ML070650516

Startup Test Report for Cycle 18

ML070650516
Person / Time
Site:	Millstone
Issue date:	02/26/2007
From:	Jordan A Dominion, Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
07-0071
Download: ML070650516 (16)

Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station Dominion-Rope Ferry Road Waterford, CT 06385 FEB 2 6 2007 U. S. Nuclear Regulatory Commission Serial No. 07-0071 Attention: Document Control Desk NSS&L/DF RO One White Flint North Docket No. 50-336 11555 Rockville Pike License No. DPR-65 Rockville, Maryland 20852-2738 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 STARTUP TEST REPORT FOR CYCLE 18 Pursuant to Section 6.9.1.3 of the Millstone Unit 2 Technical Specifications, Dominion Nuclear Connecticut, Inc. hereby submits the enclosed Startup Test Report for Cycle 18.

Should you have any questions about the information provided or require additional information, please contact Mr. David W. Dodson at (860) 447-1791, extension 2346.

Very truly yours, Plant anager - Nuclear

Enclosure:

(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

Serial No. 07-0071 Docket No. 50-336 Startup Test Report Page 2 of 2 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station

Serial No. 07-0071 Docket No. 50-336 ENCLOSURE STARTUP TEST REPORT FOR CYCLE 18 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No. 07-0071/Enclosure/Page 1 Table of Contents

1.

SUMMARY

2

2. INTRODUCTION 3

3. LOW POWER PHYSICS TESTING RESULTS 3 3.1 Unrodded Critical Boron Concentration 4 3.2 Moderator Temperature Coefficient 4 3.3 Control Element Assembly Rod Worth Parameters 5 3.4 Rodded Critical Boron Concentration 5 3.5 Control Rod Drop Time Measurements 5

4. POWER ASCENSION TESTING RESULTS 6 4.1 Power Peaking, Linear Heat Rate and Incore Tilt Measurements 6 4.2 Critical Boron Measurements 7 4.3 Hot Zero Power (HZP) to Hot Full Power (HFP) Critical Boron Difference 7 4.4 Flux Symmetry Measurements 8 4.5 Moderator Temperature Coefficient 8 4.6 Reactor Coolant System Flow 9 4.7 Core Power Distributions 9 4.8 Reactor Coolant System Radiochemistry 10

5. REFERENCES 10

6. FIGURES 10 January 2007

Serial No. 07-0071/Enclosure/Page 2 SUMIMARY The refueling outage preceding the Cycle 18 startup was approximately 44 days, starting on October 7, 2006 and ending on November 19, 2006.

The results of the Millstone 2, Cycle 18 low power physics testing and power ascension testing programs were in good agreement with the core design predictions. All measured parameters were within the review and acceptance criteria of the tests. All Technical Specification Limiting Conditions of Operation (LCOs) were met.

Millstone 2 performed a first time application of WCAP-16011-P-A, "Startup Test Activity Reduction Program." The results of the STAR Program implementation will be submitted in a summary report to the NRC. The report will (a) identify the core design method used, (b) compare the measured and calculated values and the differences between these values to the design method uncertainties and (c) show compliance with the STAR applicability requirements.

January 2007

Serial No. 07-0071/Enclosure/Page 3

2. INTRODUCTION The Millstone 2 Cycle 18 fuel loading was completed on November 6, 2006.

The attached core map (Figure 6.1) shows the final core loading. The subsequent operation/testing milestones were completed as follows:

Initial Criticality November 18, 2006 Low Power Physics Testing Complete November 19, 2006 Turbine On-Line November 19, 2006 30% Power Testing Complete November 19, 2006 69% Power Testing Complete November 20, 2006 100% Power Testing Complete November 28, 2006 The Millstone 2 Cycle 18 core is comprised of 217 AREVA manufactured fuel assemblies.

3. LOW POWER PHYSICS TESTING RESULTS Low Power Physics Testing was conducted at a power level of approximately 2 x 10-2 % power.

January 2007

Serial No. 07-0071/Enclosure/Page 4 3.1 Unrodded Critical Boron Concentration The Critical Boron Concentration (CBC) measured with CEA Group 7 at 148 steps withdrawn and an RCS temperature of 529.0°F was 1574 ppm.

Adjusted to the prediction conditions of Group 7 at 180 steps withdrawn and an RCS temperature of 532°F yields an adjusted, measured CBC of 1588 ppm.

Adjusted, measured unrodded CBC = 1588 ppm Predicted unrodded CBC = 1615 nnm 1615 n -

.. . ... un od

... e . .....

Difference -27 ppm (-219 pcm)

Review Criteria is +/- 50 ppm of the predicted CBC.

Acceptance Criteria is +/- 1000 pcm of the predicted CBC.

Review and Acceptance Criteria met? Yes.

3.2 Moderator Temperature Coefficient The Isothermal Temperature Coefficient (ITC) measurements were performed at a boron concentration of 1574 ppm, an average RCS temperature of 528.9°F, and CEA Group 7 at 148 steps.

The measured ITC at these conditions was +1.40 pcm/°F.

Adjusted to the prediction conditions for an RCS boron concentration of 1602 ppm and an RCS temperature of 532°F yields an adjusted, measured ITC of +1.57 pcm/°F.

Adjusted, measured ITC - +1.57 pcm/0F Predicted ITC -+1.09 Dcm/*F Difference - +0.48 pcm/°F Review Criteria is +/- 2 pcnm°F of the predicted ITC.

January 2007

Serial No. 07-0071/Enclosure/Page 5 Review Criteria met? Yes.

The MTC was determined by subtracting the predicted Doppler Temperature Coefficient at the test conditions from the adjusted, measured ITC. The MTC at these conditions was +0.303 x 10A Ap/°F.

The Millstone 2 Technical Specifications require the MTC be less positive than +0.7 x 10.' Ap/°F for power levels less than 70% power.

Technical Specification limit met? Yes.

3.3 Control Element Assembly Rod Worth Parameters Control Element Assembly (CEA) Rod Worth Parameters were not measured as allowed by WCAP-16011-P-A, "Startup Test Activity Reduction Program."

3.4 Rodded Critical Boron Concentration The Critical Boron Concentration (CBC) measured with CEA Group A inserted was not performed during Cycle 18 startup testing due to application of the STAR Program.

3.5 Control Rod Drop Time Measurements The Millstone 2 Technical Specifications require that all CEAs drop in less than or equal to 2.75 seconds to the 90% inserted position, with RCS conditions at greater than or equal to 515°F and full flow (all reactor coolant pumps operating).

Control rod drop time testing was done at an RCS temperature of 530'F with all 4 reactor coolant pumps operating. The average control rod drop time was 2.22 seconds to 90% insertion, with the fastest and slowest drop times being 2.13 seconds and 2.30 seconds, respectively.

Technical Specification limits met? Yes.

January 2007

Serial No. 07-0071/Enclosure/Page 6

4. POWER ASCENSION TESTING RESULTS 4.1 Power Peaking, Linear Heat Rate and Incore Tilt Measurements The following core power distribution parameters were measured during the power ascension to ensure compliance with the Technical Specifications:

• Total Unrodded Integrated Radial Peaking Factor (FrT ) is the ratio of the peak fuel rod power to the average fuel rod power in an unrodded core. This value includes the effect of Azimuthal Power Tilt.

• Linear Heat Rate (LHR) is the amount of power being produced per linear length of fuel rod.

• Azimuthal Power Tilt is the maximum difference between the power generated in any core quadrant (upper or lower) and the average power of all quadrants in that half (upper or lower) of the core divided by the average power of all quadrants in that half (upper or lower) of the core.

The measurements of these parameters were:

Power Level F 'T Peak Linear Heat Rate Incore Tilt 69% 1.616 9.36 KW/ft 0.0059 100% 1.579 12.87 KW/ft 0.0069 The corresponding Technical Specification limits for all power levels for these parameters are:

• Fr T < 1.69 (Note - larger values of F rT are permissible at less than 100%

power)

• Peak Linear Heat Rate < 15.1 KW/ft

• Azimuthal Power Tilt < 0.02 Technical Specification limit for Fr T met? Yes.

Technical Specification limit for LHR met? Yes.

Technical Specification limit for Tilt met? Yes.

January 2007

Serial No. 07-0071/Enclosure/Page 7 4.2 Critical Boron Measurements Critical Boron Concentration (CBC) measurement was performed at 100%

power at equilibrium xenon conditions.

The CBC measured at 100% power with CEA Group 7 at 180 steps withdrawn and an RCS cold leg temperature of 545. 1F was 1118 ppm.

The cycle average exposure at the time of this measurement was 222 MWD/MTU.

Adjusted to the prediction conditions of 100% power at an All Rods Out (ARO) condition and an RCS cold leg temperature of 545 °F yields an adjusted, measured CBC of 1118 ppm.

Adjusted, measured 100% power CBC = 1118 ppm Predicted 100% Dower CBC 1136 DDm Difference = -18 ppm (-141 pcm)

Review Criteria is +/- 50 ppm of the predicted CBC.

Acceptance Criteria is +/- 1000 pcm of the predicted CBC.

Review and Acceptance Criteria met? Yes.

4.3 Hot Zero Power (HZP) to Hot Full Power (HFP) Critical Boron Concentration Difference The difference in the adjusted measured Critical Boron Concentrations (CBC) performed at HZP and HFP was determined and compared to the design prediction.

Predicted change in CBC from HZP to HFP = 479 ppm Adjusted, measured change in CBC from HZP to HFP = 470 ppm Difference = 9 ppm Review Criteria is +/- 50 ppm of the predicted CBC difference.

Review Criteria met? Yes.

January 2007

Serial No. 07-0071/Enclosure/Page 8 4.4 Flux Symmetry Measurements The core neutron flux symmetry was measured at approximately 30%

power using the fixed incore detector monitoring system. The differences between measured and calculated signals in operable incore detector locations ranged from -0.037 to +0.058 Review Criteria is +/- 0.10.

Review Criteria met? Yes.

The maximum azimuthal asymmetry in the neutron flux from measurements of the variation in incore detector signals from symmetric incore detectors was 5.34%

Review Criteria is +/- 10%.

Review Criteria met? Yes.

4.5 Moderator Temperature Coefficient The Isothermal Temperature Coefficient (ITC) measurements were performed at a power level of 98.5 %, an RCS boron concentration of 1113 ppm, and an average RCS temperature of 570°F, and CEA Group 7 at 180 steps.

The measured ITC at these conditions was -7.015 pcnmiF.

The predicted ITC was determined for a power level of 100%, an RCS boron concentration of 1144 ppm, an average RCS temperature of 570'F, and at an All Rods Out (ARO) condition.

The predicted ITC at these conditions was -7.27 pcnm°F.

The predicted ITC adjusted for 98.5% power, an actual RCS boron concentration of 1113 ppm and an RCS temperature of 569.4°F yields an adjusted, predicted ITC of -7.657 pcm/°F.

Adjusted, Predicted ITC = -7.657 pcnm°F Measured ITC = -7.015 pcm/°F Difference = -0.642 pcm/°F January 2007

Serial No. 07-0071/Enclosure/Page 9 Review Criteria is +/- 2 pcm/°F of the predicted ITC.

Review Criteria met? Yes.

The MTC was determined by subtracting the predicted Doppler Temperature Coefficient at the test conditions from the adjusted, measured ITC. The MTC at these conditions was -0.578 x 10-4 Ap/°F.

The Millstone 2 Technical Specifications require the MTC be less than or equal to +0.4 x 10' Ap/°F for power levels greater than 70% power.

Technical Specification limit met? Yes.

4.6 Reactor Coolant System Flow The RCS flow rate was measured using the secondary calorimetric method, in which the RCS flow rate is inferred by performing a heat balance around the steam generators and RCS to determine reactor power, and measuring the differential temperature across the reactor core to determine the enthalpy rise.

The measured RCS flow rate at 100% power was 384,933 GPM.

When 13,000 GPM is subtracted from the measured flow rate to account for measurement uncertainties, the Minimum Guaranteed Safety Analysis RCS Flow Rate is 371,933 GPM. This value is used to satisfy the Technical Specification surveillance requirement.

The Millstone 2 Technical Specifications require the RCS flow rate to be greater than 360,000 GPM.

Technical Specification limit met? Yes.

4.7 Core Power Distributions The core power distribution measurements were inferred from the signals obtained by the fixed incore detector monitoring system. These measurements were performed at 69% power and 100% to determine if the measured and predicted core power distributions are consistent.

The core power distribution map for 69% power, cycle average exposure of 16 MWD/MTU, non-equilibrium xenon conditions is shown in Figure 6.2.

January 2007

Serial No. 07-0071/Enclosure/Page 10 This map shows that there is good agreement between the measured and predicted values.

The core power distribution map for 100%, cycle average exposure of 224 MWD/MTU, equilibrium xenon conditions is shown in Figure 6.3. This map also shows that there is good agreement between the measured and predicted values.

The Review Criteria for these measurements are:

1. The difference between the measured and predicted Relative Power Densities (RPDs) for core locations with an operable incore detector is less than 0.1.

2. The Root Mean Square (RMS) deviation for radial and axial power distributions between the measured and predicted values is less than 0.05.

Review Criteria met? Yes, for both 69% and 100% power.

4.8 Reactor Coolant System Radiochemistry RCS radiochemistry analysis during the power ascension testing program and during subsequent power operation indicate activity levels with Iodine-131 values of about 7.2 x 10i' pCi/ml. These RCS activity levels show that all failed fuel assemblies have been discharged from the core.

5. REFERENCES 5.1 EN 21004K, "Cycle 18, Low Power Physics Test" 5.2 EN 21004J, "Cycle 18, Power Ascension Testing" 5.3 "Millstone Unit 2, Cycle 18, Startup and Operations Report" 5.4 SP 21010, "CEA Drop Times,"

6. FIGURES 6.1 Cycle 18 Core Loading Map 6.2 69% Core Power Distribution Map 6.3 100% Core Power Distribution Map January 2007

Serial No.07-007 1/Enclosure/Page 11

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~C ore Location SL8 -IVFy1 Fuel Assembly ID Insert ID Figure 6.1 Millstone Unit No. 2 Cycle 18 Core Map January 2007

Serial No. 07-0071/Enclosure/Page 12 X-5 X-6 X-7

[8[10[12[1101i0 0.562 0.569 X-9 X-11 1.210 1.199 X-13 X-155 x-l X-l 6 X-16 X-17 X-17 0.293 0.295

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W4 W-5 W-6 IW-7 W-9 1W-il IW-13 W-1s5 IW-16 WA-17 IW-18 0.381 1.247 INOP I 0.382 1.233

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-0.003 -0.038 1-0.009 S-2 S-3 S-4 S-5 S-6 S-7 S-9 S-11 S-13 S-15 S-16 S-17 S-18 S-19 S-20 1.237 1.175 0.413 1.241 1.167 0.415

-0.004 0.008 -0.002 R-2 R-3 R-4 R-5 R-6 R-7 R-9 R-11 R-13 R-15 R-16 R-17 R-18 R-19 R-20 1.070 1.152 1.054 1.157 P-21 0.016 -0.005 P4-1 N-2 N-3 N4 N-5 NA N-7 N-9 N-11 N-13 N-15 N-16 N-17 N-18 N-19 N-20 1.041 1.004 INOP 1.069 0.998 M-21

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<-1 L-2 L-3 L4 L-5 L-6 L-7 L-9 L-11 L-13 L-15 L-16 L-17 -18 L-19 L-20 1.333 1.162 1166 1.353 1.337 1.167 1.166 1.337 K-21

-0.004 -0.005 0.000 0.016 J-2 J-3 J-4 J-5 J-6 J-7 J-9 J-11 J-13 J-15 J-16 J-17 J-18 J-19 J-20 0.972 1.168 0.998 1.170 H-21

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[A12 [A14 Key F 1 Core Location B10.575 Measured RPD 0.5681 0.0f Calculated RPD Difference Root Mean Square Deviation for all Core Locations = 0.009 Figure 6.2 69% Power Distribution Map All Rods Out, Non-Equilibrium Xenon, 16 MWD/MTU January 2007

Serial No. 07-0071/Enclosure/Page 13 X-5 X-6 X-7

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-0.003 -0.007 -0.001 0.020 J-2 J-3 J-4 J-5 J-6 J-7 J-9 J-11 J-13 J-15 J-16 J-17 J-18 -19 J-20 1.003 1.194 H-i 1.033 1.195 H-21

-0.030 -0.001 G-2 G-3 G-4 G-5 G-6 G-7 G-9 G-11 G-13 G-15 G-16 G-17 G-18 -19 G-20 1.014 1.052 1.033 1.055

-0.019 -0.003 F-2 F-3 F-4 F-5 F-6 F-7 F-9 F-11 F-13 F-15 F-16 F-17 F-18 -19 F-20 1.200 1.195 1.220 1.202 1.194 1.208

-0.002 0.001 0.012 E-2 E-3 4 -5 -6 -7 -9 -11 E-13 -15 -16 -17 -18 -19 -20 0.286 0.297

-0.011 D-4 D-5 0-6 D-7 D-9 D-11 D-13 D-15 D-16 D-17 D-18 D-19 0.369 1.226 1.061 1.330 0.381 1.231 1.055 1.330

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,.009 0 Ke y Axial 15 0575 Core Location Measured RPD Root Mean Square Core 1Average Calculated RPD Difference Deviation = 0.017 Figure 6.3 100% Power Distribution Map All Rods Out, Equilibrium Xenon, 224 MWD/MTU January 2007