1 .-1.3 0-o5Ai -0.7 1 0.3 .02 -. 0.3* 0.5 1.5 -1.3 ..0.409-1.4 1.043-1.4 1.185-1.4 1 .1 6'1.17211.181 14.21 '<,-0.2~, 1.079 0.7 0.42y ,1 .4,, 0.169-1.2 14-1.0 -0.7 I -I -.1. -4 I -I -I 4. 4 a -0.32C-1.8 0.354k0.37t 0.363 0.3581 0.276-1.7 k-1.6,A -1.1 -0.3 0.7 15I I -I -A. -D Measured Power% Difference (M-P)/P D Measured Location Serial No.05-804 Enclosure 1 Page 11 FIGURE 3 INCORE Power Distribution
-729o MILLSTONE UNIT 3 -CYCLE 11 R P N M L K J H G F E D C Ie I IIer7 & --I--- I -__111 ---- -__V ___D ---- I B A 0.272 0.7 U.36id 0.8' .312<,-O.5,>-.35-0.5 U.;Jb-0.3 1.33/<'1.5v 1.Z5t 1.5_ I 1 I I i-4-4-I -I -t -.t -I -I -0.409 1.017 1.208 1.161 1.163 1.201 1.053 0.416 0.175 0.17\,-3.9,., 0.409-4.0 1 .017-4.1 1.208 0.9 1.161-0.5 41.1 56<1-0.6,2 1.163 0.5 1.201 1.8 1.0532 0.5 0.416-2.1 0.'175-3.8--2 0.179 0.452 0.9691.112 1.277 1.25111.270 1.264l.32 1.132 9 0.443 0.17i-1.6 -2.0 -3.1 -2.4 -1.8 -1.6 -1.6 -0.3 22 -0.1 -. 3.9-I-- 3'0.99A\.-0.5j 1.162-2.2 1.225-2.2 1.224-0.9 1.264-1.3/4.24a 1.279-0.2 1.237 0.2 1.248 0.0 1.182-0.5 0.978-2.2 0.416-2.3-4 0.277 1.058 1.143 1.257 1.211 1.223 1.276 1.250 1.27 1.228 1.22 1.257 1.14 1.063 0.280 1.5 1.0 0.9 0.7 -0.9 -0.8 -1.6 -1.6 -1.6 -0.6 -0.2 0.3 \0.3 0.3 0.0 0.342 1.223 1.33 1.270 1.244 1.2 1.294 1.24 1.300 1.260 1.232 1.254 1.31 1.21 0.364 3.0 3.6 \3.1_ 2.9 0.7 <-0.8 -1.6 -1.9 -1.7 -0.5 -0.1 1.5 1.5 \ 1.5, -0.3 0.378 1.195 1.307 1.31 1.309 1.317 1.253 1.214 1.244 1.292 1.287 1.310 .2 1.191 0.373 3.0 3.3 3.1 .2.3 0.8 -0.5 -1.4 -1.8 -2.1 -1.7 -0.8 2.3 1.8 2.1 -0.3 70.39 1.181 1.306 1.283 1.812912 .1 .2 .51.261 71.28/1'.31) 1.195 0.395 1.5y 1.5 1.2 1.5 1.5 -0.2 -1.1 -0.8 -1.3 -1.3 -0.7 <\2.0, \2.2> 2.8 1.5 0.379 1. 1 .272 1.298 1.31 3 1.319 1.261 1.227 1.25 1.306 1.297 1.296 1.284 1.1 0.3 1.3 \1.4y 0.1 1.3 1.2 0.3 -0.8 -0.7 -1.2 -1.3 -0.2 1.2 1.3 2.0 1.6 0.367 1.205 1.300 1.247 1.24 1.273 1.31 1.259 1.300 1.265 1.244 1.24 1.306 1.191 0.335 0.5 0.7 0.0 1.0 1.1 0.6 -1.0 -1.0 -1.1 -0.1 0.7 0.7 1.1 0.9 0.9 0'O.28 1.07 1.139 1.265 1. .238 1.288 1.26 1.291 1.241 1.23 1.258 1.145 1.049.27 11 1.2 0.0 1.0 ,0.5 02 -.8 0.5 0.6 0.7- 0.8 1.1 I0.1 0.0J-5-6-7-8-9-10-11 0.434 1.9 1.028 2.8 1.196 0.7 1.244-0.3 1i.22p\~-O.5, 1.272-0.7 1.259-0.4 1.242 0.6 1.259 0.5 1.194 0.5 0.967-3.3 0.417-1.9 12 13 0.179 .45 0.993 .1 1.2831 1.262 1.28 1.272 1.302 1.149 1.025 0.458r01 7-0.6 071 -0.7 <0., -0.7 -0.5 0 -0.1 0.2 0.9 2.5 -0.7 -.3?0.420-1.2 1.036-1.1 1.167-1.1 i-0.8.1.155-0.7 1.161-0.5 1.19\<-0.4_, 1.071 1.0 20.43\<2.6,.0.180 0.0 14-S I -I -I 1-4 & -0.326--1.2 0.363-1.1-1 .02 0.371-0.8 0.363-0.5.0.280 1.1 15\ ,__ _ A_ _ _D Measured Power% Difference (M-P)/P D Measured Location Serial No.05-804 Enclosure 1 Page 12 FIGURE 4 INCORE Power Distribution
-100%MILLSTONE UNIT 3 -CYCLE 11 T P N M 01 0.41 k-3.81 -3.9 L K J H G F E D C.I I I I I-. ---I ----V; ----I onn ___v_- ----I I I B A U.Z17 1.1 U.87t 0.8-1.3 U.8b-0.8 1.4_ 4-4-1 I 7 1.021-3.7 1.202.0.9 1.151-0.9 1.146-0.3 1.18918 1.2 1.047-0.2 0.420-2.8 0.1 8-3.7 i -2 0.184 0.459 0.9771 1.137 1.2851 1.239 1.25 1.244 129 1.127 9 0.452 0.17-1.6 -2.3 -3.2 -0.8 -0.4 -1.5 -1.4 -0.9 07 -1.1 -3.8 4.8 1- 3 p0.42),,-1.2>~0/ .99~1.167-1.6 1.243-0.7 1.233-0.8 1.267-0.8 1.25',-0.7 J 1.270-0.2 1.244 0.2 1.240-0.6 1.175-0.9 0.982-2.7 0.422-2.8--4 0.278 1.049 1.140 1.245 1.227 1.22 1.29316 .29 1.234 1.23 1.252 " 1.13 051 0.281 0.0 0.0 0.0 -0.2 -0.5 -0.4 -0.7 -0.8 0. 0.0 0.3 0.0 -1.0 -0.8 -1.1 0.347 1.207 1 1.258 1.239 1 1.300 .26 1.306 1.260 1.238 1.251 1.29 1 0.365 3.0 2.7 <2.5 1.4 0.4 -0.4 -0.5 -0.7 -0.6 0.1 0.5 0.6 0.2 <\0.1, -1.4 0.383 1.180 1.283 1.30i 1.319 1.321 1.257 1.225 1.254 1.304 1.303 1.295 1.26 1.171 0.373 3.0 2.4 2.2 \2.0 1.2 0.5 -0.3 -0.3 -0.6 -0.2 0.1 1.4 0.8, 0.9 -1.6 0.39 1.171 1.28 1.290 .29 1.286 71.231 1.232 1.233 1.28 1.273 1.28 1.29 1.180 0.400 0.8 1.1 0.9 1.7 1.8 ~ 0.8 0.2 0.4 0.3 0.3 0.2 1.1 1.4 1.9 1.5 0.381 1. 1.260 1.299 1.324 1.320 1.264 1.235 1.26 1.318 .30 1.287 1.267 1.171 0.37 0.5 .0.9 0.2 1.7 1.7 1.1 0.2 0.5 0.3 0.3 0.4\ 0.9 1.0 1.6 1.6 0.370 1.191 1.272 1.254 1.24 1.269 /1.31 1.277 1.307 1.269 1.244 41.25) 1.293 1.180 0.339 0.0 0.0 -1.4 0.9 \ 1.1A 0.8 -0.1 0.1 0.1 0.8 0.8 \_0.7 0.8 0.4 0.6 0 11.075 1.144 1.2631. 1.240 1.301 .2 1.300 1.2421 1.262 1.154 1.040 0.27 1.4 1.4 -0.2 0.9 0.5 0.5 -0.2 0.0 -0.2 0.8 1.1 1.1 1.2 -0.9 -1.1-5-6-7-8-9-10-11 0.440 1.4 1.024 1.5 1.188-0.2 1.242-0.5 1.23i\-0.5*1.267-0.7 1.261-0.6'1.271\-0.51 1.251 0.6 1.270 1.4 1.20~1 .62 1.004-0.5 0.424-1.9-~ 12 13 0.18 0.46 0.998 1.13 1.2651 1.236 0.26 1.2481 1.282 1.150 1.0241 0.469r0.18
-1.1 4\1.1 -1 .1 \17-7A~ -1.4 1-1.5 -1. -0.8 1-0.6 0.3 1.5 1-0.2 k2: 0.1 ,,-l.lj 0.427-1.2 1.036-1.2 1.154-1.8/1.13\<-1.7~, 1.139-1.6 1.14E-1.1 1.17@1-l.6y 1.058rK0.43M 0.184-0.2 K 0.9,j -1.1 14 0. 272 0.330-2.1 0.365-1.9'0.38)0.374-1.3 0.364-1.6 0.284 0.0 15-I. -A. -------I -D 0 Measured Power% Difference (M-P)/P Measured Location