ML15055A032

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Startup Test Report for Cycle 17
ML15055A032
Person / Time
Site: Millstone Dominion icon.png
Issue date: 02/18/2015
From: Daugherty J
Dominion, Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML15055A032 (16)
v • d • e


Text

.- Dominion Dominion Nuclear Connecticut, Inc.

Rope Ferry Rd., Waterford, CT 06385 Maihng Address: P.O. Box 128 Waterford, CT 06385 dorn.con FEB 18--2015 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.

MPS Lic/WEB Docket No.

License No.15-042 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 STARTUP TEST REPORT FOR CYCLE 17 Pursuant to Section 6.9.1.1 of the Millstone Power Station Unit 3 Technical Specifications, Dominion Nuclear Connecticut, Inc. hereby submits the enclosed Startup Test Report for Cycle 17.

If you have any questions or require additional information, please contact Mr. William D. Bartron at (860) 444-4301.

Sincerely, Joý R. Daugherty Site Vice President - Millstone

Enclosure:

(1)

Commitments made in this letter: None

Serial No.15-042 Docket No. 50-423 Page 2 of 2 cc:

U.S. Nuclear Regulatory Commission Region I Administrator 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Mohan C. Thadani Senior NRC Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.15-042 Docket No. 50-423 ENCLOSURE STARTUP TEST REPORT FOR CYCLE 17 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 1 of 13 Table of Contents Paqe 1.0 S U M M A R Y.................................................................................

.. 2

2.0 INTRODUCTION

2 3.0 FU E L D E S IG N...............................................................................

3 4.0 LOW POWER PHYSICS TESTING.............................................

3 4.1 Critical Boron Concentration.............................................

3 4.2 Moderator Temperature Coefficient................................. 4 4.3 Control Rod Reactivity Worth Measurements.................... 5 5.0 POWER ASCENSION TESTING..................................................

6 5.1 Power Distribution, Power Peaking and Tilt Measurements.. 6 5.2 Boron Measurements........................................................

8 5.3 Reactor Coolant System Flow Measurement.................... 8

6.0 REFERENCES

8 7.0 F IG U R E S..................................................................................

.. 9

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 2 of 13 1.0

SUMMARY

This report summarizes the Cycle 17 startup testing performed following the completion of the October-November 2014 refueling outage.

2.0 INTRODUCTION

The Millstone Power Station Unit 3 Cycle 17 fuel reload was completed on November 2, 2014.

The attached core map (Figure 1) shows the final core configuration.

Reference [6.3] documents that Cycle 17 uses a low leakage loading pattern (L3P) consisting of 84 new Region 19 fuel assemblies, 85 Region 18 once-burned fuel assemblies, and 24 Region 17 twice-burned fuel assemblies. All 193 fuel assemblies in the Cycle 17 core are the Westinghouse 17x17 robust fuel assembly (RFA-2) design.

The 84 Region 19 assemblies are comprised of 52 assemblies enriched to 4.10 weight percent Uranium-235 (w/o U235) and 32 assemblies enriched to 4.95 w/o U235.

The top and bottom regions of all fuel assemblies in the Cycle 17 core are comprised of a 6-inch annular blanket region enriched to 2.6 wlo U235.

Placement of the new fuel assemblies in the designated fresh fuel assembly locations was made in a random fashion in order to prevent power tilts across the core due to systematic deviations in the fresh fuel composition.

The 109 re-insert fuel assemblies were ultrasonically cleaned during the October-November 2014 refueling outage. The purpose of the ultrasonic fuel cleaning was to remove adhered crud (primarily nickel and iron-based deposits) from the surface of fuel rods that have previous core exposure in order to reduce the probability of occurrence of crud induced power shift (CIPS).

Every fuel assembly in Cycle 17 contains an insert. The inserts consist of 61 rod cluster control assemblies (RCCAs), 130 thimble plugs, and 2 secondary source assemblies.

Subsequent operational and testing milestones were completed as follows:

Initial Criticality November 16, 2014 Low Power Physics Testing completed November 16, 2014 Main Turbine Online November 17, 2014 30% Power Testing completed November 17, 2014 74% Power Testing completed November 19, 2014 100% Power Testing completed November 24, 2014

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 3 of 13 3.0 FUEL DESIGN All of the 193 assemblies in the Cycle 17 core are of the RFA-2 design. This fuel design is the same as Cycle 16.

4.0 LOW POWER PHYSICS TESTING The low power physics testing program for Cycle 17 was completed using the procedure in reference [6.1] based on the Westinghouse dynamic rod worth measurement (DRWM) Technique described in reference [6.4]. This program consisted of the following: control and shutdown bank worth measurements, critical boron endpoint measurements for all rods out (ARO), and ARO moderator/isothermal temperature coefficient measurements. Low power physics testing was performed at a power level below the point of nuclear heat to avoid nuclear heating reactivity feedback effects.

4.1 Critical Boron Concentration The critical boron concentration was measured for the ARO configuration.

The measured values include corrections to account for differences between the measured critical rod configuration and the ARO configuration.

The review and acceptance criteria of +/-500 and +/-1000 percent milliRho (pcm), respectively, were met for the ARO configuration.

Summary of Boron Endpoint Results Measured Predicted M-P Acceptance (ppm)

(ppm)

(ppm)

Criteria (pcm)

All Rods Out 2106 2098

+8 (-47.9

+ 1000 (ARO) pcm)

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 4 of 13 4.2 Moderator Temperature Coefficient Isothermal temperature coefficient (ITC) data was measured with Control Bank D at 200 steps withdrawn. The review criteria of +/-2 pcm/degrees Fahrenheit (OF) to the predictions were met.

The ARO moderator temperature coefficient (MTC) of +1.05 pcm/°F was calculated by subtracting the design Doppler temperature coefficient (-1.74 pcm/°F) from the measured ARO isothermal temperature coefficient of -1.19 pcm/°F, and adding the delta (A) ITC correction value of +0.50 pcm/°F (AITC corrects the MTC at the measurement conditions to the minimum temperature for criticality value of 551 0F).

The technical specification limit of MTC < +5.0 pcm/°F at ARO hot zero power (HZP) was met.

Isotherm al/Moderator Temperature Coefficient Results Measured Corrected M-P Acceptance (pcm/°F)

Predicted (pcm/°F)

Criteria (pcm/°F)

(pcm/°F)

ARO ITC

-1.19

-1.94

+0.75 NA ARO MTC

+1.05 NA NA MTC < +5.0

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 5 of 13 4.3 Control Rod Reactivity Worth Measurements The integral reactivity worths of all RCCA control and shutdown banks were measured using the DRWM technique. The review criteria is the measured worth is

+/-15% or 100 pcm of the individual predicted worth, whichever is greater and sum of the measured worths is +/-8% of the predicted worths. The DRWM rod worth acceptance criteria is defined as: the sum of the measured worths (M) of all banks shall be greater than or equal to 90% of the sum of their predicted worths (P).

Control Bank Integral Worth Results Measured Predicted M-P (pcm)

(pcm)

(pcm)

Difference (M-P) / P Control Bank A 914.1 893.1 21.0 2.4 Control Bank B 518.3 513.5 4.8 0.9 Control Bank C 757.8 779.8

-22.0

-2.8 Control Bank D 662.2 606.2 56.0 9.2 Shutdown 433.4 419.8 13.6 3.2 Bank A Shutdown 820.2 859.1

-38.9

-4.5 Bank B Shutdown 399.5 377.4 22.1 5.9 Bank C Shutdown 424.0 392.8 31.2 7.9 Bank D Shutdown 63.0 62.9 0.1 0.2 Bank E Totals 4992.5 4904.6 87.9 1.8 The measured results of the individual bank worths and the total control bank worth showed excellent agreement with the predicted values. All individual and total worth review criteria were met. The acceptance criteria for sum of the measured rod worths (greater than or equal to 90% of the sum of the predicted worths) was met.

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 6 of 13 5.0 POWER ASCENSION TESTING Testing was performed at specified power plateaus of 25%, 74% and 100% Reactor Thermal Power (RTP). Power changes were governed by operating procedures and fuel preconditioning guidelines.

Thermal-hydraulic parameters, nuclear parameters, and related instrumentation were monitored throughout the power ascension. Data was compared to previous cycle power ascension data and engineering predictions, as required, at each test plateau to identify calibration or system problems. The major areas analyzed were:

1. Core performance evaluation:

Flux mapping was performed at 25%, 74% and 100% RTP using the moveable incore detector system. The resultant peaking factors and power distribution were compared to Technical Specification (TS) limits to verify that the core was operating within its design limits. All analysis limits were met and the results are summarized in Section 5.1.

2. Nuclear instrumentation indication:

Overlap data was obtained between the intermediate and power range nuclear instrumentation channels. Secondary plant heat balance calculations were performed to verify the nuclear instrumentation indications.

3. Incore/Excore Calibration:

Scaling factors were calculated from flux map data using the single point calibration methodology.

The nuclear instrumentation power range channels were re-scaled at 25%, 74% and 100% RTP.

4. RCS Flow: The RCS flow rate was measured at approximately 94% RTP using a secondary calorimetric heat balance for each loop using the steam generators as the control volumes. The calculated RCS flow rate met the TS requirements and is reported in Section 5.3.

5.1 Power Distribution, Power Peaking and Tilt Measurements The core power distribution was measured through the performance of a series of flux maps during the power ascension as specified in reference [6.2]. The results from the flux maps were used to verify compliance with the power distribution TSs.

A low power flux map at approximately 25% RTP was performed to determine if any gross neutron flux abnormalities existed. At the 25% RTP plateau flux map and again at the 74% map, data necessary to perform an excore to incore calibration via the single point methodology was obtained. Per TS Surveillance 4.3.1.1, Table 4.3-1, Functional Unit 2, Note 6, a flux map at approximately 100% RTP was performed for an excore to incore calibration. The 100% RTP map also verified core power distributions were within the design limits.

A summary of the measured axial flux difference (AFD) and incore tilt for the flux maps performed during the power ascension is provided below. Additional tables provide comparisons of the most limiting measured heat flux hot channel factor (FQ) and nuclear enthalpy rise hot channel factor (FAh), including uncertainties, to their

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 7 of 13 respective limits from each of the flux maps performed during the power ascension.

The most limiting FQ reported is based on minimum margin to the steady state limit that varies as a function of core height.

As can be seen from the data presented, all TS limits were met and no abnormalities in core power distribution were observed during power ascension.

Summary of Measured Axial Flux Difference and Incore Tilt Power Burnup Rod AFD (%)

Incore Tilt

(%RTP)

(MWD/MTU)

Position (steps) 24.8 3.6 216 5.429 1.0126 74.0 27.3 216 4.467 1.0104 99.8 258.6 216 1.477 1.0089 Comparison of Measured FQ to FQ RTP Limit Power Burnup Measured FQ FQ 0 ' steady Margin to Transient

(%RTP)

(MWD/MTU) state limit Limit 24.8 3.6 N/A N/A N/A 74.0 27.3 1.9822 3.3891 11.8%

99.8 258.6 1.8853 2.5726 14.4%

Comparison of Measured F~h to Fah Limit Power Burnup

(%RTP)

(MWD/MTU)

FAh F~ h Limit 24.8 3.6 1.598 1.944 74.0 27.3 1.509 1.710 99.8 258.6 1.467 1.587 Presented in Figures 2, 3 and 4 are measured power distribution maps showing percent difference from the predicted power for the 25%, 74% and 100% RTP plateaus. From this data, it can be seen that there is good agreement between the measured and predicted assembly powers.

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 8 of 13 5.2 Boron Measurements Hot full power ARO boron concentration measurements were performed after reaching equilibrium conditions.

The measured ARO, hot full power, equilibrium xenon, boron concentration was 1448 ppm with a predicted value of 1475 ppm. The predicted to measured difference was - 168 pcm which met the acceptance criteria of +/- 1000 pcm.

5.3 Reactor Coolant System Flow Measurement The RCS flow rate was determined using a secondary calorimetric heat balance for each loop using the steam generators as the control volumes.

The following parameters were measured:

RCS pressure Hot leg temperatures Cold leg temperatures Feedwater temperatures Feedwater flow rates Feedwater pressure

" Steam generator pressure Steam generator blowdown was not isolated during the data acquisition period.

Per TS Surveillance 4.2.3.1.3, the RCS flow was measured within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 90% RTP. The measured flow at 94.5% RTP was 400,553 gallons per minute (gpm) with a minimum required flow of 379,200 gpm. All TS limits were met.

6.0 REFERENCES

6.1 SP 31008, Rev. 006-00, "Low Power Physics Testing (ICCE)"

6.2 EN 31015, Rev. 004-00, "Power Ascension Testing of Millstone Unit 3" 6.3 ETE-NAF-2014-0098, Rev. 000, "Millstone Unit 3 Cycle 17 Nuclear Design Report" 6.4 WCAP-13360-P-A, Revision 1, "Westinghouse Dynamic Rod Worth Measurement Technique"

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 9 of 13 7.0 FIGURES Page 1

Cycle 17 Core Loading Pattern.................................... 11 2

INCORE Power Distribution - 25%..............................

12 3

INCORE Power Distribution - 74%................................ 13 4

INCORE Power Distribution - 100%.............................

14

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 10 of 13 FIGURE I CORE LOADING PATTERN MILLSTONE UNIT 3: -

CYCLE 17 R

P N

M L

I T40 LT!57 VI W54 KI JI I

G F

I I 2

D C

R A

'H IA

.1.

7k 17 k

17A iTl VL9 v44 IR8A v26 27A i.71 17A TZI

'-4 1

Ilk 1*

19B W6 2 19A wig 193 WS&

1.9k ff53 293 W73 19B V5I6 718 17A TS2 I

2.

17A 19 1931B 1A ISA 19 1113 19A ISA 15A.

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198 w92 IRA

4 900

.+/-7*

ISE 191 ISE 19A IRE 19A ISA 191 IRE 19*.

293 19A 19B 17A T52 W57 W39 V61 W42 VGS W5 742 WtSS 76 WA&

755 20 tw59 T34 17A 19B i

Ra I.

91'a 19e Ilk 19A=

1.9, 29 1

ISE 13 1A 19B 17k.

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19A 19k I*

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-n5 v09 w02 V30 WIG V12 wf4 v33 w31 w27 v24; LOA 19B le9 19A 1A 19A 10*A IRA 1.9 I9A i1, 19A 113 i29B lk v29 Wf1 V73 W2t Ve 0 w4t e

v49 V735 V45 W52 V37 w23 762 wt72

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v 2 WAS V79 V70 V42 W7l T729 17A IiS i9*

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+/-7k T30 W3 9 W22 55 Wuc vii 9

734 f01 704 vA 757 ff21 753 T22

-- 5

-6

-7

--9

--9

-- 10

-- 1I IlA v23 193 w93 "SE V93 193 vS&

193 v771 1v1 709 29A W39 V46 1.53 v72 l13 V90 2977 19B W77 12A V22 1731193 tS 11 9gA ItA 19* t 1 9 111k 19A 29ID 191. 17A T)S j69 wt4 W37 j47 wj3 Vj3 W0 v52 ff32 W79 Kw9 739 12 13 14 17A T24 igA 193 ala W476 19kL W113 13.

well W29 u9a W&7 19P f55 IRA V-2.5 71B1 TGI v13 W60

+/-7A 17A T50 Tie

iRA, vi, 7 12A 19A val v20 IA v&4 17TL T56 is 00 LEGEND REhGION AISSDWLICES ENRICHMENT FR Region Identifier ID Fuel Assembly identifier 1VA 17n 192 iRA 19i3 20 4

63 3.2 52 3.2 4.10 4.96.

4.10 4.95 4.10 4.96

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 11 of 13 FIGURE 2 INCORE Power Distribution -

254 MILLSTONE UNIT 3 -

CYCLE 17 R

P N

M L

K J

H G

F E

I I

I I

I I

I 0.280 0.361

.44) 0.4391

.423r.34) 0.268

-G.4

-t1.

1.42 -2.0

-1.9 1-w. -0.7 D

C B

A 1

0.270]

I 0.272

-1.1 0.72 0.65 1a 4

.2 1.02*, 16*4. 1.058 10o0. 1.073

0. 5

-1.3 K-1.

-0.1 1 1.5 1.5 2

0.2701 0.8841 1.17911-2411 1.0991 1.1891'T7W l.203kWW4j 1.258}'.W.I 884 1T.2

-0.7 j-.8

-0.9

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3.

2.6 14

-9.

OS It-s3 ei.54-1"l-7 1.17)8 1.372 1.7 1.42C

.4.5 1.307 4.6 1.G,5

-1.3 1.115 0.3 1.272 2.7 1.398 3.2 1.38D 3.0 1.107 D.6

0. 156a1 0-2

-i--

4 0264 1.048 1.227 1.380 1-.3 1.337 1.275 1.084 1.27 1.332 1.38 1A15 1.20 1.100 0.278 2

-0.0 0.1 1.9 ý,_2.2j 2.1

-2.1

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1 1 0.1.327 1.,21 1.097 1.12

.108 1.262 1.341 1271 1.10 1.14

-4.2

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-2.2 *-2.3

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.984 0.416 5-58

-3.7

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-9 60 1.024 41_1 13 08

-. 3

-5.7

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-14 0.3441 -.4291C,.4Q 0.4301 0.371 0.287

-2.5

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Difference (M-P)JP Measured Location

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 12 of 13 FIGURE 3 INCORE Power Distribution -

74%

MILLSTONE UNIT 3 -

CYCLE 17 R

P Ni M L

K J

H G

F E

D C

B I

I I

I I

I I

0-24,0.37; a104 OA58110444 035 0282

-1.0 3

-00

-0.7 00 10 19 8 0273 0.558 1,001.13 0

1.0

.17 1.068 1.097 1.063 0552 02751

-2.5 1.0

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1

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2.

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y. 3D..

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-2.5

.-2.4

-1.8

-0.4 -

-0.2 k.0.A 1.2 11.e.

1.8 2.8 2.0 O-T, k-0.27 0.545 1.037 1.0

'1.051 1.181 1.020r1.13b 1,01 0.57 0.283 4.8

-D.9 7 U+2 0.3 +.

K 0.3A 1.2 1.1 14 0.3581 0.446K*,O40B 0.444 0-373 0.290

-1.1 0.5 03.7 0.7 0.0 1 1.0 15 D* Measured Power

% Difference (M-P)JP 11 Measured Location

Serial No.15-042 Docket No. 50-423 MPS3 Startup Test Report For Cycle 17 Enclosure, Page 13 of 13 FIGURE 4 INCORE Power Distribution -

100%

MILLSTONE UNIT 3 -

CYCLE 17 R

P N

M L

K J

H G

F E

D C

B 0.283* 0.374

.44:

.641*.4562K0377 0.28B

-2.7

-1.1

-1.0

-1.3 j 0.0,31.

2.5 1o,.

1.0* *.1--

1.073 1.AO0 1.058D510OJ 0-2731 0-55 1.-04.5 1.11 7

1.

0 76.

-2.0 ý1-V2,

-1.3

-0

.8) 41 21 1.3

-1.8

-1.8 A

2 0.2741 C.&57 1.1.1 3 1 104 1.188 1.19 1.2 0 8Rlm11 1.2 0 7 8 0 4 K2 7

-2.5J -2.4 1-3.8 2.712

-17

&V2D.

-0.2 083 d

-1 43 r.)ý ri -1' yV2.4, 1.273

-0.9 1.33-1.7 1.250 1.7 1.120

-0.7

ý_-04.4) 1.129 0.5 1-245 2.0 1.323 1.2 1.291 0.5 1-145

-0.8 D.563

-0.4 i-4 0-2791-0311.185 1.0.32:b 1.308 1.310 1.131 1.311l 1.311 1.33 1351.1

.0

-8

-0.7

-0.9

-1.1

-0.1 0

.9

-0.5

-0.4

-0.3 1.4 2.1/

1.5

-0.

-0.4

-1.

176 1

.9 239 1-.37 71.28 1.154 1.19 1.165 1280 1.331 1.237 1.08ý 1.12' 0371

-0.3) 0.6 ý,1.4 1.5 1.1 0

0,,

.0D O.2, 1.0 2.0 2.7 0.7 7

-1.9 0.44311.049 1.200"1.124 1.325 1.1011".271 1.094 1.279 117; 1.321 1.171.18 1.000 0.438

-2.0

-1.15

-00.8 0.7 0.5 0.5 0-9 1.5j 0.3

-1.9

-2.1 2.4 0.45 113561-18 1240

.14" 1.2071.1 1.042 1.1l4 1.21 1.139( 12 1.18)

.15 0-400

-4.0

-3.8

-2.2

-0.5 1.1 D.9 1.0 12 1.4 1 2-0* D

-1.4 1.9 -2.1 01-10 1.117 1.321 1.109 1.301 1.1121.27 1.159-.31

-4.0

-3.9

-4.0

-1.0 0.3 1.3 2.5 2.1 O.6, 0.5 02

-0.3

-1.2 1.8 0.308 1.099 1.048 1l.227 1.29 1.274 1.19 1.2 229 1.180 1.277 1.310 124 1.105 1.006 0.307

-2.6

-2.8

-4.2

-0.2

-0.2 1.0 3.3 2.8 2.3 1.3 1.8 1.8 2.7

-0.4

-0.3 8

1.058 1.214 1.313 1.3 1.303 1.345*

1.17 1.363 1.33

1.

1.3m 1.U5 4

-1.4

-0.2

-0.2

-.2 0.8 2.3 13.4 3.5 2.8 2.1 1

23 0.5*

-5

-:5

-7

-8

-9

- 10

.11 D.54E

-3.0 1.100

-4.7 1.261

-1.9 1.302

-0.4 3.21. 1.1137 1279

.l.40* 1-2@41 28 339C1.

1.1 0

.9 0

ý,--g A.

9., 1~ 2.1

,*2.3 2.8 1.8 1:

12 13 0.273ýo.84? 1.117(1.191 1.00711 201r121Qj 1.215 1.151 1.2191 1.1681 0.8.85f028)

-3.

-2.5 (D.9 81-0.7 LO!

0.8 111.0j 0.2 1.2 10.8

,Ot 0.54711.0301 i.t.-o&(o) 11801 1.020t1K1.i1i.oeafoso,&I 0.284

-2.1

-0.8

-1.0 k-0.2 0.0 1-0.2 K-.)-0.4 k0.7A 0DA 14 0.28

[064 0.4530.47 0.449 0.372 0.290

.cO.4D -1.1 0.2 k0.2, 0.0

-1.6

-0.3 15 DMeasured. Power

% Difference (M-PIP D

Measured: Location

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