ML082170286

Transmittal of Startup Test Report for Cycle 19

ML082170286
Person / Time
Site:	Millstone
Issue date:	07/24/2008
From:	Price J Dominion, Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
08-0443
Download: ML082170286 (16)

Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station ij7DominionW Rope Ferry Road, Waterford, CT 06385 I JUL 2 4 2008 U. S. Nuclear Regulatory Commission Serial No. 08-0443 Attention: Document Control Desk NSS&L/GWJ 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 19 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 19.

Should you have any questions about the information provided or require additional information, please contact Mr. William D. Bartron at (860) 447-1791, extension 4301.

Very truly yours, rice Vice resident

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 Ms. C. J. Sanders Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738

Serial No. 08-0443 Docket No. 50-336 Startup Test Report Page 2 of 2 NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring and Radiation Division CT Department of Environmental Protection 79 Elm St.

Hartford, CT 06106-5127

Serial No. 08-0443 Docket No. 50-336 ENCLOSURE STARTUP TEST REPORT FOR CYCLE 19 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No. 08-0443/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 June 2008

Serial No. 08-0443/Enclosure/Page 2

1.

SUMMARY

The refueling outage preceding the Cycle 19 startup was approximately 39 days, starting on April 6, 2008 and ending on May 16, 2008.

The results of the Millstone 2, Cycle 19 low power physics testing and power ascension testing programs were in 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.

Implementation of the Startup Test Activity Reduction (STAR) Program for Millstone 2 Cycle 19 has been accomplished in accordance with the steps outlined in WCAP-16011-A-P, Rev. 0 for (1) core design, (2) CEA lifetime, and (3) fuel fabrication. The STAR Applicability requirements for refueling have been accomplished for CEA coupling verification and startup testing. The application of the STAR Program allowed for the elimination of control rod worth measurements from the startup physics testing.

June 2008

Serial No. 08-0443/Enclosure/Page 3

2. INTRODUCTION The Millstone 2 Cycle 19 fuel loading was completed on May 7, 2008. The attached core map (Figure 6.1) shows the final core loading. The subsequent operation/testing milestones were completed as follows:

Initial Criticality May 15, 2008 Low Power Physics Testing Complete May 15, 2008 Turbine On-Line May 16, 2008 30% Power Testing Complete May 16, 2008 69% Power Testing Complete May 17, 2008 100% Power Testing Complete May 21, 2008 The Millstone 2 Cycle 19 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.

June 2008

Serial No. 08-0443/Enclosure/Page 4 3.1 Unrodded Critical Boron Concentration The Critical Boron Concentration (CBC) measured with CEA Group 7 at 150 steps withdrawn and an RCS temperature of 528.0°F was 1566 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 1579.1 ppm.

Adjusted, measured unrodded CBC = 1579.1 ppm Predicrtd iinrodded CBC = 1601.0 nnm Difference = -21.9 ppm (-178 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 1566 ppm, an average RCS temperature of 529.83°F, and CEA Group 7 at 150 steps.

The measured ITC at these conditions was +1.00 pcm/°F.

Adjusted to the prediction conditions for an RCS boron concentration of 1589 ppm and an RCS temperature of 532°F yields an adjusted, measured ITC of +1.15 pcm/°F.

Adjusted, measured ITC = +1.15 pcmI0 F Predicted ITC = +0.69 Dcnm°F Difference = +0.46 pcm/°F Review Criteria is +/- 2 pcm/°F of the predicted ITC.

June 2008

Serial No. 08-0443/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 +0.260 x 10A Ap/°F.

The Millstone 2 Technical Specifications require the MTC be less positive than +0.7 x 10-4 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 19 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. All drop times were within Technical Specification requirements. 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.

June 2008

Serial No. 08-0443/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 FT Peak Linear Heat Rate Incore Tilt 69% 1.655 9.61 KW/ft 0.0070 100% 1.612 13.44 KW/ft 0.0062 The corresponding Technical Specification limits for all power levels for these parameters are:

• F r 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 F met? Yes.

Technical Specification limit for LHR met? Yes.

Technical Specification limit for Tilt met? Yes.

June 2008

Serial No. 08-0443/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 544. I°F was 1101 ppm.

The cycle average exposure at the time of this measurement was 150 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 1102 ppm.

Adjusted, measured 100% power CBC = 1102 ppm Predicted 100% Dower CBC 1118 pDm Difference = -16 ppm (-125 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 = 483 ppm Adjusted, measured change in CBC from HZP to HFP = 477 ppm Difference - 6 ppm Review Criteria is +/- 50 ppm of the predicted CBC difference.

Review Criteria met? Yes.

June 2008

Serial No. 08-0443/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 -0.032 to +0.023 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 5.37%

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 98.98 %, an RCS boron concentration of 1101 ppm, and an average RCS temperature of 569.91°F, and CEA Group 7 at 180 steps.

The measured ITC at these conditions was -7.879 pcm/°F.

The predicted ITC was determined for a power level of 100%, an RCS boron concentration of 1118 ppm, an average RCS temperature of 570'F, and at an All Rods Out (ARO) condition.

The predicted ITC at these conditions was -8.02 pcm/°F.

The predicted ITC adjusted for 98.98% power, an actual RCS boron concentration of 1101 ppm and an RCS temperature of 569.91°F yields an adjusted, predicted ITC of -8.214 pcm/°F.

Adjusted, Predicted ITC = -8.214 pcm/°F Measured ITC = -7.879 pcm/°F Difference = -0.335 pcm/°F June 2008

Serial No. 08-0443/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 -0.664 x 10-4 Ap/°F.

The Millstone 2 Technical Specifications require the MTC be less than or equal to +0.4 x 10-4 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 383,176 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 370,176 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 12 MWD/MTU, non-equilibrium xenon conditions is shown in Figure 6.2.

This map shows that there is agreement between the measured and predicted values.

June 2008

Serial No. 08-0443/Enclosure/Page 10 The core power distribution map for 100%, cycle average exposure of 29 MWD/MTU, non-equilibrium xenon conditions is shown in Figure 6.3.

This map also shows that there is 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 3.3 x 10' 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 19, Low Power Physics Test" 5.2 EN 21004J, "Cycle 19, Power Ascension Testing" 5.3 "Millstone Unit 2, Cycle 19, Startup and Operations Report" 5.4 SP 21010, "CEA Drop Times,"

5.5 WCAP-16011-P-A Revision 0. "Startup Test Activity Reduction Program",

February 2005 5.6 M2-EV-08-0013, Rev 0, "Application of the Startup Test Activity Reduction (STAR) Program for Cycle 19," May 1, 2008

6. FIGURES 6.1 Cycle 19 Core Loading Map 6.2 69% Core Power Distribution Map 6.3 100% Core Power Distribution Map June 2008

Serial No. 08-0443/Enclosure/Page 11

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Serial No. 08-0443/]Enclosure/-Page 12 K(-5 K-5

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Serial No. 08-0443/Enclosure/Page 13 0197 1 97

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- U*, 1 IKey I Core Location Axial 10.5261 Measured RPD Root Mean Square Ctore Average 05201 Calculated RPD Difference Deviation = 0.017 Figure 6.3 100% Power Distribution Map All Rods Out, Non-Equilibrium Xenon, 29 MWD/MTU June 2008