ML13212A169
| ML13212A169 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/17/2013 |
| From: | Scace S Dominion Nuclear Connecticut, Dominion |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13212A169 (17) | |
Text
Dominion Nuclear Connecticut, Inc.
Millstone Power Station Or-Dominionll Rope Ferry Road, Waterford, CT 06385 JUL 17 2013 U.S. Nuclear Regulatory Commission Serial No.13-377 Attention: Document Control Desk MPS Lic/WEB RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 STARTUP TEST REPORT FOR CYCLE 16 Pursuant to Section 6.9.1.1 of the Millstone Power Station Unit 3 Technical Specifications, Dominion Nuclear Connecticut, Inc. hereby submits the enclosed Startup Test Report for Cycle 16.
If you have any questions or require additional information, please contact Mr. William D. Bartron at (860) 444-4301.
Sincerely, Step 4dl ce e Site Vice President - Millstone
Enclosure:
(1)
Commitments made in this letter: None
Serial No.13-377 Docket No. 50-423 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I Administrator 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 James S. Kim NRC Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08 C2A One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.13-377 MPS3 Startup Test Report For Cycle 16 bc Page 2 of 2
- Verification of Accuracy
- 1. SP 31008, Rev. 005-01, "Low Power Physics Testing (ICCE)"
- 2. EN 31015, Rev. 003-03, "Power Ascension Testing of Millstone Unit 3"
- 3. ETE-NAF-2013-0037, Rev. 000, "Nuclear Design and Core Physics Characteristics of the Millstone Generating Station Unit 3, Cycle 16"
- 4. WCAP-13360-P-A, Revision 1, "Westinghouse Dynamic Rod Worth Measurement Technique" Action Plan/Commitments (Stated or Implied)
- 1. None
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 1 of 14 ENCLOSURE STARTUP TEST REPORT FOR CYCLE 16 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 2 of 14 Table of Contents Page 1.0 SUM M ARYO.. N.................................... .................................... 3
2.0 INTRODUCTION
......................................................... 3 3.0 FU E L D E S IG N ............................................................................ 4 4.0 LOW POWER PHYSICS TESTING ........................................... 4 4.1 Critical Boron Concentration ............................................ 4 4.2 Moderator Temperature Coefficient .................................. 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 Measurem ents ....................................................... 9 5.3 RCS Flow Measurement .................................................. 9 6.0 R EFER EN C ES ........................................................................... 9 7 .0 F IG UR E S ................................................................................. . . 10
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 3 of 14 1.0
SUMMARY
This report summarizes the Cycle 16 startup testing performed following the completion of the April-May 2013 refueling outage.
2.0 INTRODUCTION
The Millstone Power Station Unit 3 Cycle 16 fuel reload was completed on May 4, 2013. The attached core map (Figure 1) shows the final core configuration. Reference [6.3] documents that Cycle 16 uses a low leakage loading pattern (L3P) consisting of 85 new Region 18 fuel assemblies, 84 Region 17 once-burned fuel assemblies, and 24 Region 16 twice-burned fuel assemblies. All 193 fuel assemblies in the Cycle 16 core are the Westinghouse 17x1 7 robust fuel assembly (RFA-2) design.
The 85 Region 18 assemblies are comprised of 53 assemblies enriched to 4.10 weight percent Uranium-235 (w/o U235 ) and 32 assemblies enriched to 4.95 w/o U 2 3 5 . The top and bottom regions of all fuel assemblies in the Cycle 16 core are comprised of a six inch annular blanket region enriched to 2.6 w/o U 2 35 . Placement of the new fuel assemblies in the designated fresh fuel assembly locations was made in a random fashion in order to prevent power tilts across the core due to systematic deviations in the fresh fuel composition.
The 108 re-insert fuel assemblies were ultrasonically cleaned during the April-May 2013 refueling outage. The purpose of the ultrasonic fuel cleaning was to remove adhered crud (primarily nickel and iron-based deposits) from the surface of fuel rods that have previous core exposure in order to reduce the probability of occurrence of crud induced power shift (CIPS).
Every fuel assembly in Cycle 16 contains an insert. The inserts consist of 61 rod cluster control assemblies (RCCAs), 130 thimble plugs, and two secondary source assemblies. The decision to reintroduce two secondary sources in Cycle 15 was based on the future projected core cycles having lower burned fuel assemblies loaded in front of source range detectors resulting in lower available neutron source strengths.
Subsequent operational and testing milestones were completed as follows:
Initial Criticality May 17, 2013 Low Power Physics Testing completed May 18, 2013 Main Turbine Online May 19, 2013 24% Power Testing completed May 19, 2013 74% Power Testing completed May 20, 2013 100% Power Testing completed May 28, 2013
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 4 of 14 3.0 FUEL DESIGN All of the 193 assemblies in the Cycle 16 core are of the RFA-2 design. This fuel design is the same as Cycle 15, with the following exceptions:
9 Fuel clad material has been changed from Zirlo to Optimized Zirlo 4.0 LOW POWER PHYSICS TESTING The low power physics testing program for Cycle 16 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 .Acceptance Measured Predicted M-P eria (ppmr) (ppm) (pp*m) Cr)
All Rods Out (ARO) 2039 2035 +4 (-25.2 pcm) + 1000
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 5 of 14 4.2 Moderator Temperature Coefficient Isothermal temperature coefficient (ITC) data was measured with Control Bank D at 196 steps withdrawn. The review criteria of +/-2 pcm/degrees Fahrenheit (OF) to the predictions were met.
The ARO moderator temperature coefficient (MTC) of +0.22 pcm/°F was calculated by subtracting the design Doppler temperature coefficient (-1.73 pcm/°F) from the measured ARO isothermal temperature coefficient of -1.95 pcm/ 0 F, and adding the delta (A) ITC correction value of +0.44 pcm/OF (AITC corrects the MTC at the measurement conditions to the minimum temperature for criticality value of 551°F). The technical specification limit of MTC < +5.0 pcm/°F at ARO hot zero power (HZP) was met.
Isothermal/Moderator Temperature Coefficient Results Corrected Acceptance
- Measured (pcm/OF) Predicted , M-P pmO) .. Criteri Criteria-(pcm/F) pct 0 (pcm/(F)
_____________ _______ (pcm/ F) ________ (pcm/0 F)
ARO ITC -1.95 -2.60 +0.65 NA ARO MTC +0.22 NA NA MTC < +5.0
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 6 of 14 4.3 Control Rod Reactivity Worth Measurements The integral reactivity worths of all RCCA control and shutdown banks were measured using the DRWM technique. The review criteria of 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).
Control Bank Integral Worth Results Measured Predicted M-P % Difference (pcm), (pcm) (pcm) (M-P) I P Control Bank A 722.3 728.4 -6.1 -0.8 Control Bank B 636.3 620.2 16.1 2.6 Control Bank C 737.9 753.0 -15.1 -2.0 Control Bank D 610.2 576.7 33.5 5.8 Shutdown Bank A 479.3 473.7 5.6 1.2 Shutdown Bank B 938.7 952.5 -13.8 -1.4 Shutdown Bank C 422.5 404.5 18.0 4.4 Shutdown Bank D 407.1 395.0 12.1 3.1 Shutdown Bank E 82.1 78.8 3.3 4.2 Totals 5036.4 4982.8 53.6 1.1 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.
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 7 of 14 5.0 POWER ASCENSION TESTING Testing was performed at specified power plateaus of 24%, 74% and 100%
reactor thermal power (RTP). Power changes were governed by operating procedures and fuel preconditioning guidelines.
Thermal-hydraulic parameters, nuclear parameters, and related instrumentation were monitored throughout the power ascension. Data was compared to previous cycle power ascension data and engineering predictions, as required, at each test plateau to identify calibration or system problems. The major areas analyzed were:
- 1. Core performance evaluation: Flux mapping was performed at 24%, 74%
and 100% RTP using the moveable incore detector system. The resultant peaking factors and power distribution were compared to technical specification (TS) limits to verify that the core was operating within its design limits. All analysis limits were met and the results are summarized in Section 5.1.
- 2. Nuclear instrumentation indication: Overlap data was obtained between the intermediate and power range nuclear instrumentation channels.
Secondary plant heat balance calculations were performed to verify the nuclear instrumentation indications.
- 3. Incore/Excore Calibration: Scaling factors were calculated from flux map data using the single point calibration methodology. The nuclear instrumentation power range channels were re-scaled at 24%, 74% and 100% RTP.
- 4. Reactor Coolant System (RCS) Flow: The RCS flow rate was measured at approximately 90% RTP using a secondary calorimetric heat balance for each loop using the steam generators as the control volumes. The calculated RCS flow rate met the TS requirements and is reported in Section 5.3.
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 TSs.
A low power flux map at approximately 24% RTP was performed to determine if any gross neutron flux abnormalities existed. At the 24% RTP plateau flux map and again at the 74% map, data necessary to perform an excore-to-incore calibration via the single point methodology, was obtained. Per TS Surveillance 4.3.1.1, Table 4.3-1, Functional Unit 2, Note 6, a flux map at approximately 100% RTP was performed for an excore-to-incore calibration.
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 8 of 14 The 100% RTP 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 (FAh),
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 TS limits were met and no abnormalities in core power distribution were observed during power ascension.
Summary of Measured Axial Flux Difference and Incore Tilt
~Rod Power., Burnup R.o
- 'P6sition (%)7Incore Tilt
(%RTP), (MWD/MTU) (steps) AFD '_, __,_'_.._
24.2 5.2 216 3.550 1.0107 73.7 27.0 216 2.234 1.006 99.9 343.9 216 -0.885 1.0056 Comparison of Measured FQ to FQ RTP Limit Power Burnup Measured FQ FORTP steady Margin to
(%RTP) (MWD/MTU) state limit TransientLimit 24.2 5.2 N/A N/A N/A 73.7 27.0 1.8861 3.528 45.8 %
99.9 343.9 1.8983 2.603 27.06 %
Comparison of Measured FAh to FAh Limit Power Burnup ,,,F h , Um
(%RTP) (MWD/MTU) F:Ah FzhLimit 24.2 5.2 1.547 1.947 73.7 27.0 1.470 1.711 99.9 343.9 1.444 1.586
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 9 of 14 Presented in Figures 2, 3 and 4 are measured power distribution maps showing percent difference from the predicted power for the 24%, 74% and 100% RTP plateaus. From this data, it can be seen that there is good agreement between the measured and predicted assembly powers.
5.2 Boron Measurements Hot full power ARO boron concentration measurements were performed after reaching equilibrium conditions. The measured ARO, hot full power, equilibrium xenon, boron concentration was 1400 ppm with a predicted value of 1373 ppm. The predicted to measured difference was - 163 pcm which met the acceptance criteria of +/- 1000 pcm.
5.3 RCS Flow Measurement The RCS 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:
" RCS 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 TS Surveillance 4.2.3.1.3, the RCS flow was measured within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 90% RTP. The measured flow at 90.8% RTP was 399,976 gallons per minute (gpm) with a minimum required flow of 379,200 gpm. All TS limits were met.
6.0 REFERENCES
6.1 SP 31008, Rev. 005-01, "Low Power Physics Testing (ICCE)"
6.2 EN 31015, Rev. 003-03, "Power Ascension Testing of Millstone Unit 3" 6.3 ETE-NAF-2013-0037, Rev. 000, "Nuclear Design and Core Physics Characteristics of the Millstone Generating Station Unit 3, Cycle 16" 6.4 WCAP-13360-P-A, Revision 1, "Westinghouse Dynamic Rod Worth Measurement Technique"
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 10 of 14 7.0 FIGURES Paqe 1 Cycle 16 Core Loading Pattern 11 2 INCORE Power Distribution - 24% 12 3 INCORE Power Distribution - 74% 13 4 INCORE Power Distribution - 100% 14
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 11 of 14 FIGURE 1 CORE LOADING PATTERN MILLSTONE UNIT S - CYCLE 16 R P N N L K J K a F N D C B A 1StI I1t I 1t I itIl tlI t li 16A I 1A 17A 17A 17" .16k I I [m
-1 636 sI T44 Tr9 TIe s02 121 1 51 19B 19A LOB 1 9& jGB L a 1 7A 2 o11 T56 v55 v75 v02 v3 "0a v77 V57 TSO SAO 1B 159 183 O1 7B LiA 17ALit AS 17B liltIO l it8B A 4-3 81 v79 IE jv65 ij T62 1715 1 v37i viA J.rGIV6v6oJ v9 0 17A. LOB 1iA 17Bl 17 lit l LOA It 17A . 17 17 inB 17A ___
-- 4 r22 V71 TO 3 T7i TI7 TI v38 T09 T54 TSO TOt v2 T30 l6t 1St 1S 173 LOA I 7s 1i 17i IRA li7 19 1t 1 IRA 189 16A
--5 62a VVi vt7 T 74 v20 71 T65 v26 T7i V30 r92 v52 v59 a22 l6A, LOB t7B 17A 17s lat lit l0t 17A Itt 17 17A 1.7B 18B 1SA
-6 8021 VG4 754 T19 T69 v12 T42 v42 T36 V41 T5 TV7 T59 v74 S01 lit LOA 1A litA 1It 17A I&A 1A 1SA 17A l8t 17A I A i la 17A --
T2t 705 V27 712 V14 T25 VI0 rI1 VII T732 v8 T07 VI1 Vol T55 liL LOB lit lit 17B lOA 17 1tA 17 iLO liB IDA 17 laB 17A
-- g T53 V62 T41 739 TE6 V40 T27 V73 TA9 3V7 Ti7 V29 T73 V73 r24 liA i1,. LOA lit 1St lit 18A lit LOt 1iA ll 1it 16A l8Ax lit
-9 T35 Vi2 V23 TOE V24 T31 Vol0 46 V5 T745 V21 TOO V22 V09 T23 1?A l8t lit lit lia 1St 17A 1tA it7 ISA 17 17A 17B 1B lt
- 10 803 V15 759 T4 T74 Vt T74 V734 T29 v31 Ti3 T2 T60 73. 0O0 19A LOt LOA lit 10A l7i itt lit LOA lit 181.A 17i iat 18i IA 1
1-sit 760 751 7 V70I T72 V17 n6a Vi9 T70 VAS T7 V73 V54 530 1it lIs* 17A 1iB 17.A 1A 17B 17A 17A 1SAL 17A I17A T 17B -- _ 12 nT3 74 TO&t9 TIAO T0S V44 T1 2970 T02 v69 T52 1SA 19B 189 LOt I 17Bn 1 1{1& n 0t I[si fia Its [ 16-B --_ 13 Boa jVol v7701411 T57J Vi I rT41 7259 I T3 V49vto67 v6 v :3i I6B l7jL lit OIB iea 1StO 1St lBs 17A lit la 14 039 T21 v21 I6v79 IvOS 76 v oi 'Vt7VS vSE r:40 1n0t ICA I IA 174 7 I 17A 1 7A :12 A 15 9ý33 809 T14 Tic T15 L12 s2G 00 LEGEND REGION ASSE*MLINS fNRICMCfl lSt 20 4.10 F Region Identifier 16a 4 4.95 Fuel Assembly Identifier 17A 56 4.10 172 29 4.96 53 4.10 19S 32 4.95
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 12 of 14 FIGURE 2 INCORE Power Distribution 24%
MILLSTONE UNIT 3 - CYCLE 16 R P N M L K J H G F E D C B A I
0.297 0.36960.45 0.474 0.45810.38ý 0.312
' ' ' ' ' I 1
1 -2.3 -1.1 -1.5 -1.7 -0.9 \1.9j 2.0 0.29ý 0.595 1.113'1.16 1.11971.23 1.140 1.206 1.169 0.620 0,310 2
--2.0 -0.9 -11 -08 04 24 2041.0 0.3 0.3051 0.94411.306 1.199 1.232 1.237L1.10I 1.257 1.30 1.262"1.35 0.9600.30ý -3
-1.3 1 -1.3 1 -1 .2-2.2 -2.1 -1.5 j-1.2j -0.2 2.8/ 1.9 0.
11.3E 1.217 1.073 1.124 '.19) 1.138 1.091 1.244 1.255 1.338 0.61 E -- 4 0.2 0.6 0.6 -0.3 I. O.Oj 0.7 1.8 1.9 1.7 1.2 1.1 0.307 1.154 1.241 1.231'1.20") 1.196 1.188 1.198 1.19" 1.215/1.22 1.236/1.24 1.159 0.308 -5 0.3 0.7 0.2 0.8 -0.1 -0.1 -1.6 -1.0 -0.9 1.3 1.72.0 1.3 70.38 1.20371.30 1.0931.211 1.141 1.016 1.09 1.038 1.176 1.218 1.0911.285 1.19 0.377 -6 2.1 \2.7, 2.0 1.9 1.0 -1.0 -2.1 -,1.7, 0.0 1.4 1.8 2.2 2.1 2.1 1.1 0.470 1.162 1.300/1.5) 1.218 1.018 1.13ý 0.966 1.154 1.03 1.206 1.1571.28 1.160 0.4671 -7 1.7 2.4 3.2 2.4/ 0.8 2.67 -3.1 -1.0 -0.2 -0.1 2.7 2.1 2.5 1.3 0.49 1.280'/1.15 1.228 1l.22 1.090 0.96 1.021 0.981 1.10 1.211 1.22 1 1.28 -8 1.7,/l 2.6 ý3.3,, 2.4 \.1.4 . -2.4 \-3.4/ -3.6 -1.6 \-1.2 0.1 2.1 2.5 3.0 2.1 0.4691.16) 1.294 1.13811.199 1.019 1.132 0.964 12 1018 129 7 -9 1.7 \ý2.5/ 3.0 1.0 1 -0.7 -1.8 -2.9 -3.3 -3.3 -1.9 0.4, 2.3 2.6 3.2 22 0.372 1.171 1.285 1.059 1.18 1.145 11.02 1.092 1.013 1.141 1.20971.08 - 10
-0.3 0.0 2.1 - 0.8 -1.3 -1.4 -2.2 -2.4 -1.6 0.8 1.0 3.3 0.5 0.3 0.29 1.121.2201 1.201 /1.20N 1.194 1.204"1.20 1.206 1.192 1.21 1.24011.27411.122 0.30 -11
-2.3 -2.1 -0.5 -0.7 -0.1 -0.4 -0.3 -0.7 -0.1 -0.4 1.2 1.6 2.8 -2.1 \2,0 0.591 1.272 1.215 1.226 /'1.07* 1.133 1.197 '1. 12A 1.064 1.217 '1.24~ 1.324 0.593 12
-3.0 -3.7 -1.5 0.4 0.3 -0.2 -0.3 0.6 -1.0 -3.4 13
-4.6 j-j4.
0.292L0.91 1.'297 1.24
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"0.2 9ý 0.5941 1.1221 1.157r_.121 1.2361 1.11 81.4 1.2 51 0.2 9
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-0.9 -1.2 _1.6A -1.7 0.25. 14 0.365 0.456r0.47ý 0.454 0.366 0.299 15
\ý-3.9/ -2.7 -1.3 k-1.5i -1.5 -1.9 -1.6 D-0 Measured Power
% Difference (M-P)/P Measured Location
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 13 of 14 FIGURE 3 INCORE Power Distribution - 74%
MILLSTONE UNIT 3 - CYCLE 16 R P N M L K J H S F E D C B SI I I I I I I 0.2e98 .37 .4}g A0a84r 0.489 0.38 0.317 -i1
-32 -1.3 _1. 1 -1.41 -0.6 k2.1 2.3 1.077,*.1, -2 221 1.127 1.. 1.t0 1.180 1.1m0f
-3.1 -1.4 -10 0.2 23 1.4 a071 7 0.3091
-0.
0-30510,P171 12571 1.161 1.2021 1.221150ý1 -3
-t.9
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-.5 -3 6.30 (LOe 1.27~j1 12911 1.193 1.07! 1.134r1.201 1.145 1.089 1.21 1.2041.2.80 0.608 -4 0.3 -0.5 -0.6 k-0.4V 0.2 1.0 0.7 0.3 0.1 0.3 0.313 1.125 1.205 1.2(05( 0~.122.11119.1 1.9 1.202 1.211 121@"1,.1,* t.216 121 1.21 1.207 1.20 1.219 1.1G.309 1.0 0.5% -0.5 -0.2 0o.7 -0.8 -1.3 -1.0 -1.0 0.4 0.7 0.8 0.0 0. 0-3 "1.30 1.179 ý1276 1.090 1.218 1.171 1.057 1.13 1.073 1.195 1.227 1Q89 1.257 1.1 0.380 -c
,,2.9,/ 2.2 , 1.8ýý 1.1 A -0.2S -1.5 -1.3 -0.1 1.0 1. 513 1.3 1.3 0.3 U.463 1A151 1.28171.18 1.237 1.055 1.19 1.025 1.203, 1.07 1.231 71"127 1.148 0A74 -7 2.3 2.3 2.3 1.8) 0.7 -0.8 -1.3 -1.5 -0.4 0.4 0.3 2.8 2. 2.3 0.6 0.49 1.260 1.15 1-236 1.24 1.144 1.02 1.083 1.038 1.14 1.235 123 115 12 0.503 -8 1 22.2 2.4ý 2.1 1.5 -0.7 -1.2 -1.5 -0*5 -. 3 0.3 .1.4 2 2 0.478 1.14 1.278 1.153 1.228 1.070 1.200 1.030( 1.18 1.062 "1.23 UAL -g 1.6 ,_20, 2.2 1.1 V0.1 -0.3 -0.7 -1.1 -1.7 -1.1 0.8 2.3 2.8 3.4 2
.0.382 1.159 1,257 1.0841.1 1.174. 1.0 1.142 1.080 1.172 1.221 1.08) 1.291 1.181 0.389 -10 0.8 1 0.9 1.3 1 -1.0 -0.* -a .6 -0.9 -1.2 -0.G 0.8 1.0 3.5 2.3 2.1 11.1801 1.1881.19 1.2061 1227, j.23 1. 120. 1.227 1.247 1.128.31 -11 0.3ý 0.5 -1.8 -0.9 -0.54G -0.1 0..2 0.4 0.1_ 1.3ý 1.7 3.0 0.8 0.8
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<-:1.2.4-1.81 -0.s k-o0-Sj -131-2 -1.9 H
F-1 Measured Power
% Difference (M-PYP Measuremd Location
Serial No.13-377 MPS3 Startup Test Report Cycle 16 Enclosure, Page 14 of 14 FIGURE 4 INCORE Power Distribution - 100%
MILLSTONE UNIT 3 - CYCLE 16 R P N ML# K . H G F E D C B A S I I I I I I 0.297[ 0.375. 45 048I047f.4'.39 0.321 -1
-4.r -2l ,.25 -0o-B082'. 28 0.30 0.59 1. - -31.t11 1-4fl211 1.124 1.16B 1.1141a570. 8
-28 -4.4 -2.4 -2.1 -1.4 -0.2 1.7 0.5 13 0-3G41 09111-22811.138 1.1731 1222 1-T0 1.241 124 1 42 091
-19 030 -- 3
-2.6262.9 -4.5 -4.5 -2.2 -14 -10 0- -0. 1. 1
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ý0.3A 1.17f1.2577 1.088 1.2211 1.19ý 1.014 1.17) 1.099 1.221 1.237 1.083 1.2 41.15 .382 -6 1.9 1.9 2.9 1.4 1.1 02 -0.1 0.1 1.3 2.1 2.5 1.2 0.8 0.7 -0.3 01.490 1.152 1.2821.16 S.73 1.255 1.093 1.23 o) 1 01 ,1.o 1.2155 1.2391.10 1 1.172 127 1.14 -7 2.5 2.3 12.3 2.1 1. 0.7 0.3 0.2 1.0 9 1.5 12.7 17 1.7 0.0 "0.5iý 1.ý254 ý1.14) 1.250 1.26 1.183 1.00 1.129 1.0681 1.13 1.255 1.25 1.14 1.28 0.50B -8 12 1.8 . 2.4 _2.1) 0.9 0.2 0 .48. . 1.8 -2.4 2.2 2.8/ 2.0 0.482 1.14 1.283 - ~~~ 6,,-' 1.244 1.157 1.094 1.241 1.063 1.221ý ~ _ - 1.037 (1.25) 1.176 1-288 1.159 GA.4 -. 9 1_6, 1.84I 1.4 0.6 0.8 1.1 0.4 -0.5 0.2 1. 2.9 2.6 2.9 2.1 0.382 1.142 1.228103 120 1.195 109 1.74 1.03 1.198 1.227 1.09 1.23 1.174 0.393 -10
-0.3 -0.2 1 0.0 -0.7 -0.8 -0.1 0.7 0.2 -0.2 0.0 1.8 1.8 4.0 22 2.1 0U. 3 1' 1.099 1.175 1.178 1.19 1.210 1.247 1.24 1.240 1.208 1 1.21 1213 1.238 1.110, -11
-0.32 -0.3 1 -1.4 -0.7 -0.2/ 0.2 0.8 0.93 0.8 0.1 1.4 1.7 2.9 0.8 0.6
-___12 G.5881 1.193ý 1.1471 1.164(1.06 1.1481 1.22815.1441.7119 1.19, 126-3l 0.599
-3.0 -5.5 -3.0 -0.8 -0.6 OA GA4 0.5. 0.2 0.8 0.8 -0.9 -1.8 029 227Y
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-. 30-. 15' V-;1-2.3 -1.3 k-1.0)-1.5 -3.4 -2.9 DMeasured t%Difference (M-PVP Power D Measured Location