ML16033A469

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Startup Test Report for Cycle 24
ML16033A469
Person / Time
Site: Millstone Dominion icon.png
Issue date: 01/15/2016
From: Daugherty J
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
15-594
Download: ML16033A469 (16)
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Text

Dominion Nuclear Connecticut, Inc.

Rope Ferry Rd., Warerford, CT 06385 Dominion Mailing Address: P.O. Box 128 JAN 15 2016 Waterford, CT 06385 dora.corn U.S. Nuclear Regulatory Commission Serial No.15-594 Attention: Document Control Desk MPS Lic/WEB R0 Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT. INC.

MILLSTONE POWER STATION UNIT 2 STARTUP TEST REPORT FOR CYCLE 24 Pursuant to Section 6.9.1.3 of the Millstone Power Station Unit 2 (MPS2) Technical Specifications, Dominion Nuclear Connecticut, Inc. hereby submits the enclosed Startup Test Report for Cycle 24.

If you have any questions or require additional information, please contact Mr. Thomas G. Cleary at (860) 444-4377.

Sincerely, Joh R.Duherty Site Vice President - Millstone

Enclosure:

(1)

Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I Administrator 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Richard Guzman NRC Senior Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08 C2 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

  • L

Serial No.15-594 MPS2 Startup Test Report For Cycle 24 Enclosure Enclosure Millstone Power Station Unit 2 Startup Test Report for Cycle 24

Serial No. 15-594/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 ConcentrationDifference 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 11
6. FIGURES 11 6.1 Cycle 24 Core Loading Map 12 6.2 69% Core Power Distribution Map 13 6.3 100% Core Power Distribution Map 14 November 2015

Serial No. 15-594/Enclosure/Page 2 1.SUMIMARY The Millstone Power Station Unit 2 (MPS2) refueling outage preceding the Cycle 24 startup was approximately 35 days, starting on October 3, 2015 and ending on November 7, 2015.

The results of the MPS2, Cycle 24 low power physics testing and power ascension testing programs were in agreement with the core design predictions.

Measured parameters were within the review and acceptance criteria of the tests. Technical Specification Limiting Conditions of Operation (LCOs) were met.

Implementation of the Startup Test Activity Reduction (STAR) Program for MPS2 Cycle 24 has been accomplished in accordance with the steps outlined in WCAP-16011-A-P, Rev. 0 for (1) core design, (2) Control Element Assembly (CEA) lifetime, and (3) fuel and CEA fabrication. The STAR Applicability requirements for refueling have been accomplished for core verification, 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.

November 2015

Serial No. 15-594/Enclosure/Page 3

2. INTRODUCTION The MPS2 Cycle 24 fuel loading was completed on October 23, 2015. The attached core map (Figure 6.1) shows the final core loading. The subsequent operation/testing milestones were completed as follows:

Initial Criticality November 6, 2015 Low Power Physics Testing Complete November 6, 2015 Turbine On-Line November 7, 2015 30% Power Testing Complete November 7, 2015 69% Power Testing Complete November 9, 2015 100% Power Testing Complete November 20, 2015 The MPS2 Cycle 24 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.

November 2015

Serial No. 15-594/Enclosure/Page 4 3.1 Unrodded Critical Boron Concentration The Critical Boron Concentration (CBC) measured with CEA Group 7 at 168 steps withdrawn and a reactor coolant system (RCS) temperature of 529.3°F was 1492 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 1509 ppm.

Adjusted, measured unrodded CBC = 1509 ppm Predicted unrodded CBC = 1505 ppm Difference = +4 ppm (+34 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 1492 ppm, an average RCS temperature of 529.6°F, and CEA Group 7 at 168 steps.

The measured ITC at these conditions was +0.448 pcmI°F.

The predicted ITC of +0.040 pcmI°F for an RCS boron concentration of 1505 ppm and an RCS temperature of 532°F, adjusted for measured conditions, yields an adjusted, predicteded JTC of -0.109 pcmI°F.

Measured ITC = +0.448 pcm/°F Adjusted. predicted ITC = -0.109 pcm/°F Difference = +0.557 pcmI°F Review Criteria is +/-+2 pcmI°F of the predicted ITC.

November 2015

Serial No. 15-594/Enclosure/Page 5 Review Criteria met? Yes.

The Moderator Temperature Coefficient (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 +0.19 x 10-4 Ap/°F. The MPS2 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 CEA Rod Worth Parameters were not measured as allowed by WCAP-16011-P-A, Revision 0, "Startup Test Activity Reduction Program."

3.4 Rodded Critical Boron Concentration The CBC measured with CEA Group A inserted was not performed during Cycle 24 startup testing due to application of the STAIR Program.

3.5 Control Rod Drop Time Measurements The MPS2 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 535.5 °F with all four reactor coolant pumps operating. The average control rod drop time was 2.15 seconds to 90% insertion, with the fastest and slowest drop times being 2.00 seconds and 2.24 seconds, respectively.

Technical Specification limits met? Yes.

November 2015

Serial No. 15-594/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 FrT Peak Linear Heat Rate Ineore Tilt 69% 1.565 9.36 KW/ft 0.0066 100% 1.576 12.88 KW/ft 0.0057 The corresponding technical specification limits for all power levels for these parameters are:

  • FrT -* 1.69 (Note - larger values of FrT are permissible at less than 100%

power)

  • Peak Linear Heat Rate _*15.1 KW/ft
  • Azimuthal Power Tilt <_0.02 Technical Specification limit for FrT met? Yes.

Technical Specification limit for LHR met? Yes.

Technical Specification limit for Tilt met? Yes.

November 2015

Serial No. 15-594/Enclosure/Page 7 4.2 Critical Boron Concentration Measurements 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 544.7°F was 1040 ppm.

The cycle average exposure at the time of this measurement was 270 Megawatt Days per Metric Ton Uranium (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 1040.3 ppm.

Adjusted, measured 100% power CBC = 1040.3 ppm Predicted 100% power CBC= 1036.4 ppm Difference +3.9 ppm (+32 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 CBC performed at HZP and HFP was determined and compared to the design prediction.

Predicted change in CBC from HZP to HFP = 468.6 ppm Adjusted, measured change in CBC from HZP to HFP = 468.2 ppm Difference = 0.4 ppm Review Criteria is +/-+50 ppm of the predicted CBC difference.

Review Criteria met? Yes.

November 2015

Serial No. 15-594/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 -0.033 to +0.044.

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 3.09%

Review Criteria is _+10%.

Review Criteria met? Yes.

4.5 Moderator Temperature Coefficient The ITC measurements were performed at a power level of 99.03 %, an RCS boron concentration of 1040 ppm, and an average RCS temPerature of 569.60°F, and CEA Group 7 at 180 steps.

The measured JTC at these conditions was -8.273 pcnI°F.

The predicted ITC was determined for a power level of 100%, an RCS boron concentration of 1049 ppm, an average RCS temperature of 570.0°F, and at an ARO condition.

The predicted JTC at these conditions was -8.520 pcmI°F.

The predicted ITC adjusted for 99.03% power, an actual RCS boron concentration of 1040 ppm and an RCS temperature of 569.60°F yields an adjusted, predicted ITC of -8.582 pcmI°F.

Adjusted, Predicted ITC = -8.582 pcmI°F Measured ITC = -8.273 pcmI°F Difference = -0.309 pcmI°F Review Criteria is +/- 2 pcnil°F of the predicted ITC.

November 2015

Serial No. 15-594/Enclosure/Page 9 Review Criteria met? Yes.

The MTC was determined by subtracting the predicted Doppler Temperature Coefficient at the test conditions from the measured ITC.

The MTC at these conditions was -0.70 x 10-4 Ap/°F. The MPS2 Technical Specifications require the MTC be less than or equal to +0.4 x 104 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 391,180 gallons per minute (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 378,180 GPM. This value is used to satisfy the technical specification surveillance requirement.

The MPS2 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 20 MWDIMTU, non-equilibrium xenon conditions is shown in Figure 6.2. This map shows that there is good agreement between the measured and predicted values.

November 2015

Serial No. 15-594/Enclosure/Page 10 The core power distribution map for 100%, cycle average exposure of 204 MWD/MTU, non-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 approximately 2.2 x 10.4 gCi/ml. These RCS activity levels show there are no failed fuel assemblies resident in the core.

November 2015

Serial No. 15-594/Enclosure/Page 11

5. REFERENCES 5.1 EN 21004K, "Cycle 24, Low Power Physics Test" 5.2 EN 21004J, "Cycle 24, Power Ascension Testing" 5.3 ETE-NAF-2015-0121, Rev. 0, Attachment A, "Millstone Unit 2, Cycle 24, Startup and Operations Report," October 2015 (Areva NP, Inc. Proprietary).

5.4* SP 21010, "CEA Drop Times" 5.5 WCAP-16011-P-A Revision 0. "Startup Test Activity Reduction Program,"

February 2005 5.6 ETE-MP-2015-1144, Rev 0, "Application of the Startup Test Activity Reduction (STAR) Program for Cycle 24," October 31, 2015

6. FIGURES 6.1 Cycle 24 Core Loading Map 6.2 69% Core Power Distribution Map 6.3 100% Core Power Distribution Map November 2015

Serial No. 15-594/Enclosure/Page 12

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Serial No. 15-594/Enclosure/Page 13

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Serial No. 15-594/Enclosure/Page 14

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Dominion Nuclear Connecticut, Inc.

Rope Ferry Rd., Warerford, CT 06385 Dominion Mailing Address: P.O. Box 128 JAN 15 2016 Waterford, CT 06385 dora.corn U.S. Nuclear Regulatory Commission Serial No.15-594 Attention: Document Control Desk MPS Lic/WEB R0 Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT. INC.

MILLSTONE POWER STATION UNIT 2 STARTUP TEST REPORT FOR CYCLE 24 Pursuant to Section 6.9.1.3 of the Millstone Power Station Unit 2 (MPS2) Technical Specifications, Dominion Nuclear Connecticut, Inc. hereby submits the enclosed Startup Test Report for Cycle 24.

If you have any questions or require additional information, please contact Mr. Thomas G. Cleary at (860) 444-4377.

Sincerely, Joh R.Duherty Site Vice President - Millstone

Enclosure:

(1)

Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I Administrator 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Richard Guzman NRC Senior Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08 C2 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

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Serial No.15-594 MPS2 Startup Test Report For Cycle 24 Enclosure Enclosure Millstone Power Station Unit 2 Startup Test Report for Cycle 24

Serial No. 15-594/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 ConcentrationDifference 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 11
6. FIGURES 11 6.1 Cycle 24 Core Loading Map 12 6.2 69% Core Power Distribution Map 13 6.3 100% Core Power Distribution Map 14 November 2015

Serial No. 15-594/Enclosure/Page 2 1.SUMIMARY The Millstone Power Station Unit 2 (MPS2) refueling outage preceding the Cycle 24 startup was approximately 35 days, starting on October 3, 2015 and ending on November 7, 2015.

The results of the MPS2, Cycle 24 low power physics testing and power ascension testing programs were in agreement with the core design predictions.

Measured parameters were within the review and acceptance criteria of the tests. Technical Specification Limiting Conditions of Operation (LCOs) were met.

Implementation of the Startup Test Activity Reduction (STAR) Program for MPS2 Cycle 24 has been accomplished in accordance with the steps outlined in WCAP-16011-A-P, Rev. 0 for (1) core design, (2) Control Element Assembly (CEA) lifetime, and (3) fuel and CEA fabrication. The STAR Applicability requirements for refueling have been accomplished for core verification, 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.

November 2015

Serial No. 15-594/Enclosure/Page 3

2. INTRODUCTION The MPS2 Cycle 24 fuel loading was completed on October 23, 2015. The attached core map (Figure 6.1) shows the final core loading. The subsequent operation/testing milestones were completed as follows:

Initial Criticality November 6, 2015 Low Power Physics Testing Complete November 6, 2015 Turbine On-Line November 7, 2015 30% Power Testing Complete November 7, 2015 69% Power Testing Complete November 9, 2015 100% Power Testing Complete November 20, 2015 The MPS2 Cycle 24 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.

November 2015

Serial No. 15-594/Enclosure/Page 4 3.1 Unrodded Critical Boron Concentration The Critical Boron Concentration (CBC) measured with CEA Group 7 at 168 steps withdrawn and a reactor coolant system (RCS) temperature of 529.3°F was 1492 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 1509 ppm.

Adjusted, measured unrodded CBC = 1509 ppm Predicted unrodded CBC = 1505 ppm Difference = +4 ppm (+34 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 1492 ppm, an average RCS temperature of 529.6°F, and CEA Group 7 at 168 steps.

The measured ITC at these conditions was +0.448 pcmI°F.

The predicted ITC of +0.040 pcmI°F for an RCS boron concentration of 1505 ppm and an RCS temperature of 532°F, adjusted for measured conditions, yields an adjusted, predicteded JTC of -0.109 pcmI°F.

Measured ITC = +0.448 pcm/°F Adjusted. predicted ITC = -0.109 pcm/°F Difference = +0.557 pcmI°F Review Criteria is +/-+2 pcmI°F of the predicted ITC.

November 2015

Serial No. 15-594/Enclosure/Page 5 Review Criteria met? Yes.

The Moderator Temperature Coefficient (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 +0.19 x 10-4 Ap/°F. The MPS2 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 CEA Rod Worth Parameters were not measured as allowed by WCAP-16011-P-A, Revision 0, "Startup Test Activity Reduction Program."

3.4 Rodded Critical Boron Concentration The CBC measured with CEA Group A inserted was not performed during Cycle 24 startup testing due to application of the STAIR Program.

3.5 Control Rod Drop Time Measurements The MPS2 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 535.5 °F with all four reactor coolant pumps operating. The average control rod drop time was 2.15 seconds to 90% insertion, with the fastest and slowest drop times being 2.00 seconds and 2.24 seconds, respectively.

Technical Specification limits met? Yes.

November 2015

Serial No. 15-594/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 FrT Peak Linear Heat Rate Ineore Tilt 69% 1.565 9.36 KW/ft 0.0066 100% 1.576 12.88 KW/ft 0.0057 The corresponding technical specification limits for all power levels for these parameters are:

  • FrT -* 1.69 (Note - larger values of FrT are permissible at less than 100%

power)

  • Peak Linear Heat Rate _*15.1 KW/ft
  • Azimuthal Power Tilt <_0.02 Technical Specification limit for FrT met? Yes.

Technical Specification limit for LHR met? Yes.

Technical Specification limit for Tilt met? Yes.

November 2015

Serial No. 15-594/Enclosure/Page 7 4.2 Critical Boron Concentration Measurements 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 544.7°F was 1040 ppm.

The cycle average exposure at the time of this measurement was 270 Megawatt Days per Metric Ton Uranium (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 1040.3 ppm.

Adjusted, measured 100% power CBC = 1040.3 ppm Predicted 100% power CBC= 1036.4 ppm Difference +3.9 ppm (+32 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 CBC performed at HZP and HFP was determined and compared to the design prediction.

Predicted change in CBC from HZP to HFP = 468.6 ppm Adjusted, measured change in CBC from HZP to HFP = 468.2 ppm Difference = 0.4 ppm Review Criteria is +/-+50 ppm of the predicted CBC difference.

Review Criteria met? Yes.

November 2015

Serial No. 15-594/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 -0.033 to +0.044.

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 3.09%

Review Criteria is _+10%.

Review Criteria met? Yes.

4.5 Moderator Temperature Coefficient The ITC measurements were performed at a power level of 99.03 %, an RCS boron concentration of 1040 ppm, and an average RCS temPerature of 569.60°F, and CEA Group 7 at 180 steps.

The measured JTC at these conditions was -8.273 pcnI°F.

The predicted ITC was determined for a power level of 100%, an RCS boron concentration of 1049 ppm, an average RCS temperature of 570.0°F, and at an ARO condition.

The predicted JTC at these conditions was -8.520 pcmI°F.

The predicted ITC adjusted for 99.03% power, an actual RCS boron concentration of 1040 ppm and an RCS temperature of 569.60°F yields an adjusted, predicted ITC of -8.582 pcmI°F.

Adjusted, Predicted ITC = -8.582 pcmI°F Measured ITC = -8.273 pcmI°F Difference = -0.309 pcmI°F Review Criteria is +/- 2 pcnil°F of the predicted ITC.

November 2015

Serial No. 15-594/Enclosure/Page 9 Review Criteria met? Yes.

The MTC was determined by subtracting the predicted Doppler Temperature Coefficient at the test conditions from the measured ITC.

The MTC at these conditions was -0.70 x 10-4 Ap/°F. The MPS2 Technical Specifications require the MTC be less than or equal to +0.4 x 104 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 391,180 gallons per minute (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 378,180 GPM. This value is used to satisfy the technical specification surveillance requirement.

The MPS2 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 20 MWDIMTU, non-equilibrium xenon conditions is shown in Figure 6.2. This map shows that there is good agreement between the measured and predicted values.

November 2015

Serial No. 15-594/Enclosure/Page 10 The core power distribution map for 100%, cycle average exposure of 204 MWD/MTU, non-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 approximately 2.2 x 10.4 gCi/ml. These RCS activity levels show there are no failed fuel assemblies resident in the core.

November 2015

Serial No. 15-594/Enclosure/Page 11

5. REFERENCES 5.1 EN 21004K, "Cycle 24, Low Power Physics Test" 5.2 EN 21004J, "Cycle 24, Power Ascension Testing" 5.3 ETE-NAF-2015-0121, Rev. 0, Attachment A, "Millstone Unit 2, Cycle 24, Startup and Operations Report," October 2015 (Areva NP, Inc. Proprietary).

5.4* SP 21010, "CEA Drop Times" 5.5 WCAP-16011-P-A Revision 0. "Startup Test Activity Reduction Program,"

February 2005 5.6 ETE-MP-2015-1144, Rev 0, "Application of the Startup Test Activity Reduction (STAR) Program for Cycle 24," October 31, 2015

6. FIGURES 6.1 Cycle 24 Core Loading Map 6.2 69% Core Power Distribution Map 6.3 100% Core Power Distribution Map November 2015

Serial No. 15-594/Enclosure/Page 12

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Serial No. 15-594/Enclosure/Page 13

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Serial No. 15-594/Enclosure/Page 14

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