ML13004A112
| ML13004A112 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/26/2012 |
| From: | Scace S Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 12-758 | |
| Download: ML13004A112 (17) | |
Text
Dominion Nuclear Connecticut, Inc.
Dominion Millstone Power Station Dominion-Rope Ferry Road Waterford, CT 06385 U.S. Nuclear Regulatory Commission Serial No.12-758 Attention: Document Control Desk MPS Lic/WEB RO 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 22 Pursuant to Section 6.9.1.3 of the Millstone Power Station Unit 2 Technical Specifications, Dominion Nuclear Connecticut, Inc. hereby submits the enclosed Startup Test Report for Cycle 22.
If you have any questions or require additional information, please contact Mr. William D. Bartron at (860) 444-4301.
Sincerely, Stephen E. Scace 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 James S. Kim NRC Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08 C2A One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.12-758 MPS Unit 2 Startup Test Report For Cycle 22 bc Page 2 of 2 Action Plan/Commitments (Stated or Implied)
- 1. None
- Verification of Accuracy
- 1. EN 21004K, "Cycle 22, Low Power Physics Test"
- 2. EN 21004J, "Cycle 22, Power Ascension Testing"
- 3. ETE-NAF-2012-0140, Rev. 0, Attachment A, "Millstone Unit 2, Cycle 22, Startup and Operations Report," October 2012 (Areva NP, Inc. Proprietary).
- 5. WCAP-1 6011-P-A Revision 0, "Startup Test Activity Reduction Program,"
February 2005
- 6. ETE-MP-2012-1174, Rev 0, "Application of the Startup Test Activity Reduction (STAR) Program for Cycle 22," November 20, 2012
Serial No.12-758 MPS Unit 2 Startup Test Report For Cycle 22 Enclosure Enclosure Millstone Power Station Unit 2 Startup Test Report For Cycle 22
Serial No.12-758 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 11
- 6. FIGURES 11 6.1 Cycle 22 Core Loading Map 12 6.2 69% Core Power Distribution Map 13 6.3 100% Core Power Distribution Map 14 December 2012
Serial No.12-758 Enclosure/Page 2
SUMMARY
The Millstone Power Station Unit 2 (MPS2) refueling outage preceding the Cycle 22 startup was approximately 48 days, starting on October 6, 2012 and ending on November 23, 2012.
The results of the MPS2, Cycle 22 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.
Implementation of the Startup Test Activity Reduction (STAR) Program for MPS2 Cycle 22 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.
December 2012
Serial No.12-758 Enclosure/Page 3
- 2.
INTRODUCTION The MPS2 Cycle 22 fuel loading was completed on November 8, 2012. The attached core map (Figure 6.1) shows the final core loading. The subsequent operation/testing milestones were completed as follows:
Initial Criticality November 21, 2012 Low Power Physics Testing Complete November 22, 2012 Turbine On-Line November 23, 2012 30% Power Testing Complete November 23, 2012 69% Power Testing Complete November 24, 2012 100% Power Testing Complete December 5, 2012 The MPS2 Cycle 22 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.
December 2012
Serial No.12-758 Enclosure/Page 4 3.1 Unrodded Critical Boron Concentration The Critical Boron Concentration (CBC) measured with CEA Group 7 at 148 steps withdrawn and a reactor coolant system (RCS) temperature of 528.2°F was 1571 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 1582 ppm.
Adjusted, measured unrodded CBC Predicted unrodded CBC
=
1582 ppm
=
1578 DDm Difference 4 ppm (30 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 1571 ppm, an average RCS temperature of 529.3°F, and CEA Group 7 at 148 steps.
The measured ITC at these conditions was +0.97 pcm/°F.
Adjusted to the prediction conditions for an RCS boron concentration of 1565 ppm and an RCS temperature of 532°F yields an adjusted, measured ITC of +0.77 pcm/°F.
Adjusted, measured ITC Predicted ITC
=
+0.77 pcm/°F
=
+0.96 ncm/°F Difference
=
-0.19 pcm/°F Review Criteria is +/- 2 pcm/°F of the predicted ITC.
December 2012
Serial No.12-758 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 +0.22 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 the STAR Program.
3.4 Rodded Critical Boron Concentration The CBC measured with CEA Group A inserted was not performed during Cycle 22 startup testing due to application of the STAR 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°F with all four reactor coolant pumps operating. The average control rod drop time was 2.16 seconds to 90% insertion, with the fastest and slowest drop times being 2.04 seconds and 2.24 seconds, respectively.
Technical Specification limits met?
Yes.
December 2012
Serial No.12-758 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 Incore Tilt 69%
1.571 9.14 KW/ft 0.0079 100%
1.556 12.71 KW/ft 0.0081 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.
December 2012
Serial No.12-758 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 544.1°F was 1099 ppm.
The cycle average exposure at the time of this measurement was 351 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 1099.8 ppm.
Adjusted, measured 100% power CBC =
Predicted 100% Dower CBC 1099.8 ppm 1099.6 DDm Difference 0.2 ppm (2 pem)
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
= 478.4 ppm Adiusted, measured change in CBC from HZP to HFP = 481.8 DDm Difference
=
-3.4 ppm Review Criteria is +/- 50 ppm of the predicted CBC difference.
Review Criteria met?
Yes.
December 2012
Serial No.12-758 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 -0.043 to +0.040.
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 2.60%
Review Criteria is +/- 10%.
Review Criteria met?
Yes.
4.5 Moderator Temperature Coefficient The ITC measurements were performed at a power level of 98.49 %, an RCS boron concentration of 1099 ppm, and an average RCS temperature of 569.27°F, and CEA Group 7 at 180 steps.
The measured ITC at these conditions was -7.234 pcm/°F.
The predicted ITC was determined for a power level of 100%, an RCS boron concentration of 1122 ppm, an average RCS temperature of 570.1°F, and at an ARO condition.
The predicted ITC at these conditions was -7.290 pcm/°F.
The predicted ITC adjusted for 98.49% power, an actual RCS boron concentration of 1099 ppm and an RCS temperature of 569.27°F yields an adjusted, predicted ITC of -7.490 pcm/°F.
Adjusted, Predicted ITC
=
-7.490 pcm/°F Measured ITC
=
-7.234 pcm/PF Difference
=
-0.256 pcm/°F Review Criteria is +/- 2 pcm/°F of the predicted ITC.
December 2012
Serial No.12-758 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 -0.6 x 10-4 Ap/°F. The MPS2 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 390,541 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 377,541 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 23 MWD/MTU, non-equilibrium xenon conditions is shown in Figure 6.2. This map shows that there is good agreement between the measured and predicted values.
December 2012
Serial No.12-758 Enclosure/Page 10 The core power distribution map for 100%, cycle average exposure of 157 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 about 2.6 x 10-4 gCi/ml. These RCS activity levels show there are no failed fuel assemblies resident in the core.
December 2012
Serial No.12-758 Enclosure/Page 11
- 5.
REFERENCES 5.1 EN 21004K, "Cycle 22, Low Power Physics Test" 5.2 EN 21004J, "Cycle 22, Power Ascension Testing" 5.3 ETE-NAF-2012-0140, Rev. 0, Attachment A, "Millstone Unit 2, Cycle 22, Startup and Operations Report," October 2012 (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-2012-1174, Rev 0, "Application of the Startup Test Activity Reduction (STAR) Program for Cycle 22," November 20, 2012
- 6.
FIGURES 6.1 Cycle 22 Core Loading Map 6.2 69% Core Power Distribution Map 6.3 100% Core Power Distribution Map December 2012
Serial No.12-758 Enclosure/Page 12 Zr41 I~
Z-rZ-3
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N-4 AA-76 N-5 BB-03 183 N-6 BB-23 N-7 AA-02 224 N-9 AA-60 N-i1 AA-31 206 N-13 AA-53 N-15 AA-07 229 N-16 BB-26 N-17 BB-06 226 N-18 AA-70 1-18 1-19 88-18 AA-75 V-3 AA-71 V-4 BB-19 169 V-5 AA-09 V-6 Z-65 187 V-7 BB-55 V-9 Z-05 209 1 BB-63 V-13 Z-04 185 V-15 BB-58 1-16 Z-64 198 V-17 AA-16 V-18 BB-18 173 V-19 AA-75 P-i Z-45 M-1 Z-34 K-i Z-37 H-1 Z-42 T-2 T-3 T-4 T-5 T-6 T-7 T-9 T-11 T-13 T-15 T-16 T-17 T-18 T-19 T-20 Y-23 BB-07 AA-13 AA-48 BB-47 Z-53 AA-33 AA-19 AA-37 Z-52 BB-50 AA-47 AA-12 BB-02 Y-18 171 228 208 182 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 Z-17 BB-27 Z-61 BB-51 AA-21 AA-68 AA-41 BB-43 AA-50 AA-61 AA-24 BB-46 Z-68 BB-22 Z-24 190 232 196 186 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 BB-15 AA-08 BB-59 Z-49 AA-62 BB-31 Z_10 Z-28 Z-15 BB-30 AA-67 Z-56 BB-54 AA-01 BB-10 207 178 159 218 197 167 212 N-2 N-3 N-4 N-5 N-6 N-7 N-9 N-11 N-13 N-15 N-16 N-17 N-18 N-19 N-20 BB-39 AA-54 Z-0I AA-38 AA-51 Z-16 BB-71 AA-28 BB-70 Z-09 AA-44 AA-36 Z-08 AA-59 BB-34 214 201 180 213 217 179 L-2 L-3 L-4 L-5 L-6 L-7 L-9 L-11 L-13 L-15 L-16 L-17 L-18 L-19 L-20 BB-68 AA-32 BB-64 AA-20 BB-44 Z-25 AA-25 AA-77 AA-27 Z-27 BB-42 AA-18 BB-62 AA-30 BB66 200 116 168 225 202
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C-4 AA-72 C-5 BB-08 156 C-6 BB-28 C-7 AA-05 210 C-9 AA-55 C-11 AA-29 221 C-13 AA-58 C-15 AA-04 223 C-16 BB-21 C-17 BB-01 166 C-18 AA-74 4-4-4 a -
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B-5 B-6 Y-24 IZ-18 B-7 BB-16 B-9 BB-40 216 B-11 BB-65 B-13 BB-33 181 B-15 BB-09 B-16 B-17 Z-23 IY-17 a -
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rZ-46
[Z-35 Z-38 Z-143 Figure 6.1 Millstone Unit No. 2 Cycle 22 Core Loading Map NORTH December 2012
Serial No.12-758 Enclosure/Page 13
[8[1 [1 [10291r:
4001 F -
F -
F -
I -
I -
q -
q -
q -
(-5
(-7 X-1 3 X-l 5 X-l 6 X-1 7 1107 0.289
(-5
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(-9 X-1 1 1.146 1.139 0.007 X-1 3 X-1 5 X-16 X-1 7 01289 0.288 0,001 1.100 0.286 0.007 0.001 F -
F -
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N-S N-il W-17 N-4 W-18 N-4 0.405
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h -
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/-3 1-19 13
/-4
/-5
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'-1
(-1 K T-2 T-3 T-4 T-5 T-6 T-7 9
T-11
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-16 T-17 T-18 T-19
-20 0,284 1.085 1.289 0.288 1.095 1.304
-0.004
-0.010
-0.015 S-2 S-3 S-4 S-5 S-6 S-7 S-9 S-11 S-13 S-15 5-16 5-17 5-18 S-19
-20 1.288 1.248 0.490 1.289 1.272 0.493
-0.001
-0.024
-0.003 R-2 R-3 R-4 R-5 R-6 R-7 R-9 Ru-11 R-13 R-15 R-16 R-17 R-18 R-19 R-20 1.256 1.107 1.258 1.112
-0.002
-0.005 N-2 N-3 N-4 N-5 N-6 N-7 N-9 N-1 N-13 N-15 N-16 N-17 N-18 N-19 N-20 1.116 0.868 1.107 1.132 0.889 1.095
-0.016
-0.021 0.012 L-2 L-3 L-4 L-5 L-6 L-7 L-9 L-11 L-13 L-15 L-16 L-17 L-18 L-19 L-20 1.350 1.243 1,253 1.353 1.345 1.273 1.273 1.345 0.005
-0.030
-0,020 0.008 J-2 J-3 J-4 J-5 J-6 J-7 J-9 J-11 J-13 J-15 J-16 J-17
"-18
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-0.003 0-2 0-3 G-4 G-5 G-6 0-7 G-9 G-11 G-13 G-15 G-16 G-17 0-18 0-19 G-20 0.865 INOP 0.885
-0.020 F-2 F-3 F-4 E-5 F-6 F7 F-9 F-11 F-13 F-15 F-16 F-17 F-18 F-19 F-20 INOP 1.241 1.312 1.273 1.289
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--16 E-17 6-18 6-19 E-20 0.290 0,288 0.002
(-21 M1-21 D-3 0.409 0.407 0.002 D-4 D-6 1.225 1214 0.1 1.256 1.258
-0.002 0-11 1.351 1.345 0.006 D-13 D-15 D-16 D-17 D-18 0-19 U -
S -
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Serial No.12-758 Enclosure/Page 14
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-0.004 N-2 N-3 N-4 N-5 N-6 N-7 N-9 N-11 N-13 N-15 N-16 N-17 N-18 N-19 6-20 1.146 0.894 1.119 1.171 0.920 1.112 0025
-0.026 0.007 L-2 L-3 L-4 L-5 L-6 L-7 L-9 L-1I L-13 L-15 L-16 L-17 L-18 L-19 L-20 1.341 1.266 1.271 1.342 1.335 1.291 1.291 1.335 0.006
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-0.023 F2 F-3 F-4 F-5 F-6 F-7 F-9 F-11 F-13 F-15 F-16 F-17 F-18 F-19 F-20 INOP 1.262 1.288 1.291 1265
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(-21 H-21 3-3 0.413 0.411 0n002 3-4 3-5 1.213 1.199 nn014 3-6 3-7 1.250 1.250 n nno 3-11 1.344 1.335 0.009 3-13 3-15 3-16 3-17 3-18 3-19 0009 I
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3-5 2-6 1.282 1.265 0.017 9-7
,-11 L-13 IG-15
-16 8
-1i7 C-18 1.231 1.289 0,420 1.195 1.265 0.411 003 1 0024 0.009 9
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3-5 lB-6 0.284 0.292
-0.008 7 1.094 1.075 0.019 3-9 3-11 3-13 3-15 1.104 1.075 0.029 3-16 13-17 Radial 0,34035 Root Mean Square Deviation 0.00 1 4 or1 11ll C li~
L.
tII*Fion Axial Root Mean Square Co Deviation = 0.013 S-U'" '"J Key
- 5 Core Location 0,5261 Measured RPD ore Average Calculated RPD Figure 6.3 0.006 Difference 100% Core Power Distribution Map All Rods Out, Non-Equilibrium Xenon, 157 MWD/MTU December 2012