ML052150035

Startup Test Report for Cycle 17

ML052150035
Person / Time
Site:	Millstone
Issue date:	07/21/2005
From:	Scace S Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
05-391
Download: ML052150035 (18)

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Millstone Power Station Rope Ferry Road Warerford, CT' 06385 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 JU 21 Serial No.

MPS Lic/MAE Docket No.

License No.05-391 RD 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 STARTUP TEST REPORT FOR CYCLE 17 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 17.

There are no regulatory commitments contained within this letter.

If you have any questions or require additional information, please contact Mr. David W.

Dodson at (860) 447-1791, extension 2346.

Very truly yours, Stephe ace, Director Nuclear Station Safety and Licensing

O

Serial No.05-391 Page 2 of 2 Enclusures: (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 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station

Enclosure Startup Test Report for Cvcle 17 Millstone Power Station, Unit 2 Dominion Nuclear Connecticut, Inc. (DNC)

Serial No. 05-391/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 6

3.5 Control Rod Drop Time Measurements 7

4. POWER ASCENSION TESTING RESULTS 7

4.1 Power Peaking, Linear Heat Rate and Incore Tilt Measurements 7

4.2 Critical Boron Measurements 8

4.3 Flux Symmetry Measurements 8

4.4 Moderator Temperature Coefficient 9

4.5 Reactor Coolant System Flow 10 4.6 Core Power Distributions 10 4.7 Reactor Coolant System Radiochemistry 11

5. REFERENCES 11

6. FIGURES 11 June 2005

Serial No. 05-391/Enclosure/Page 2

1.

SUMMARY

The refueling outage preceding the Cycle 17 startup was approximately 39 days, starting on April 9, 2005 and ending on May 18, 2005.

The results of the Millstone 2, Cycle 17 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.

June 2005

Serial No. 05-391/Enclosure/Page 3

2.

INTRODUCTION The Millstone 2 Cycle 17 fuel loading was completed on May 9, 2005. The attached core map (Figure 6.1) shows the final core loading. The subsequent operation/testing milestones were completed as follows:

Initial Criticality May 17, 2005 Low Power Physics Testing Complete May 18, 2005 Turbine On-Line May 18, 2005 30% Power Testing Complete May 18, 2005 60% Power Testing Complete May 19, 2005 100% Power Testing Complete May 25, 2005 The Millstone 2 Cycle 17 core is comprised of 217 Framatome ANP 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 2005

Serial No. 05-391/Enclosure/Page 4 3.1 Unrodded Critical Boron Concentration The Critical Boron Concentration measured with CEA Group 7 at 154 steps withdrawn and an RCS temperature of 532.00 F was 1563 ppm.

Adjusted to the prediction conditions of Group 7 at 140 steps withdrawn and an RCS temperature of 5320F yields an adjusted, measured CBC of 1553 ppm.

Adjusted, measured unrodded CBC

=

1553 ppm Predicted unrodded CBC

=

1557 ppm Difference

=

-4 ppm (-33 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 1562 ppm, an average RCS temperature of 531.10F, and CEA Group 7 at 154 steps.

The measured ITC at these conditions was +0.78 pcm/IF.

Adjusted to the prediction conditions for an RCS boron concentration of 1557 ppm and an RCS temperature of 5320F yields an adjusted, measured ITC of +0.69 pcm/IF.

Adjusted, measured ITC

=

+0.69 pcm/IF Predicted ITC

=

+0.57 pcm/°F Difference

=

+0.12 pcm/IF Review Criteria is +/- 2 pcm/0F of the predicted ITC.

June 2005

Serial No. 05-391/Enclosure/Page 5 Review Criteria met?

Yes.

The Moderator Temperature Coefficient was determined by subtracting the predicted Doppler Temperature Coefficient at the test conditions.

The MTC at these conditions was +0.214 x 10i Ap/PF. The Millstone 2 Technical Specifications require the MTC be less positive than +0.7 x 10' Ap/0F 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 measured using the 'rod swap" method. Figure 6.2 shows the CEA group configuration.

CEA Group 'A" was used as the 'reference' group and its reactivity worth was measured using the 'boron exchange' method (dilution results are shown below). The reactivity worth of the remaining CEA groups was measured by establishing a critical condition with the 'test' group fully inserted and the 'reference" group partially withdrawn.

The results of the CEA worth measurements were:

Group Measured Prediction Difference

% Difference A

1045 pcm 1046 pcm

-1 pcm 0.10 %

B 450.1 pcm 431.5 pcm 18.6 pcm

-4.31 %

1 780.2 pcm 771.7 pcm 8.5 pcm

-1.10 %

2 734.7 pcm 744.3 pcm

-9.6 pcm 1.29 %

3 561.8 pcm 533.8 pcm 28.0 pcm

-5.25 %

4 712.9 pcm 719.1 pcm

-6.2 pcm 0.86 %

5 343.5 pcm 327.7 pcm 15.8 pcm

-4.82 %

6 366.4 pcm 344.8 pcm 21.6 pcm l

-6.26 %

7 878.6 pcm 861.7 pcm 16.9 pcm

-1.96 %

Total 5874 pcm 5781 pcm 93 pcm

-1.61 %

June 2005

Serial No. 05-391/Enclosure/Page 6 The Review and Acceptance Criteria are:

1. The measured 'reference' group worth is within +/- 10% of the predicted worth.

2. The measured worth of the individual CEA groups is within

+/- 100 pcm or +/- 15% of the predicted worth, whichever is larger.

3. The sum of the measured CEA worths is within +/- 10% of the sum of the predicted CEA worths.

Review Criteria met for 'reference' CEA group?

Yes.

Review Criteria met for individual CEA groups? Yes.

Acceptance Criteria met for sum of CEA group worths? Yes.

3.4 Rodded Critical Boron Concentration The Critical Boron Concentration measured with CEA Group A at 23 steps withdrawn and an RCS temperature of 530.40 F was 1453 ppm.

Adjusted to the prediction conditions of Group A at 0 steps withdrawn and an RCS temperature of 5320F yields an adjusted, measured CBC of 1451 ppm.

Adjusted, measured rodded CBC

=

1451 ppm Predicted rodded CBC

=

1449 Tpm Difference

=

+2 ppm (17 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.

June 2005

Serial No. 05-391/Enclosure/Page 7 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 5350 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 2.32 seconds, respectively.

Technical Specification limits met?

Yes.

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 (F.T) 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 60%

1.631 8.20 KW/ft 0.0068 100%

1.580 13.11 K*W/ft 0.0084 June 2005

Serial No. 05-391/Enclosure/Page 8 The corresponding Technical Specification limits for all power levels for these parameters are:

F T < 1.69 (Note - larger values of F T 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.

4.2 Critical Boron Measurements Critical Boron Concentration (CBC) measurement was performed at 100%

power at equilibrium xenon conditions.

The CBC measured at 99.7% power with CEA Group 7 at 180 steps withdrawn and an RCS temperature of 568.50F was 1099 ppm. The cycle average exposure at the time of this measurement was 145 MWD/MTU.

Adjusted to the prediction conditions of 100% power at an All Rods Out (ARO) condition and an RCS temperature of 5740F yields an adjusted, measured CBC of 1100 ppm.

Adjusted, measured 100% power CBC =

1100 ppm Predicted 100% power CBC

=

1102 ppm Difference

=

-2 ppm (-16 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.

June 2005

Serial No. 05-391/Enclosure/Page 9 4.3 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 -2.08% to +3.61%.

Review Criteria is +/- 10% (deviation between the highest and lowest values in symmetric incore locations).

Review Criteria met?

Yes.

4.4 Moderator Temperature Coefficient The Isothermal Temperature Coefficient (ITC) measurements were performed at a power level of 98.5 %, an RCS boron concentration of 1100 ppm, and an average RCS temperature of 569.50 F, and CEA Group 7 at 180 steps.

The measured ITC at these conditions was -7.404 pcm/IF.

The predicted ITC was determined for a power level of 100%, an RCS boron concentration of 1102 ppm, an average RCS temperature of 5740F, and at an All Rods Out (ARO) condition.

The predicted ITC at these conditions was -8.35 pcm/nF.

The predicted ITC adjusted for 98.5% power, an actual RCS boron concentration of 1100 ppm and an RCS temperature of 569.50 F yields an adjusted, predicted ITC of -7.823 pcm/IF.

Measured ITC

=

-7.404 pcm/0F Predicted ITC

=

-7.823 pcm/IF Difference

=

-0.419 pcm/IF Review Criteria is +/- 3 pcm/IF of the predicted ITC.

Review Criteria met?

Yes.

June 2005

Serial No. 05-391/Enclosure/Page 10 The Moderator Temperature Coefficient (MTC) was determined by subtracting the predicted Doppler Temperature Coefficient at the test conditions. The MTC at these conditions was -0.617 x 10' Ap/PF. The Millstone 2 Technical Specifications require the MTC be less than or equal to +0.4 x 104 Ap/0F for power levels greater than 70% power.

Technical Specification limit met? Yes.

4.5 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 384,358 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 371,358 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.

4.6 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 60% power and 100% to determine if the measured and predicted core power distributions are consistent.

The core power distribution map for 60% power, cycle average exposure of 11 MWD/MTU, non-equilibrium xenon conditions is shown in Figure 6.3.

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 145 MWD/MTU, equilibrium xenon conditions is shown in Figure 6.4. This June 2005

Serial No. 05-391Enclosure/Page 11 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) of all of the differences between the measured and predicted RPDs is less than 5%.

Review Criteria met?

Yes, for both 60% and 100% power.

4.7 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 1.1 x 104 pCi/gram. These RCS activity levels are well below the Technical Specifications limit of 1.1 pCi/gram.

5.

REFERENCES 5.1 EN 21004K, 'Cycle 17, Low Power Physics Test' 5.2 EN 21004J, 'Cycle 17, Power Ascension Testing" 5.3

'Millstone Unit 2, Cycle 17, Startup and Operations Report" 5.4 SP 21010, 'CEA Drop Times,'

6.

FIGURES 6.1 Cycle 17 Core Loading Map 6.2 CEA Group Configuration 6.3 60% Core Power Distribution Map 6.4 100% Core Power Distribution Map June 2005

Serial No. 05-391/Enclosure/Page 12 Y-lo IY-12 11-14 T-51 T-57 I T-39 T-55 S -

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h1 2 5A-14 T-53 T-37 I T-59 T-49 Key Core Location IW-16 Fuel Assembly ID Insert ID Figure 6.1 Millstone Unit No. 2 Cycle 17 Core Map NORTHtL Source Core Location l

Guide tube 7

F-3 SW 8

S-19 SE 9

X-11 NW 10 B-11 SW June 2005

Serial No. 05-391/Enclosure/Page 13 Channel 'T Uncompensated 0J Ion Chamber NORTH A

Channel sV OJ Uncompensated Ion Chamber Figure 6.2 Millstone unit NO. Z CEA Group Configuration June 2005

Serial No. 05-391/Enclosure/Page 14 01280 0.275, U -

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Figure 6.3 60% Power Distribution Map All Rods Out, Non-Equilibrium Xenon, 11 MWD/MTU June 2005

Serial No. 05-391/Enclosure/Page 15 o[10

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• 121 i-21 0.442 0.442 0.000 D-5 1.281 1.269 0.012 0-6 0-7 1.235 1.234 0.001 0-9

)-11 30-13 3-16 10-17 0-18a 0.970 0.984

-0.014 0-19 a -

a-a-'.

I. -

a -6.

-6.

4444 0-6 1.075 1.057 0.018 C-7 0-9 I11

(>13 1.301 1.273 0.028 3-15 3-16 1.081 1.065 0.016 C-17 C-18 0.454 0.442 0.012

44Sq

 -

9 S9S94

4

0-I i-s 0.304 0.296 0.008 0.822 0.816 0.006 6-9 3-11 3-13 3-15 0.838 0.824 0.014 3-16 13-17 10 r 2 r-4 I

[03690372 0003lK ey Root Mean Square Deviation Pi!

CoereLmatot for all Core Locations = 0.81 %

Mer6402 Calculated RPD Figure 6.4 0.25 fference 100% Power Distribution Map All Rods Out, Equilibrium Xenon, 145 MWD/MTU June 2005