ML090580196

Submittal of Startup Test Report for Cycle 13

ML090580196
Person / Time
Site:	Millstone
Issue date:	02/16/2009
From:	Jordan A Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML090580196 (18)

Text

Dominion Nuclear Connecticut, Inc..Dn Millstone Power Station Dn l Rope Ferry Road, Waterford, CT 06385 U.S. Nuclear Regulatory Commission Serial No.09-073 Attention: Document Control Desk MPS Lic/WEB RO Washington, DC 20555-001 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC. FEB 1 6 2009 MILLSTONE POWER STATION UNIT 3 STARTUP TEST REPORT FOR CYCLE 13 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 13.

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

Sincerely, A. J. Ian Site President - Millstone

Enclosure:

(1)

Commitments made in this letter: None K4~Y2)

Serial No.09-073 MPS Unit 3 Startup Test Report For Cycle 13 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I Administrator 475 Allendale Road King of Prussia, PA 19406-1415 Ms. 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

Serial No: 09-073/Enclosure/Page 1 of 16 ENCLOSURE STARTUP TEST REPORT FOR CYCLE 13 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

Serial No. 09-073/Enclosure/Page 2 of 16 Table of Contents Page 1.0

SUMMARY

...................................................................... 3 2.0 INTR O DUCT IO N ................................................................................ 4 3.0 FU E L D E S IGN .................................................................................... 5 4.0 LOW POWER PHYSICS TESTING ................................................... 5 4.1 Critical Boron Concentration .................................................... 5 4.2 Moderator Temperature Coefficient ......................................... 6 4.3 Control Rod Reactivity Worth Measurements ........................... 7 5.0 POWER ASCENSION TESTING ......................................................... 8 5.1 Power Distribution, Power Peaking and Tilt Measurements ......... 9 5.2 Boron Measurem ents ............................................................... 10 5.3 Reactor Coolant System Flow Measurement ............................ 11

6.0 REFERENCES

............................................................ 11 7 .0 F IGUR E S ........................................................................................... . . 12

Serial No. 09-073/Enclosure/Page 3 of 16 1.0

SUMMARY

This report summarizes the Cycle 13 startup testing performed following the completion of the October-November 2008 refueling outage. Preparations for both the refueling outage and Cycle 13 operation included a stretch power uprate (SPU) to allow operation at a rated thermal power (RTP) level of 3650 mega-watts thermal (MWt), or an increase of approximately 7% power. The planning for the SPU included the following:

• On July 13, 2007, Dominion Nuclear Connecticut (DNC) submitted License Arniendment Request Serial No. 07-0450, requesting approval to operate Millstone Power Station Unit 3 at the SPU power level of 3650 MWt. Reference

[6.6]

• Plant modifications were planned to support the SPU. The modifications included items such as the following:

L3 Main feedwater pump turbine replacements 0I Turbine building ventilation to provide additional cooling in the condensate pump area LI Control room emergency ventilation automatic initiation of emergency mode (filtered pressurization) following Control Building Isolation signal L0 Modifications to the main turbine-generator instruments, controls and operating points L3 Modifications to increase the component cooling water piping design temperature between the residual heat removal system and the component cooling water heat exchanger O Various instrumentation and control system setpoint changes O Various piping support modifications O Installation of a Safety Injection Actuation Signal (SIAS) permissive logic that requires both a Safety Injection signal and a low reactor coolant system (RCS) pressure signal to exist before automatically opening the emergency core cooling system cold leg injection valves L3 Rescaling of various instrument loops LI Deletion of the automatic control rod withdrawal capability

• On August 12, 2008, License Amendment No. 242 was issued to support the SPU. Reference [6.7]

Serial No. 09-073/Enclosure/Page 4 of 16

2.0 INTRODUCTION

The Millstone Power Station Unit 3 Cycle 13 fuel reload was completed on November 3, 2008. The attached core map (Figure 1) shows the final core configuration.

Reference [6.3] documents that Cycle 13 uses a low leakage loading pattern (L3P) consisting of 80 new Region 15 fuel assemblies, 76 Region 14 once-burned fuel assemblies, and 37 Region 13 twice-burned fuel assemblies. All 193 fuel assemblies in the Cycle 13 core are the Westinghouse 17xl 7 robust fuel assembly (RFA) design.

The 80 Region 15 assemblies are comprised of 56 assemblies enriched to 4.10 weight percent Uranium-235 (w/o U235) and 24 assemblies enriched to 4.90 w/o U235 .

The top and bottom regions of all fuel assemblies in the Cycle 13 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 113 re-insert fuel assemblies were ultrasonically cleaned during the October-November 2008 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) in the uprated core.

Every fuel assembly in Cycle 13 contains an insert. The inserts consist of 61 rod cluster control assemblies (RCCAs) and 132 thimble plugs.

Subsequent operational and testing milestones were completed as follows:

Initial Criticality November 23, 2008 Low Power Physics Testing completed November 23, 2008 Main Turbine Online November 24, 2008 30% Power Testing completed November 25, 2008 75% Power Testing completed November 27, 2008 93% Power Testing completed November 27, 2008 97% Power Testing completed November 28, 2008 99% Power Testing completed November 29, 2008 100% Power Testing completed December 4, 2008

Serial No. 09-073/Enclosure/Page 5 of 16 3.0 FUEL DESIGN All of the 193 assemblies in the Cycle 13 core are of the RFA design. 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 vane grids and IFMs improve the fuel assembly thermal performance and increase the margin to fuel-related design limits.

The mechanical design of the fresh Region 15 fuel assemblies is the same as the Region 14 fuel assemblies, with the exception that Region 15 incorporates the oxide-coated cladding feature for the first time in Millstone Power Station Unit 3. This new feature consists of a zirconium dioxide (ZrO 2) protective coating, covering a minimum of 4.5 inches of the bottom end of the fuel rod, including a coating over the bottom end plug, the bottom end plug weldment, and a portion of the cladding. The coating provides a hard, wear resistant, surface layer of ZrO 2 for additional debris and grid-to-rod fretting damage resistance, thereby improving fuel reliability.

The Cycle 13 core was designed for an uprated RTP condition of 3650 MWt. The previous RTP for Cycles 1 through 12 was 3411 MWt.

4.0 LOW POWER PHYSICS TESTING The low power physics testing program for Cycle 13 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) 2088 2088 0 (-2.6 pcm) + 1000

Serial No. 09-073/Enclosure/Page 6 of 16 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/degrees Fahrenheit (OF) to the predictions were met.

The ARO moderator temperature coefficient (MTC) of +0.27 pcm/°F was calculated by subtracting the design doppler temperature coefficient (-1.74 pcm/°F) from the measured ARO isothermal temperature coefficient of -1.85 pcm/'F, and adding the delta (A) ITC correction value of +0.38 pcm/°F (AITC corrects the MTC at the measurement conditions to the minimum temperature for criticality value of 551 OF).

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 (pcmi°F) Criteria (pcm/°F) (pcm/IF)

ARO ITC -1.85 -2.31 +0.46 NA ARO MTC +0.27 NA NA MTC < +5.0

Serial No. 09-073/Enclosure/Page 7 of 16 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 is 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)/ P Control Bank A 907.5 866.9 40.6 4.7%

Control Bank B 563.9 588.2 -24.3 -4.1%

Control Bank C 793.1 771.2 21.9 2.8%

Control Bank D 642.9 610.0 32.9 5.4%

Shutdown Bank A 439.3 435.5 3.8 0.9%

Shutdown Bank B 799.8 817.9 -18.1 -2.2%

Shutdown Bank C 354.3 354.2 0.1 0.0%

Shutdown Bank D 342.6 346.6 -4.0 -1.2%

Shutdown Bank E 50.7 52.0 -1.3 -2.5%

Totals 4894.1 4842.5 51.6 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. 09-073/Enclosure/Page 8 of 16 5.0 POWER ASCENSION TESTING Since the power ascension for Cycle 13 included first time operation at an uprated thermal power of 3650 MWt, the standard post-refuel power ascension test program was augmented to include additional testing/evaluations. A specific station procedure was written for the power ascension to the uprated power level. This power ascension testing procedure provided the overall sequence of required activities as well as the types of management reviews and approvals needed to continue the power ascension to the next power plateau.

Testing was performed at specified power plateaus of 30%, 50%, 75%, 93%, 97%,

99% and 100% RTP. Power changes were governed by operating procedures and fuel preconditioning guidelines.

Test activities 1 through 4 described below, are standard power ascension activities performed following all refueling outages. Items 5 through 11 describe the additional testing/evaluations performed to ensure a conservative, deliberate approach to the uprated power level of 3650 MWt.

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%, 74% and 100% RTP using the moveable incore detector system. The resultant peaking factors and power distribution were compared to 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% and 100% RTP.

4. RCS Flow: The RCS flow rate was measured at 93% and 100% 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. RCS AT indication: All RCS AT loops were initially scaled to the uprated power level of 3650 MWt using the Cycle 12 loop AT values (obtained at a RTP level of 3411 MWt). Data from 30%, 50%, 75% and 93% RTP met prescribed acceptance criteria. Data was evaluated at 97% RTP and the loop 3 AT was re-scaled.

6. RCS Temperatures: Data was obtained for the narrow-range RCS loop temperatures. Evaluations for AT and average temperature (TAVG) and reference temperature (TREF) were performed. The data showed that TREF required, re-scaling prior to raising power to the uprated power level.

Serial No. 09-073/Enclosure/Page 9 of 16

7. Turbine 1st stage pressure (TREF): The initial scaling of high pressure (HP) turbine 1st stage pressure was set during the 3R12 refueling outage based on engineering calculations for expected full power HP turbine 1 st stage pressure.

The scaling of TREF was evaluated during the power ascension and required re-scaling at 99% RTP.

8. Plant Walkdowns: At the 93%, 97%, 99% and 100% RTP testing plateaus, walkdown of selected secondary plant systems/components was performed to evaluate the overall response/stability of these systems/components. Acceptable results from these walkdowns were documented as part of the approval process to continue to increase power to the next plateau.

9. Augmented Data Collection/Evaluations: For the areas of nuclear steam supply system (NSSS), balance of plant and key control systems, selected additional monitoring points were evaluated against expected values at the testing plateaus.

Acceptable results from these evaluations were documented as part of the approval process to continue to increase power to the next plateau.

10. Main Feedwater Pump Performance Testing: Due to the replacement of the turbines on the main feedwater pumps, testing of both turbine-driven main feedwater pumps was performed at 55% RTP.

11. Vibration Monitoring Walkdowns: At selected testing plateaus, walkdowns of selected secondary plant systems/components were performed to evaluate the overall response/stability in regards to piping/component vibrations. Acceptable results from these walkdowns were documented as part of the approval process to continue to increase power to the next plateau.

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, 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.

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.

Serial No. 09-073/Enclosure/Page 10 of 16 Summary of Measured Axial Flux Difference and Incore Tilt Power Burnup Rod AFD (%) Incore Tilt

(%RTP) (MWD/MTU) Position (steps) 30.8 9.4 216 4.366 1.0049 74.0 45.9 216 2.478 1.0038 99.9 275.0 216 -0.767 1.0047 Comparison of Measured FQ to FQRTP Limit RTP Power Burnup Measured FQ FQTP steady Margin to Transient

(%RTP) (MWD/MTU) state limit Limit 30.8 9.4 N/A N/A N/A 74.0 45.9 1.785 3.514 33.9%

99.9 275.0 1.853 2.603 13.4%

Comparison of Measured FAh to FAh Limit Power Burnup

(%RTP) (MWD/MTU) FAh FAh Limit 30.8 9.4 1.485 1.916 74.0 45.9 1.453 1.711 99.9 275.0 1.440 1.587 Presented in Figures 2, 3 and 4 are measured power distribution maps showing percent difference from the predicted power for the 30%, 74% 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 1429 ppm with a predicted value of 1411 ppm. The predicted to measured difference was +108 pcm which met the acceptance criteria of

+/- 1000 pcm.

Serial No. 09-073/Enclosure/Page 11 of 16 5.3 Reactor Coolant System 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 approximately 93% RTP was 401,606 gallons per minute (gpm) with a minimum required flow of 379,200 gpm. The RCS flow measurement was re-performed after reaching 100% RTP. The measured flow at 100% power was 402,113 gpm with a minimum required flow of 379,200 gpm. All TS limits were met.

6.0 REFERENCES

6.1 SP 31008, Rev. 003-03, "Low Power Physics Testing (ICCE)"

6.2 SPROC OPS08-3-03, Rev. 000-01, "Implementation of Power Uprate to 3650 MW Rated Thermal Power (ICCE)"

6.3 MP-24-NF-NDR13, Rev. 000, "Nuclear Design and Core Physics Characteristics of the Millstone Generating Station Unit 3, Cycle 13" 6.4 WCAP-13360-P-A, Revision 1, "Westinghouse Dynamic Rod Worth Measurement Technique" 6.5 NEU-08-77, Letter from D. L. Rogosky (Westinghouse) to Robert Borchert, "Dominion Nuclear Connecticut Millstone Unit 3 Transmittal of LPPT/DRWM Final Report," dated December 16, 2008.

6.6 Serial No. 07-0450, Letter from G.T. Bischof (Dominion) to U.S. Nuclear Regulatory Commission, "Dominion Nuclear Connecticut, Inc., Millstone Power Station Unit 3, License Amendment Request Stretch Power Uprate,"

dated July 13, 2007.

6.7 Letter from J.G. Lamb (USNRC) to D.A. Christian (Dominion), "Millstone Power Station, Unit No. 3 - Issuance of Amendment Re: Stretch Power Uprate (TAC No. MD6070)," dated August 12, 2008.

Serial No. 09-073/Enclosure/Page 12 of 16 7.0 FIGURES Page 1 Cycle 13 Loading Plan .............................................................. 13 2 INCORE Power Distribution - 30% ........................................... 14 3 INCORE Power Distribution - 74% ........................................... 15 4 INCORE Power Distribution - 100% ......................................... 16

Serial No. 09-073/Enclosure/Page 13 of 16 FIGURE 1 CORE LOADING PATTERN MILLSTONE UNIT 3 - CYCLE 13 R P N M L K J H G F E D C B A I I I I_* I I I 13B I13 13B 13B 13B 13B 133B 1

N58 N45 371 N48 N72 N40 N50 13E I 14B 15B I15B 15A I15A 15A 15B 15B 1 1411 1 1311 R67 R58 R03 R06 R08 R60 R70 --_ 2 N54 P43 P48 N62 13B 15A 115 15A 14B 15A 14A 15A 14B 15A 15B 15A 13B

--_ 3 N59 R14 R 9 I72 P54 R31 P30 R34 P49 R44 R78 11 N68 14B 15B 14B 14A 14A 14A 15A 14A 14A 14A 114B 1153 14B1 -- 4 P41 R7 9 P37 P02 P15 P06 R45 P08 P20 P33 P38 R66 P47 133 15B 15A 14A 15A 14B 15A 14A 15A 14B 15A 14A 15A 153 133

-5 N53 380 R18 P14 R53 P68 R24 P23 R39 P60 R40 P04 R36 R68 357 13B 153 14B 14A 14B 15A 14B 15A 14B 15A 14B 14A 14B 15B 13B

-6 N43 R61 P52 P31 P61 R37 P65 R30 P58 R33 P59 P35 P51 R62 N42 13B 15A 15A 14A 15A 14B 14A 14B 14A 14B 15A 14A 15A 15A 13B

-7 N64 R02 R17 P09 R43 P71 P27 P75 P18 P72 R29 P10 R26 R16 N65 133 15A 14A 15A 14A 15A 14B 13A 14B 15A 14A 15A 14A 15A 13B 900 -- 8 351 R04 P19 R50 P36 R48 P67 N09 P70 R42 P22 356 P24 311 N52 133 15A 15A 14A 15A 14B 14A 14B 14A 14B 15A 14A 15A 15A 133

-9 N66 312 341 P1 3R38 P62 P16 P64 P13 P73 R47 P05 325 R09 N67 133 153 143 14A 14B 15A 14B 15A 14B 15A 14B 14A 143 153 133 10 N38 363 P50 P17 P74 R52 P57 R23 P76 R32 P66 P29 P56 R57 N44 133 153 15A 14A 15A 14B 15A 14A 15A 14B 15A 14A 15A 153 133 1

1-360 R75 R46 P01 R35 P63 R49 P21 R51 P69 R55 P34 320 376 N49 143 153 143 I 14A 14A 14A 1A 14A 14A 14A I143 153 143 12 P46 373 P39 P32 P28 PI2 R54 P07 P25 P03 P40 R7 P45 133 15iA 153 [15A 143 15AI 14A 15AI 1431 15Aj 153 j15A~ 133 370 310 R69 R321jP53 R27 P26 R322 P55 1R281R71 R130 N6 J - 13 133 143 153 15B I15A 15A 15A 15B 15B R59 14 N73 P44 R65 R64 R07 R01 R13 R77 P42 N55 359 377 133 13B 13B 13B 13B 13B 13B 15 N46 N39 N61 N47 N56 N41 N63 00 LEGEND REGION ASSEMBLIES ENRICHMENT 13A 1 4.00

[D]

FiR Fuel RegionAssembly Identifier Identifier 13B 36 4.95 14A 36 4.70 14B 40 4.95 15A 56 4.10 15B 24 4.90

Serial No. 09-073/Enclosure/Page 14 of 16 FIGURE 2 INCORE Power Distribution - 30%

MILLSTONE UNIT 3 - CYCLE 13 R P N M L K J H G F E D C B A I 0.2 79 0.370'0.39* 0.346 0.358/36) 0.278 -1

-24 2.1 -1.9 -1.4 22 -26 2.5 0.90670.973 1.21" 1.067 1.02" 1.072 1.233 0.9990.6761 0.302 2

ý:3.31 -3.0 -2.6 -2.0j -1.7 4 -1.0 -0.6 07 -0.6 -0.7 0.296 0.866 1.20911.15411.198 1.155 /1.08 1.161 1.24 121 24 08 -3

-2.6 -2.7 1

-2.7-271 -2.6 1 -1.8. 1 5 -0.9 1 jj. 0.2 v -0.8 1 10.66 1.21~ 1.3101.189 1.155 1.113 1.14"j 1.130 1.174 1.20E 1.332 1.2381 0.674 4

\ . -2.5 -1.1 I0.3 0.3 -1.4 ,-0.71 -0.2 1.5 0.8 0.5 -0.4 1-0.4 0.281j 0.994 1.185 1.195/'1.25ý 1.269 1.215 1.168 1.221 1.280 1.26 1.198 1.18 0.995 0.284 5

-1.4 -1.2 -1.2 -0.3 1.3 0.8 0.4 \0.6] 1.7 \1.9 10 -0.4 -0.7 0.37 1.244"1.24) 1.166 1.27271.28) 1.284 1.26ý 1.286 1.286 1.286 1.159 1.22671.23 0.374 -6 0.3

-1.1 .1.1 0.8 1.0 k1.7 2.4 \1.9, 2.2 2.2 2.6 0.6 -0.3 -0.2 -1.1 0.36.3 1.077 1.169 1.13ý 1.236 1.286 1.22" 1.283 1.229 1.29 1.230 1.127 1.17 1.081 0.363 7

-0.8 -0.6 - 1.6 2.2 2.3 2.1 2.8 3.2 2.1-0.5 0.34!ý 1.020 1.09 1.153 1.18ý 1.262 1.28) 1.160 1.301 1.27ý 1.184 1.1 8

-1.4 -,1.2 0.2

-0.9 1.5 2.1 \2.1,/ 2.8 3.6 \2.9,/ 1.8 0.2 -3 .6 -0.9 0.361 '1.07) 1.154 1.137 1.230 1.280 1.220 1.292 1.23) 1.295 1.23 1.143 1.176 1.075 0.36 9

-1.1 -1.4 -1.9 0.7 2.1 2.1 2.1 2.9 \3.7/ 2.9 1.6 1.0 0.4 -0.7 0.367 1.205 1.213 1.16 1.26ý 1.276 1.28" 1.266 1.286 1.285 1.2791.17) 1.268 1.217 0.371 -10

-2.9 -2.6 -1.4 1.0 1.0 1.4 1.8 2.4 2.6 2.1 1.6 1.7 2.6 -1.9 -2.1 0.27A 0.959 1.*185 1.*197 1.25 1.279 1.236 1.17A 1.211 1.259 M1.25 1.211 1.213 0.982 0.27 11 3.8 -4.0 -0.1 0 1.6 1.6 1.1/ 0.5 0.5 0.9.2 -2.4

-. 658 -1.8 1.201 0 1.163 1.13 1.145rl.121 1.157 1.190]3 3. 1.2341 0.6 -- 12

-2.8-1. -10 10.3 k\0.3,ý 0.1 -0.5 \-0.4j 0.4 0.3 04 -1.11 - .

-- 13 0.295rC.6) l. 22 1L'Y 1.2331 162r1T01 1.1571 1.2161 1.1691 1.2341 0.878rO.i9

-3. ý -22 I- 0 1 -. 1 -. 8 1 . -1. -1.1 -1 .4 -07 1 13 L-.

0 .291 0.6611 0.9771 1.212[1.061l 1.0111 1.058r1.2081 0.979r0.6671 0.29E 14

ý-2. 6 -2.8 1-2.9 1-2.33-2.1j -2.31 -2.5 k\-2.3jý

. - i - - ; i - - i

-2.0 k-1.5 i - - ,

-2.0 60.271 0.3671 0.358 0.341 0.3551 0.3681 0.28C 15 2

\-4.2j -3.21 -Z2 r_- .3A -2.71 -2.61 -2.1 I-1 D]

Measured Power

% Difference (M-P)/P Measured Location

Serial No. 09-073/Enclosure/Page 15 of 16 FIGURE 3 INCORE Power Distribution - 74%

MILLSTONE UNIT 3 - CYCLE 13 R P N M L K J H G F E D C B A 0.2 88 0.380O0.31 0 .361 0.37 3 '.387 0.28'7 -1

-117 _-1.6 _-1.3 - 1.1 -1.3 V1.6 _1.7

- - I 0.29 06561 0.9 71 r119m 1.072 1 .03I 1.077 1.216 0.988 0.67307306 2

\,,7.51 '3.2 -1.

7k-l.M -1.2k 101 -0.6 -0. ,

-1.2 -1.6 K

11* .7 .9 3 1.54.2 1.101 jI 11*. 1 1.I0I.L.XDj I.10Uf I.UIIV.01 I u..)UJ

-21.6 j 2.6 1.O~

1.01

-2.9 H I.UI~ 1.17A

-1.8 1-1.8 I. Ivoj j -1.4 k-.j-0.8 k0.9A -0.2 k-Il)A I 3

• -1.4 1.

4 (0O664'1.19ý

<2 j -21.-3 I1.17511.1521 1.273 -0.3 1-0.3 1-1.5 k0.9j 1.1401 1.125[_.117~ -0.4 1.17010.9 1.19411.29311.20710.674 0.4 0. -0.7 -0.6 0.2891 0.985 1.169 1.1831.23) 1.264 1.221 1.180 1.22) 1.274 1.24) 1.1881.17 0.988 0.292 5 0.8 -1.1 -0.5 \0.5/ 0.6 0.4 0.1 \0.1* 1.0 \1.3 0.8 -. 1 0.0 -0.3

/0.38ý 1.225/1.2311661.270 1.27 1.285,1.26) 1.287 1.279 1.280 1.161 1.2 1.21 038 6

-0.3 0.6 11 0.5 0.6 \1.1ý 1.7 \1.4, 1.6 1.5 1.9 0.5 0.1 0.0 -0.3 0.376 1.079 1.172 1.15 1.242 1.286 1.22 1.287 1.236 /1.29g 1.237 1.142 1.17 1.088 0.378 7

-0.5 -0.4 -0.1 OA 1.3 1.5 \ý1.5 1. 23 2. .7 0. .1 03 .

70.36 1.0301.10 1.167.197 1.263 1.2 1.162 1.302/1.27 1.197 1.16 1.11 1.04 0.365 8

-0.2 \1.4 1.5 k,1.3/, 1.9 2.8 \2.3 1.5 0.3 0.3 0.2 0.0 0.375 1.07 1.162 1.148 1,238 1.283 1.223 1.291 1.24 1.296 1.24 1.155 1.183 1.085 0.37 9

-0.5 -09 -1.4 0.5 1.8 1.6 1.2 1.9 \2.8 2.3 \1.5 0.9 0.9 0.2 -0.3 0.378 1.195 1.212 1.161 1.26ý 1.272 1.28" 1.264 1.283 1.28 1.280383 -10

-2.1-. 7 -0.7 0.5 0.6, 1.0 \1. 1 1.6 1.6 1.6 1.4 1.5 2.6 -0.8 -1.0 10.28 0.958 1.162 1.184"1.23) 1.273 1.237"1.18) 1.218 1.261 '1.24 1.205 1.201 0.985/0.28 - 11 0 -0.8 0.4 05j 0.9 -0.9 \0.T 0.2 0.4 \1.2 1.3 1.6 -0.8 -1.0 0.66411.2011 1.2751 1.182'1.15 1.141 1.158 1.13ý 1.159 1.186 1.30 1.215 0.671 -12

-2.1 I-1.21 -1.21 -0.6 \,-0.5, -0.3 -0.6 ,-0.4, 0.3 0.6 \ý0.8 -04 1.

0.304"0.861 1.1981 1.7j 1.217 1.164 1.10~ 1.16411.2101 1 1.16311.2161 0.877r/0.30ý -13 19 8 -1.8 \, 06.7V V -~ j-.

14

\<2.3A 0.6651 K030 0.96911 1.195[l.0611

-2.3 1-2.4 -1.9 k-1.3j 1.0271 -1.3 1.068r1

-1.6 [-1.7A 19ýI 0.975r"067A1

-1.3 k\-07j1 0.306-13

'0.28"I 0.3781 0.373r0.36A 0.371 0.3791 0.28S 15

\-./-2.3 -1.3 \-1.1,J -1.6 1-1.8 -1.4 D1  % Difference Measured (M-P)/P Power Measured Location

Serial No. 09-073/Enclosure/Page 16 of 16 FIGURE 4 INCORE Power Distribution - 100%

MILLSTONE UNIT 3 - CYCLE 13 R P N M L K H I GI FI E D C B A

-0.7 0.3 "0. 71 0.367 0.378 0.381 0.290 -2 6 -1.6 -1.8 -2.0. 2.4

-- 2 r.30 0.657 0.983r.19) 1.078[il.031 1.075 1.1971 0.978 0.6701 0.3081

_3.81 -3.7 -0.7 _1.2, -1. -1.3 -1.4 -1.4 - 1.7 -2.0 -2.2

-2.5 0.3071 -2.7 0.861 -3.5 1.169 1.162 1.2051 1.170r1.101 0.866fr.30E --- 3

-0 .7 -0 .7 -1.2 \-1.3 j 1.1651.20)

-1.2 -0.8/ 1.163

-1.4 119

\-2.1 , -2.1 ,,2.2 1 "0.67 "Or .118"1.258 1.177 1.1561 1.130K1.16"i 1.140 1.162 1.1771 1.279 1.197 0.677 - 4

\-2-0,4 \-2-4 , -1.5 0.4 0.5 -1.2 k-0.5 -0.5 0.7 -0.4 0.2 -1.2 -0.7 0.293 0.982 1.164 1.173 1'.24 " 1.267 1.232 1.1881.23 " 1.273 1.25ý 1.186 1.16 0.988 0.294 -5

-1.3 -1.3 -1.4 -0.8 1.1 1.4 1.0 0.7 0.7 .1.4 1.5 1.2 0.2

.- -0.2 -1.3 "0.38" 1.209 1.23- 1.166 1.275 1.28ý 1.286 1.26 1.288 1.285 1.280 1.155 1.206 1.20ý 0.387 -6

-1.3 -0.4 \1.2 1.0 1.6 \1.7, 2.5 2.1, 2.3 2.0 2.4 0.4 -0.6 -0.6 -1.3 0.381 1.081 1.182 1.15ý 1.255 1.286 1.22 " 1.280 1.236 "1.30 1.251 1.141 1.17 1.086 0.383 -7

-1.0 -0.8 0.3 \0.9" 2.1 2.1 2ý2.2 .2 33 3.7 2. -03 04 -. 5 05 0.37) 1.038 1.11 1.184 1.20ý 1.268 1.27 1.156 1.298 1.28 1.208"1.17W1.11 1.04" 0.373 -8

-0.8 -1.2 -0.4 0.9 2.2 2.0 \1.8 2.4 3.6 \3.1/ 2.4 \0.3./-0.1, ,-0.3, 0.0 0.380 71.07 1.166 1.150 1.239 1.276 1.216 1.281 1.24) 1.297 "1.25 1.162 1.192 1.0880.38 -9

-1.3 -1.3 -1.5 0.5 1.6 1.7 1.7 2.2 \3.7/ 3.0 \2.4 .j 1.4 1.1 -0.2 \-0.3 0.382 1.182 1.197 1.152 1.25) 1.270 "1.28" 1.269 1.284 1.283 1.280/1.17ý 1.260 1.201 0.388 -10

-2.6 -2.5 -1.3 0.2 [,0.2 0.8 \1.7/ 2.1 2.3 1.8 2.0 \\2.11 3.5 -1.1 -1.0 0.28? 0.953 1.163 1.173 1.23 1.265 1.245r1.19A 1.233 1.261 1.24 1.197 1.198 0.983 0.29

-11

-3.7 ,-3.7 -0.6 0.1 0.2 0.8 1.3 \1.4 , 1.1 0.9 1.1 1.3 1.5 -1.2 -1.3 0.662 1.1831 1.2551 1.172r1.141 1.145 1.174r1.14 1.160( 1.174K1.271 1.2001 0.673 12

-2.9 -2.3 1 -1.7 -0.8 K-0.6A -0.1 0.0 K0.11 0.9 0.2 K 0.2,1 -1.2 1 -1.6 0.3060.86 1.182 1.16 1.207 1.170 1.11 1.169 1.201 1.155 1.207 0.877 *0.30ý .-- 13

-2.9 \ -2.7 -2.7 ,-1.1/ 0 -0 . 8 N 7 -1.3 -1.0 -1.3 -0.3 -0.9 _2.2/

'. 3 0.664 0.963 1.186 /1.07" 1.0371 1.069r1.17 0974/06861 0.311 14

\-2.9 -2.9 -3.2 *-2.3 k-1.4j -1.3 -2.1 -2.9 -1.6 -03 -1.3 0.285 0.383 0.381 r0.3651 0.3761 0.3801 0.293 15

\-4.0j -2.3 -1.0 _-1.1/ -2.3 -3.1 -1.7 7 Measured Power

% Difference (M-P)/P DMeasured Location