ML12055A388

Startup Test Report for Cycle 15

ML12055A388
Person / Time
Site:	Millstone  (NPF-049)
Issue date:	02/16/2012
From:	Scace S Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
12-040
Download: ML12055A388 (16)

Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station Dom inion-Rope Ferry Road Waterford, CT 06385 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.

MPS Lic/WEB Docket No.

License No.12-040 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 STARTUP TEST REPORT FOR CYCLE 15 FEB 16 2012 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 15.

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

Sincerely,

/ Stepe~kScace Site Vice President - Millstone

Enclosure:

(1)

Commitments made in this letter: None

Serial No.12-040 MPS Unit 3 Startup Test Report For Cycle 15 Page 2 of 2 cc:

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

ENCLOSURE STARTUP TEST REPORT FOR CYCLE 15 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

Table of Contents Pa1e 1.0

SUMMARY

3 2.0 INTRO D U CTIO N.................................................................................

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 M easurem ents...............................................................

8 5.3 Reactor Coolant System Flow Measurement............................ 9 6.0 R E FER E N C ES.....................................................................................

9 7.0 F IG U R E S...........................................................................................

.. 10 2

1.0

SUMMARY

This report summarizes the Cycle 15 startup testing performed following the completion of the October-November 2011 refueling outage.

2.0 INTRODUCTION

The Millstone Power Station Unit 3 Cycle 15 fuel reload was completed on October 29, 2011.

The attached core map (Figure 1) shows the final core configuration.

Reference [6.3] documents that Cycle 15 uses a low leakage loading pattern (L3P) consisting of 84 new Region 17 fuel assemblies, 85 Region 16 once-burned fuel assemblies, and 16 Region 15 and eight Region 14 twice-burned fuel assemblies. All 193 fuel assemblies in the Cycle 15 core are the Westinghouse 17x17 robust fuel assembly (RFA) design.

The 84 Region 17 assemblies are comprised of 56 assemblies enriched to 4.10 weight percent Uranium-235 (w/o U235) and 28 assemblies enriched to 4.95 w/o U235.

The top and bottom regions of all fuel assemblies in the Cycle 15 core are comprised of a 6-inch annular blanket region enriched to 2.6 w/o U235.

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 109 re-insert fuel assemblies were ultrasonically cleaned during the October-November 2011 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 15 contains an insert. The inserts consist of 61 rod cluster control assemblies (RCCAs), 130 thimble plugs, and two secondary source assemblies. For Cycle 15, the decision to reintroduce two secondary sources was based on the future projected core cycles having lower burned fuel assemblies loaded in front of source range detectors. This may result in lower available neutron source strengths. Cycle 15 will be used to charge the secondary sources for use in future cycles.

Subsequent operational and testing milestones were completed as follows:

Initial Criticality November 20, 2011 Low Power Physics Testing completed November 20, 2011 Main Turbine Online November 23, 2011 30% Power Testing completed November 23, 2011 74% Power Testing completed November 24, 2011 100% Power Testing completed December 12, 2011 3

3.0 FUEL DESIGN All of the 193 assemblies in the Cycle 15 core are the RFA-2 design. This fuel design is the same as Cycle 14 with the following exceptions:

Standardized debris filter bottom nozzle (SDFBN) which eliminates the side skirt flow holes and improves debris resistance Robust protective bottom grid design which increases nominal height of grid and ligament length Low strain radius (LSR) to zirlo mid-grids and intermediate flow mixing grids to lower the strain on the formed features Modification to fabrication process for alloy 718 top nozzle leaf springs to allow for earlier identification of issues Increase in length of the integrated fuel burnable absorber (IFBA) coating from 120 inches to 122 inches in IFBA fuel rods which reduces the potential for predicted minimum FQ margin occurring in the surveillance exclusion zone 4.0 LOW POWER PHYSICS TESTING The Low Power Physics Testing program for Cycle 15 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 Apcrn)

All Rods Out (ARO) 2059 2068

-9 (-53.7 pcm)

+ 1000 4

4.2 Moderator Temperature Coefficient Isothermal temperature coefficient (ITC) data was measured with Control Bank D at 203 steps withdrawn. The review criteria of +/-2 pcm/degrees Fahrenheit (OF) to the predictions were met.

The ARO moderator temperature coefficient (MTC) of -0.41 pcm/°F was calculated by subtracting the design Doppler temperature coefficient (-1.72 pcm/°F) from the measured ARO isothermal temperature coefficient of -2.47 pcm/°F, and adding the delta (A) ITC correction value of +0.34 pcm/°F (AITC corrects the MTC at the measurement conditions to the minimum temperature for criticality value of 5510F).

The technical specification limit of MTC < +5.0 pcm/0F at ARO hot zero power (HZP) was met.

Isothermal/Moderator Temperature Coefficient Results Measured Corrected M-P Acceptance (pcm/°F)

Predicted (pcm/°F)

Criteria (pcm/fF)

(pcm/F)

ARO ITC

-2.47

-3.10

+0.63 NA ARO MTC

-0.41 NA NA MTC < +5.0 5

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 worth is +/-8% of the predicted worth. 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) / P Control Bank A 623.1 612.4 10.7 1.7 Control Bank B 788.6 794.6

-6.0

-0.8 Control Bank C 678.2 697.1

-18.9

-2.7 Control Bank D 662.4 615.8 46.6 7.6 Shutdown Bank A 480.1 472.2 7.9 1.7 Shutdown Bank B 1033.2 1050.1

-16.9

-1.6 Shutdown Bank C 460.5 440.5 20.0 4.5 Shutdown Bank D 456.8 439.6 17.2 3.9 Shutdown Bank E 83.5 86.7

-3.2

-3.7 Totals 5266.4 5209.0 57.4 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.

6

5.0 POWER ASCENSION TESTING Testing was performed at specified power plateaus of 30%, 73% and 100% Rated 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 30%, 73% 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 30%, 73% and 100% RTP.

4. RCS Flow: The RCS flow rate was measured at approximately 93% 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 30% RTP was performed to determine if any gross neutron flux abnormalities existed. At the 30% RTP plateau flux map and again at the 73% 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. 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.

7

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 Power Burnup Rod AFD (%)

Incore Tilt

(%RTP)

(MWD/MTU)

Position (steps) 30.0 8

213 5.735 1.0136 73.2 30.3 216 2.839 1.0098 99.9 176.5 216

-0.124 1.0075 Comparison of Measured FQ to FQ RTP Limit Power Burnup Measured FQ FQRTP steady Margin to Transient

(%RTP)

(MWD/MTU) state limit Limit 30.0 8

N/A N/A N/A 73.2 30.3 1.997 3.552 43.8 %

99.9 176.5 1.999 2.603 23.2 %

Comparison of Measured FAh to FAh Limit Power Burnup

(%RTP)

(MWD/MTU)

Fh F~ h Limit 30.0 8

1.580 1.919 73.2 30.3 1.525 1.714 99.9 176.5 1.506 1.586 Presented in Figures 2, 3 and 4 are measured power distribution maps showing percent difference from the predicted power for the 30%, 73% and 100% RTP 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 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 1392 ppm. The predicted to measured difference was - 42 pcm which met the acceptance criteria of

+/- 1000 pcm.

8

5.3 Reactor Coolant System Flow Measurement The Reactor Coolant System (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 93.4% RTP was 400,167 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. 004-01, "Low Power Physics Testing (ICCE)"

6.2 EN 31015, Rev. 003-02, "Power Ascension Testing of Millstone Unit 3" 6.3 ETE-NAF-2011-0159, Rev.

000, "Nuclear Design and Core Physics Characteristics of the Millstone Generating Station Unit 3, Cycle 15" 6.4 WCAP-13360-P-A, Revision 1,

"Westinghouse Dynamic Rod Worth Measurement Technique" 9

7.0 FIGURES Paqe 1

Core Loading Pattern...............................................................

11 2

INCORE Power Distribution - 30%...........................................

12 3

INCORE Power Distribution - 74%...........................................

13 4

INCORE Power Distribution - 100%.........................................

14 10

FIGURE 1 CORE LOADING PATTERN MILLSTONE UNIT 3 -

CYCLE 15 R

P N

M L

K J

H G

F B

D C

B A

I I I I I I I I

15A 16A 15A 16A ISA 16A 15A R39 S26 RS4 833 R52 904 R24 1

179 16k 149 14:

P42 16A 17B 17B 12 T5 T70 17A 17B 17A T06 T65 T08 17B T72 17B 16A T60 S09 14B P44

-I-------2 14B 17A 17B 17A 16B 16B 16A 169 16B 17A 17B 17A 14B P455

$44 73

$8171885 s

49 T28 TS0 T02 P46 3

16A 906 17B T81 16B 16B 17A S41 S64 T31 16B 17A 16B 551 T43 S54 17A T45 16B 16B S69 S40 17B T82 16A 603 90° ISA 173 17A 16B 17A 16A 17A 16A 17A 16A 17A 16B 17A 17B 15A R38 761 T14 862 T53 823 T20 S15 T38 S32 T39 868 T35 T62 R47 16A 173 16B 17A 16A 17A 16B 17A 16B 17A 16A 17A 16B 17B 16A 907 T73 842 736 S24 T27 S71 T30 S84 T13 819 T42 S48 T74 S34 15A 17A 169 168 17A 16B 17A 16B 17A 16B 17A 16B 16B 17A 15A T32 T09 870 859 726 S74 T22 S55 TS0 S76 T48 S60 882 T10 R50 16A 179 16A 17A 16A 17A 16B 16A 16B 17A 16A 17A 16A 17B 16A 930 766 S20 741 S14 T56 961 827 S50 T40 805 T37 825 T67 928 15A 17A 16B 169 17A 16B 17A 16B 17A 16B 17A 169 16B 17A 15A R56 711 972 952 T47 877 T21 853 T52 S83 719 857 875 705 R37 16k 179 169 17k 16A 17A 16B 17A 16B 17A 16A 17A 16B 17B 16A 822 T75 847 729 831 T46 S79 T34 878 T49 935 T51 846 T69 S08 15k 17B 17A 169 17A 16A 17A 16A 17A 16A 17A 16B 17A 17B 15A T43 763 T55 867 716 S18 T54 S10 T17 829 724 866 TI7 T57 R29

-5 6

-- 7 8

-9 10

-- 11 16A 17B 913 T83 169 1 169 17A 939 S65 T25 16B 17A 16B S58 T

856 17A T32 16B 16B 963 938 17B T77 16A 801 12 13 1,43 17A P47 T0 179 17A 16B T23

$4S 16B 16A 16B

.91.37 980 16B S43 17A 17B T44 779 17A T04 14B P41 14B 16A 17B 17B T64 T76 17A 17B 17A T12 768 T07 17B T71 17B 16A T59 916 14B P43 14 15k 16k 15k 1SA 16A R51 Sll 15A 16A 15A R33 821 R45 16A 936 15A 1R49 15 351 I 811 249 00 LEGEND REGION ASSEMBLIES ENRICHMENT

[R Region Identifier ID] Fuel Assembly Identifier 14B 15A 16A 16B 17A 17B 8

16 37 48 56 28 4.95 4.10 4.10 4.95 4.10 4.95 Page 11

FIGURE 2 INCORE Power Distribution - 30%

MILLSTONE UNIT 3 -

CYCLE 15 R

P N

M L

K J

H G

F E

D C

B 0.3170.4540.43ý 0.477 0.440"0.47 0.331

-3.6

-3'.4

-3'.2

-1.3 04.4 0.6 0.33" 0599 1.161/.26ý 1.1387 27ý 1.164 1.321 1.223 0.639 0.355

\\-4.03

-4.0

-3.5 K-3.4i

-2.9 \\27 1.2 1.6 4

2.0 A

-1

-2

-3 0.34110.94 1.61 1.23~ 1.27911.217 /1.08 1.23 1.35 1.302 130.9810.5 2.120-3.1 1-3.51-3.41-2.6 -2.4 -1.2

2.

2.\\

1.4,

'.610 1.261 10 0.261 1.203 1.1461.11A 1.164 1.213 1.29(

\\-l.0j,,-1.2ý -1.01 0.2 0.2

-2.1 \\-./-0.6 11.3 12.4 1.4031 1.335 0.'641 3.0 j2.61 2.7 4

0.329 1.205 1.277 1.26 1.15ý 0.978 1.033 0.948 1.03 0.996 1.18 1.30 1.31 1.24 0.33 0.0 0.1 0.2 0.3

-0.6

-0.6

-1.7

-1.4

-1.2 1.1 \\25 3.3 3.3 3.4 2.4 0.477 1.322 1.35 1.21 0.983 1.011 0.994 1.00) 1.001 1.025 0.993 1.244 1.3731.35 0.48

-0.2 1.3 \\2.0 1.2

-0.2 \\-1.0

-1.4

-1.1

-0.8 0.4 0.9 3.6 2.6 0.444 1.181 1.270 1.18 1.054 1.001'1.00J 1.011 1.005 0.99 1.050.2

-0.4 0.8 1.6 \\1.51 0.2

-0.8 \\-1.

-1.3

-1.53.7 3.0 2.9 16 "0.49) 1.319 1.11ý 1.143 /0.971 1.008 1.01ý 0.915 1.013 "1.00" 0.961 1.16 1.14 1.35 0.49 0-.2 0.3,0.7 1.0 1.0

-0.6

-1.3

-1.0

-1.1

,-1.0 0.0 o 2.8 1.2 0.446 1.17ý 1.258 1.185 1.06 1.010 1.007 1.015 "1.00 1.001 1.05 1.19 1.28 1.1980.45

-0.2 0.3 0.6 1.3 1.3 0.2

-1.3

-0.9

-1.3

-0.8 0.6 2.2 2.4 2.2 1.3 0.473 1.311 1.328 1.214 0.99J 1.024 11.00 1009 1.007 1.020 0.991 1.21 1.34 1.331 0.48 0.6 0.5 0.3 1.1 1.1 0.3

-0.5

-0.5

-0.1

-0.1 0.6 0.7 1.7 2.0 1.9 0.33 1.212 1.281 1.27 41.16 0.98 1.04510.95 1.04 0.97 1.16 1.27 1.29 1.229

.33 0.6 0.7 0.5 1.1 0.3

-0.1

-0.7 \\-0.8

-0.9

-0.8.10.

1 2.1

-5

-6

-7

-8

-9

-10

-11 0.63(

1.0 1.317 1.366 1.254L1.19* 1.161 1.119r1.151 1.2 0.3

-0.5 r0.71 -0.9

-1.1 k1.2,

1.

1.7

-1.0 1.274r1.3271 1.3051 0.62E 1.1

1.

0.3 10.2 12 13 0.348rO.961 1.29 1.26] 1.301 1.223 1.08A 1.221 1.281 1.2611.3010.961 0.34 0.0 \\0:1q -0.4 X.-1-1

-1.9

-2.2 L-2.j4

-2.3

-2.7

-0.9 0.5

-0.1 0.348' 0.620 1.187 1.276r1.135 1.274 1.136r1.2581 1.176r0.61A 0344

\\0.0j -0.6

-1.4

-2.2 k-3.2j -3.1

-3.1 k-3.5,

-2.2 k-1.Oi -1.1 14 t

t -

I.,-.-~

I. ~

-1 10.321 0.458 0.42910.4711 0.431 0.4541 0.321

\\-1.51 -2.81 -3.8 T-3.9

-3.8

-3.4

-2.4 15 D* Measured Power

% Difference (M-P)/P D Measured Location Page 12

FIGURE 3 INCORE Power Distribution - 74%

MILLSTONE UNIT 3 -

CYCLE 15 R

P N

M L

K J

H G

F E

D C

B 0.320 0.462 0.44ý 0.486 0.446 '.48ý 0.33

-36

-2.5

-. 2.9 -1.3 11 12 0.60 1,1331.237 1.125 1.147 1.290 1A1870.620

ý-1A -,51-3.3

\\,-2.5-,

-2.6 ý,-2.3-,

-0.7 1.7 1.31

.106 A

1

-- 2 0.3451 0.9311t221 1.2011 1.252 1.199 I.07A 1.216'1.32j 1.257212651 0954'03

-2.0

-1.9

-2.7-3.5

-3.5

-3.0 L-2.84 -1.7 L1.81 1.0 0A

.06 1 3

-10.61ýr.

2 41.30 1.2401 1.19 1.151 r.12. 1.160 1.2010.2 1.0311 21106 34

"-11,kI.IA

-. 01-0.2

-0.2

-2.4 k`-2.0,

-1.01 0.6 1.0 1.116119 i

4 0.335 1.179 1.243 1.241.15ý 0.99 1.06 0.983'1.06ý 1.012 1.17 1.270"1.27 1.20 0.34 0.9 0.6

-0.1

-0.2

-1.0

-1.3

-1.8

-1.5

-1.s 0.0 1.2 2.3 2.8 3.0 2.4 0.48ý 1296 1.31 1.211 1.0061.04 1.041 11.0 1.0 1.06 1.011.34 1.31 0.48

,2. 2 1

0

-0.6

-1.1

-1.0

-0.75 -0.4 0.1 0

2.7 3.3 33 2.5 0.456 1.172 1.2561.19ý 1.085 1.04671.05 1.068 1.062 1.04) 1.084 1.211.27 1.19 0.46 0.9 1 1.5 1.5 \\, 1.4 A,0.1

-0.6 \\-0.8

-0.4 -0.4

-0.5 01 3.3 30 3.3 2.0 0.50 1.302/1.127 1.16 31.00) 1.059 1.06ý 0.965 1.07 5 0.91.17 1.14 1.33 0.511

ý0.0 0.9 1.1 1.4 1.1 0.1 \\-0.6

-0.2

-0.2 ý-0.2 0.1 2.5 3.1

3.

2.2 0.453 1.16) 1.250 1.191 1.096 1.055 1.060 1.070 1.06ý 1.048 '1.08 1.20 1.267 1.1910.46 1

1.4 1.2 0.3

-0.6

-0.2

-0.5/ -0.4 0.4 1.9 2.4 3.1 2.2 0.48q 1.285 1.30 1.201 1.01ý 1.05 1.05" 1.059 1.056 1.059 1.016 1.20 1.31 1.30 0.48 1.3 1 1.3 0.4 0.0

-0.3

-0.1 0.1 0.4 0.0 0.4 0.6 1.6 3.0 2.7 0.J33 1.1981 1232 1.

24 3 '1.15ý 1.004 1.07 0.99 1.083 1.00 1.17 1.25 1.268 1.2T10.34 1.8 2 -1.0 0.1 \\.7

-0.8

-0.6

-0.1 0.0

-0.5 1.0 1-2 1.9 3.2 3.0

-5

-6

-7

-8

-9

-10

- 11 0.8

-01.25-0.9 j-1.2227 1.8 13 1.70.13 7A".171 1.0k1.2455 j 0.82.

0.8 1 0.2 1

-0. 1.1.7 k-1.7A -1.3 1-0.7 k-0.7A -0.4 11.0 A

0.

10

-_12 13

_090r941 1.2481.22 1.2691 1.207[7.08f 1.2141.27541.239 11274 0.95 0.

-09 7

~-9 1.0 a-t~2.2 -2.4 Sa

-18.1.7j -0.4 1.01 0.2f1.1 15

,-0.9~,1 -1.01 -0.9

-1.6 ký-2.6,, -2.41 -2.5 k-72.8j,.

-1.6 ký-0.6 -0.9

-~14

'0.33 0.467 0,440*.48 0.441 0.4611 0.321

, 0.0,,, -1.7

-2.7,_-2.8,

-2.6 1-2.7 1-1.8 15

[

Measured Power

% Difference (M-P)IP D Measured Location Page 13

FIGURE 4 INCORE Power Distribution -

100%

MILLSTONE UNIT 3 -

CYCLE 15 R

P N

M L

0.3 4.1-

_,.-37]

3.

-4J K

J H

G F

I I

I I

I E

D C

B A

.... I I

I r --

~I* -

I -

Y -~

I" -

11I 0.46tC'0441] 0.488 0.448r0 48'euss 81-3.1

-3.

-32A

-2.

0.9

^0. 33 0.9 1-1

¶IT~2I i[1.r.224i 1.

1.267 1.163 0.0 0.612

-1.8 I -0.8

+ ~

4-4 I -4

~-4 4-4

-~ 4--I.,-

0.34710.923 1.20 1.171 1.221 1.18 1.07 120129 1228

-2.5

-2.4

-3.4

-4.5

-4.6

-3.3 [-2.8

-2.0 0.8j -0.6

/'1.22i V-1.S, 2

-3

-4

-0.6

'.61'2rk.221.280 1.24 1.05 0

.15T 1.138 1.172 1.216 1.231 1.31] 1.256

\\,-1.9,f, -2.0A -1.41 0.5 0.5

-1.8 \\-1.2, -0.6 0.9 0.2 0.8 0.5 0.633 1.4 0.331 1.153 1.221 1.227r1.16 1.021 1.094 1.011r.091 1.032r/.181 1.26C

.2

0. -. 3 0.6 [,0.3t 0.2

-0.2 0.0 \\0.0A 1.1 [,1.6A/ 2.1 r1.6, 1.18(

1.5 0.3 0.48" 1.272.29" 1.211 1.0261.07" 1.076 1.08*

1.081 1.088 1.038 1.22c 1.310 1.28 0.473 1.5 1.3 1.1 0.8 0.5 \\,0.4 0.9 \\1.2j 1.4 1.3 1.7 2.4 2.0 \\2.0 0.2 0.459 1.159 1.242 71.19ý 1.110 1.079 "1.09") 1.103 1,099"'1.08"( 1.111 1.215 "1.25"* 1.173" 0.45c, 0.4 1.0 1.2 1.6 1.2 1.2 \\1.0 1.4 1.5 1.3 1.4 3.1

,2.1, 2.1 0.4 0.50 1.283 /1.11" 1.173 1.031 1.093 /1.10 0.99 1.10 1.09 1.025 '1.18 1'.13") 1.31ý 0.512

-0.65 0.2 0.6 1.8 [2.0 1.7 \\1.1/

1.3 1.4 \\1.4, 1.4 \\2.7 2.5 2.7 1.6 0.454 /1.14) 1.229 1.205 1.122 1.085 1.096 1.102 1.09 1.08 1.11 1.207 1.254 1.177 0.46

-0.7,,0.0, 0.2 2.3 2.4 1.8 1.2 1.3 \\1.2, 1.3 [1.5, 2.4 2.2 2.5 \\1.5 0.478 1.257 1.269 1.206 1.02 1.081 1.08) 1.092 1.085 1.086 1.034/1.21ý 1.309 1.296 0.493 0.0 0.1

-1.2 0.5 0.6.j 0.7 1.5 1.6 1.8 1.1 1.3

ý1.2, 1.9 3.2 3.1 70.33ý 1.177 1.219 1.23 1.16 1.02 1.103 "1.02 1.10 1.021 1.17 1.24 1.24 1.20 0.34 0.9 1.3

-1.2 0.4

-0.2 0.1 0.5 1.0 0.8 0.0 0.9 0.9 1.1 3.6 L3.6 5

6

-7

-8

-9

-10

-11 0.623 1.230 1.278 1.2128 1.117 1.1501.172 1.2001 1.2391.30

.630

-0.

6

-18

-. 8 *-.8

-0.5

-0.2 k,-0.2j 0.0 0.4 \\0.5, -0.4 11.0 12

____13 0.3511~"~~~I 1227f' 1.252 1.197r, A 1.202 1.251 1.218 1.24d 0.940'.35

-14 1!

1.8

,-2.

-2.5

-2.4,-2.1,

-2.0

-1.9

-1.3

-0.2

-0.6 10.3510.61411.144 1.228LI.111 1.24651 1.117ri.21 0.6110.351

-1.4,J -1.6 1 -t6

-2.2

-2.8

-2.7 1 -2.8 k-3.5

-2.2

-1.0

-1.4 14

'0.33" 0.468 0.443,0.48l 0.444 0.4611 0.327

0.61 -2.1

-3.1 K,-3.0,

-2.8

-3.6

-2.4

- -- 15 D

Measured Power

% Difference (M-P)JP D Measured Location Page 14