B12865, Startup Test Rept,Cycle 9

Startup Test Rept,Cycle 9

ML20151T860
Person / Time
Site:	Millstone
Issue date:	04/30/1988
From:	Mroczka E, Sears C NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
B12865, NUDOCS 8804290180
Download: ML20151T860 (18)

Text

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Docket No. 50-336 '

B12865

,h Millstone-Nuclear Power Station, Unit No. 2 t Start-Up Test Report Cycle 9 J

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t April 1988 880429o18o oso43o DR ADOCK 05000336 k DCD \

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INDEX~

2 1.

SUMMARY

2. LINTRODUCTION

3. LOW POWER PHYSICS. TESTING RESULTS 3.1 Critical Boron Concentrations 3.2 Control Element' Assembly Symmetry Checks 3.3 Moderator Temperature Coefficients 3.4 Control Element Assembly Reactivity Worths F.' S Hot Rod"Drops

, 4. P0'VER ASCENSION TESTING RESULTS 4.1 Power Peaking, Linear Heat Rate and Tilt Measurements 4.2 Boron Measurements 4.3 Moderator Temperature' Coefficient at 96% Power 14 . 4 Doppler Only Power Coefficient 4.5' RCS Flow at 100% Power 4.6 Power Distributions 4.7 Reactor Coolant System Radiochemistry

5. Rt. '.NCES

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1.

SUMMARY

Low Power Physics Testing and Power Ascension Testing for Millstone 2 Cycle 9 identified no unusual situations or anomalies. All parameters measured were within their acceptance criteria and Technical Specification limits. One parameter is noteworthy of mention:

4 The most positive measured MTC at zero power was + 0.502 X 10

.4 AK/K/ F, while the Technical Specification limit is + 0.50 X 10 AK/K/ F. While the measured value was in excess of the MTC limit, this condition was permitted by a Special Test Exception which allows the limit to be suspended in order to perform the MlC measurement. Administrative restrictions were established on CEA withdrawal and RCS average temperature in order to ensure that the MTC would be within the Technical Specification limits. This is a typical situation at initial startup conditions, given the large boron concentrations required following refueling.

2. INTRODUCTION The Millstone 2, Cycle 9 fuel loading was completed on January 21, 1988.

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

Subsequent operation / testing milestones were completed as follows:

Initial Criticality February 17, 1988 Low Power Physics Testing Completed February 20, 1988 Main Turbine On-Line February 21, 1988 50% Power Testing Completed February 24, 1988 96% Power Testing Completed February 28, 1988 100% Power Testing Completed March 7, 1988 Cycle 9 operation is with 217 Westinghouse manufactured fuel assemblies.

The Safety Analysis is supplied by Westinghouse.

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3. LOW POWER PHYSICS TESTING RESULTS

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Low Power Physics Testing was performed at a power level of < 5 X 10 power to avoid heat addition from the nuclear fuel.

3.1 Critical Baron Concentrations Critical Boron Measurements were taken at two different Control Element Assembly (CEA) configurations, at All Rods Out (AR0) and with CEA Groups 7 through 2 inserted. See Figure 2, CEA and Excore Detector locations.

The Critical Boron Concentration (CBC) measured with CEA Group 7 at 142 steps was 1298 ppi. Adjusted to All Rods Out, the CBC is 1306 ppm. Therefare.

Measured CBC at BOL-HZP-ARO = 1306 ppm Baron Predicted CBC at BOL-HZP-ARO = 1279 ppm a= 27 ppm The Acceptance Criteria is t 87 ppm.

Acceptance Criteria met ? Yes The Critical Boron Concentration (CBC) measured with CEA Groups 7 through 3 inserted and Group 2 at 18 steps was 882 ppm.

Adjusted to CEA Groups 7-2 inserted, the CBC is 877 ppm.

Therefore, Measured CBC at BOL-HZP 2-7 CEA = 877 ppm Boron Predicted CBC at BOL-HZP 2-7 CEA = 859 ppm A= 18 ppm The Acceptance Criteria is 1 87 ppm.

Acceptance Criteria met? Yes

3. 2 Control Element Assembly (CEA) Symmetry Checks Millstone 2 performs rod swaps among all CEA's in a group of CEA's to verify that no serious tilts are present from either a core misloading, CEA problem, or other reactivity anomalies.

Results of the CEA symmetry checks are expressed as the largest deviation (in cents of reactivity) of any CEA from the average CEA for that CEA group.

Two sets of values are given, raw values and corrected values.

The corrected values take into account the slight design tilt, since the core is not exactly 1/8 core symmetric. The raw values assume the core is 1/8 core symmetric.

The results were:

Maximum Value of Maximum Value of Raw Deviation (C) Corrected Deviation (C)

Group 1 CEA's 1.02 1.04 Group 3 CEA's 1.24 1.47 Group A CEA's 0.62 0.80 Group 8 CEA's 0.47 0.71 The Acceptance Criteria is i 2.50.

Acceptance Criteria met? Yes NOTE: peff = 0.5925% AK/K

3.3 Moderator Temperature Coefficients The Moderator Temperature Coefficients (MTC) were measured at two different CEA configurations, at All Rods Out and with CEA Groups 7 through 2 inserted.

All Rods Out MTC Measurement The measured MTC value witt. CEA Group 7 at 148 steps, an average RCS temperature cf 526.3 F, and an RCS boron concentration of 1298 ppm was + 0.493 X 10' AK/K/ F.

Comparing the adjusted MTC value to the predicted value yields:

Adjusted, measured MTC at 532 F,1279 ppm, BOL, ARO = + 0.502 X 10' AK/K/ F Predicted MTC at 532 F, 1279 ppm, 80L, ARO = + 0.440 X 10 AK/K/ F a= 0.062 X 10' AK/K/*F The Acceptance Criteria is t 0.3 X 10' AK/K/*F.

Acceptance Criteria met? Yes In addition to comparing the measured MTC value to the predicted value, it is also required to verify that the Technical Specification MTC limits are satisfied.

The Millstone 2 Technical Specification MTC limit states that the MTC shall be less positive than + 0.50 X 10' AK/K/ F whenever thermal power is less than or coual to 70% of rated thermal power.

While the measured MTC value exceeds the Technical Specification limit, this is permitted by a Special Test Exception which allows the MTC limit to bt suspended in order to allow the MTC measurement to be performed.

Since the measured MTC value was in excess of the Technical Specification limit, it was necessary to establish administrative restrictions on CEA withdrawal and RCS average temperature in order to ensure that the MTC would be less positive than

+ 0.50 X 10 AK/K/ F. These restrictions were only required until the critical boron concentration was reduced by fuel depletion.

CEA Groups 7-2 Inserted ITC Measurement The manured ITC value with CEA Groups 7 through 3 inserted and CEA Group 2 at 12 steps, at an average RCS temperature of 528.0 F, and an RCS boron concentration of 882 ppm was

-0.717 X 10' AK/K/ F.

Adjusting this measured value to the prediction conditions of 532 F and 859 ppm yields an ITC value of -0.709 X 10' AK/K/ F.

Comparing the adjusted ITC value to the predicted value yields:

Adjusted, measured ITC at 532 F, 859 ppm, BOL, CEA 7-2 Inserted = -0.709 X 10' AK/K/ F Predicted ITC at 532 F, 859 ppm, BOL, LEA 7-2 Inserted = -0.530 X 10' AK/K/ F A = 0.179 X 10' AK/K/ F The Acceptancn Criteria is 1 0.3 X 10 AK/K/ F.

Acceptance Criteria met? Yes

3.4 Control Element Assembly Reactivity Worths Reactivity worth measurements were performed twice on CEA Groups 7 through 2. The first measurement involved measuring the reactivity worth of each CEA group individually. The second measurement involved measuring tha reactivity worth of CEA Groups 2, 3, and 4 individually, and CEA Groups 5 through 7 in their normal overlap mode of operation.

The results of the measurements were:

Individual CEA Group Measurements (by dilution)

CEA Measured Predicted Delta  % Difference Group Worths (%AK/K) Worths (%AK/K) (M-P) [(M-P)/P]

7 0.713 0.688 0.025 3.6%

6 0.414 0.413 0.001 0.2%

5 0.278 0.263 0.015 5.7%

4 1.128 1.112 0.016 1.4%

3 0.473 0.465 0.008 1.7%

2 1.538 1.406 0.132 9.4%

Total 4.544 4.347 0.197 4.5%

CEA Overlap Measurements (by boration)

CEA Measured Predicted Delta  % Difference Group Worths (%AK/K) Worths (KiK/K) (M-P) [(M-P)/P]

2 1.507 1.406 0.101 7.2%

3 0.463 0.465 -0.002 -0.4%

4 1.093 1.112 -0.014 -1.3%

5-7 1.391 1.364 0.027 2.0%

Total 4.459 4.347 0.112 2.6%

The Acceptance Criteria for the Total Worth of CEA Groups 7 through 2 inserted is i 10% of the predicted total worth.

Acceptance Criteria mot? Yes

The Acceptance Criteria for any individual CEA Group is the greater of either 10.1% AK/K or i 15% of the predicted group worth.

Acceptance Criteria met on all CEA Groups? Yes i

3.5 Ho_t Rod Orops Hot Rod Orops were performed on all 61 CEA drive mechanisms.

The drop times from 0 to 100% insertion ranged from 2.20 to 2.48 seconds.

The Acceptance Criteria, per Millstone 2 Technical Specifications, is that all CEA's must drop from 0 to 90% insertion in less than 2.75 seconds.

Acceptance Criteria met? Yes

4. POWER ASCENSION TESTING RESULTS 4.1 Power Peaking, Linear Heat Rate and Tilt Measurements The measurements of these parameters were:

T T Power level Fxy Fr Maximum Linear Heat Rate Incore Tilt 50% 1.485 1.411 6.62 KW/ft 0.003 96% 1.458 1.384 12.17 KW/ft 0.005 100% 1.434 1.366 12.19 KW/ft 0.005 The corresponding Technical Specification limits are:

T T l

Power Level Fxy Fr Maximum Linear Heat Rate Incore Tilt 50% 1.836 1.675 15.6 KW/ft 0.020 96% 1.719 1.542 15.6 KW/ft 0.020 l 100% 1.719 1.537 15.6 KW/ft 0.020 l

l Technical Specification limits met? Yes l

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D 4.2 Boron Measurements At 50% power, 38 MWD /MTU, ARO and Equilibrium Xenon, the measured boron concentration was 999 ppm.

Measured boron concentration 50% power, 38 MWD /MTU, AR0, EQ. Xenon = 999 ppm Predicted boron concentration 50% power, 50 MWD /MTU, ARD, EQ. Xenon = 1017 ppm A= 18 ppm The Acceptance Criteria is 1 87 ppm Boron.

Acceptance Criteria met? Yes At 100% pover, 2.18 MWD /MTU, CEA Group 7 at 171 steps and Equilibrium Xenon, the measured boron concentration was 887 ppm.

Adjusted, Measured boron concentration 100% power 218 MWD /MTU, AR0, EQ. Xenon = 880 ppm Predicted boron concentration 100% power 218 MWD /MTU, AR0, EQ. Xenon = 900 ppm a, 20 ppm The Acceptance Criteria is i 87 ppm Boron.

Acceptance Criteria met? Yes

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4.3 Moderator Temperature Coefficient at 96% Power The measured MTC value at 96% power, with CEA Group 7 at 150 steps, at an average RCS temperature of 567.14 F, and an

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RCS boron concentration of 900 ppm was -0.427 X 10 AK/K/ F.

Adjusting this measured value to the prediction conditions of

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96%, 567.2 F and 908 ppm yields an HTC value of -0.417 X 10 AK/K/ F.

Comparing the adjusted MTC value to the predicted value yields:

Adjusted, measured MTC at 96%,

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9e8 ppm boron, and T = 567.2 F = -0.417 X 10 AK/K/ F ave Predicted MTC at 96%,

908 ppm boron, and T,y, = 567.2 F = -0.353 X 10 AK/K/ F A= 0.064 X 10 AK/K/ F The Acceptance Criteria is 1 0.3 X 10 ~4 AK/K/ F.

Acceptance Criteria met? Yes 4.4 Doppler Only Power Coefficient The measured Doppler only power coefficient (00PC) at 93.60%

power, an average RCS temperature of 571.2 F, and an RCS boron concentration of 900 ppm was -1.036 X 10 AK/K/% power.

I Adjusting this measured value to the prediction conditions

.4 yields a Doppler only power coefficient value of -1.034 X 10 AK/K/% power.

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Comparing the adjusted value to the' predicted value yields:

Adjusted, measured DOPC at _

93% power, 900 ppm and 572 F = - 1.~034 X.10 AK/K/% Power Predicted.00PC at-93% power 908 ppm'and 572 F. = -0.931'X 10 AK/K/% Power

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A= 0.103 X 10 AK/K/% Power The Acceptance Criteria is 1 0.3 X 10" AK/K/% Power.

Acceptance Criteria met? Yes 4.5 RCS Flow at 100% Power The measured RCS flow at 100% power was 361,600 GPM.

The Acceptance Criteria per Millstone 2 Technical Specifications, is that RCS flow must be greater than 340,000 GPM.

Acceptance Criteria met? Yes 4.6 Power Distributiog Power Distribution Maps are shown for 50% and 100% power conditions in Figures 3 and 4. The agreement between the measurements and the predictions is good.

Tna Acceptance Criteria is that all locations are within i 10%

of -he predicted values.

Acceptance Criteria met? Yes 4.7 Reactor Coolant System Radiochemistry Reactor Coolant System (RCS) radiochemistry analyses during power ascension testing and subsequent power operation showed low activity levels in the RCS with Iodine-131 values of about 4 X 10' pCi/ml.

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5. REFERENCES 5.1 In-Service Test T88-1, Initial Criticality / Low Power Physics Test - Cycle 9.

5.2 In-Service Test T88-2, Power Ascension Test - Cycle 9.

5. 3 Westinghouse Nuclear Design Report - Cycle 9. WCAP-11695.

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Figure 1 1 2 3 4 5 6 7 8 9 10 11 1213 14 15 16 17 18 19 20 21 L68 L48 L29 L27 L53 L30 L59 J50 Og35 J80 L57 W L67 X 115 40 L39 J20 K52 J73 Ltd J35 LO9 J87 K22 J21 L66 14 79 98 89 55 L47 Ll6 K44 J30 K06 Kl6 JIB Kit K13 Jt7 K25 LOS L33 Y 95 W 110 114 87 51 L50 J24 K3G K21 J56 KiB K42 J83 K19 K30 J44 K32 K40 J29 L55 T- 6 Plug 82 88 Plug 122 L49 K63 J25 J53 G40 K24 J79 J74 J77 K37 G61 J67 J28 K49 L31 3 120 59 g 107 17 L28 J70 K14 K56 K55 HOS Ll3 J78 LO7 H01 K53 K26 K07 J75 L41 5 85 111 77 45 90 84 L54 L32 p

J69 LO8 K10 K59 J48 LO2 JB4 H16 J71 L15 J61 K48 K02 LIB J51 N 103 106 113 38 SB 123 O (g

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% Plu0 22 100 118 Plug 99 L64 g L37 J42 LO3 K09 K23 J85 Ll7 J49 Hl4 J60 LO! J62 K64 KIS L19 J54 1 80 28 37 57 64 L23 L46 g

L65 J76 K08 K39 K57 H06 LO4 J68 L12 H09 K34 K31 K05 J46 L42 G 104 12 76 116 78 83 121 L22 KS8 J23 J45 G45 K61 JS1 J66 J50 K38 G38 J65 J27 K17 L34 F 49 91

@ 105 109 L56 Ji9 K33 K62 J59 K45 K28 J88 K50 K27 J86 K43 K60 J32 L26 E 3 Plug 81 117 Plug 60 L45 LIO K47 J31 K03 K04 J38 K12 K01 J34 K54 LO6 L25 0 92 108 112 86 119 94 L36 J39 K46 J41 L20 J33 L11 J82 K51 J22 L24 C

11 25 97 41 52 L21 L35 L61 J55 K20 J63 L38 L43 L62 0 26 g 35 L52 L51 L58 L63 b

SOURCE CORE LOCATION S-3 F-3 (SV)

CYCLE 9 570 S-4 S-19 ( SE 1 CORE MAP g S-5 X-11 (NV)

S-6 B-11 (SV1 e- SOURCE

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t Figure.2 CEA and Excore Detector Locations 1 2 3 4 5 6 7 8 9 10 11 1213 14 15 16 17 18 19 20 21 Y

Y x 3-66 3-67 V A-47 4-55 7-41 4-56 A-48 V 7-65 A-47 1-31 1-32 A-40 7-68 1 A-46 2-23 2-24 A-49 S A-46 6-16 6-17 A-49 R 4-54 2-22 B-8 5-5 B-9 E-25 4-57 P

N 3-64 t-30 B-e B-9 l-33 3-69 H

L 7-40 5-4 7-1 5-2 7-38 K

J 3-63 1-29 B-7 B-6 1-26 3-58 H

G 4-53 2-21 B-7 5-3 8-6 2-10 4-50 F A-45 6-15 6-14 A-42 E A-45 2-20 2-19 A-42 D 7-62 A-44 1-28 1-27 A-43 7-59 C A-44 4-52 7-39 4-51 A-43 B 3-61 3-60 A

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figure 3 Relative Power Densitles -

50% Power -

BOC'9 L 0.66 0.678

+2.7%

e 0.83 10 0.90 0.832 0.933

+0.2% +3.7%

3 0.94 I'1.19 te o,90 0.964 1.219 0. ill ,

+2.5% +2.4% +3 3%

• 0.97 12 0.98 l9 1.15 24 1.02

-2 5% C 2; - 1.5 0 5 1.00 13 1.24 ao 1.23 25 1.04 29 1.25 0.996 1.230 1.212 1.034 1.241

-0.4% -0.8% -1.5% -0.6% -0.7%

6 0.86 14 1.09 atg.07 26 0.87 30 1.14 331.13 "

0.831 1.083 1.073 0.886 1.162 1.131

-3.4% -0.6% +0.3% +1.8% +1.9% +0.1%

35 22 j ,og 3d 7

0.92 1.29 27 1.13 3'O.71 0.68 0.917 1.273 1.093 1.126 0.735 0.G94  !

-0.3% -1.3% +1.2% -0.3% +3.5% +2.1%

23 28 8

1.17 is 0.98 1.15 0.92 32 0.56 1.131 0.980 1.142 0.936 0.577

-3.3% 0.0% -0.7% +1.7% +3.0%

S 0.90 '7 0.69 0.878 0.664

-2.4% -3.8%

KEY XXX = Predicted RPD. 50% Power. ARO. Ea. Xenon. 50 MVD/MTU YYY = INCA Heosured RPD 50% Power. ARD. Eo. Xenon. 30 MVDA1TU ZZZ = Percent Difference I (( M-P 1/P l'1001 Nunber in upper left corner is the reference octont locotton nunber

Figure 4 ,

Relotive Power Densit-ies 100% Power -

BOC 9

' O.713 0.734

+2.9%

a 0.887 3 0.947 0.900 0.980

+1.5% +3.5%

3 0.981 t.227 18 0.939 ,

1.003 1.255 0.955

+2.2% +2.3% +1.7%

• 1.006 38 1.013 39 1.179 t.045 0.977 0.999 1.156 1.028

-2.9% -l.4% -1.9% -1.6%

5 25 1.025 18 1.252 #

1.243 1.057 2'l.243 1.012 1.238 1.222 1.038 1.235

-1.3% -1.1% -1.7% -1.8% -0.6%

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6 0.882 1.099 1.081 26 0.879 8'l.132 33 1.100 0.850 1.086 1.078 0.883 1.150 1.120

-3.6% -1.2% -0 3% +0.5% +1.6% +1.8%

7 'S 0.915 1.265 22 1.064 27 1.100 3'O.704 3'O.667 0.907 1.254 1.076 1.109 0.728 0.688

-0,9% -0.9% +1.1% +0.1% +3.4% +3.1%

is 3 #8 3# '

1. ' 1 131 0.947 1.101 0.889 0.557 l.097 0.955 1.104 0.909 0.573

-3.0% +0.8% +0.3% +2.2% 2.9%  !

' 7 0 860 0.661 0.052 0.648

-0.9% -2.0%

b KEY XXX = Predicted RPD. 100% Power. ARD. Eq. Xenon. 500 t1VD/MTU YYY = INCA Measured RPD. 100% Power. ARO. Eq. Xenon. 504 MVD/MTU ZZZ = Percent Di f rerence 1 ( ( M-P 1/P l* 1001 Nunber in upper left hond corner is the reference octont location nunber

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P.O.8OX 270 H ARTFORD. CONNEC7ICUT 06141-0270 k L J Z [ C(($U,'$~. (203) 665-5000 April 20, 1988 Docket No. 50-336 B12865 Re: Technical Specification 6.9 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Millstone Nuclear Power Station, Unit No. 2 Start-Up Test Reoort for Cycle 9 Millstone Unit No. 2 achieved criticality on February 17, 1988, and reached 100 percent power on February 28, 1988, following its refueling outage. As required by the Millstone Nuclear Power Station Unit No. 2 Technical Specifi-cations, Section 6.9, Northeast Nuclear Energy Company hereby submits the attached Millstone Unit No. 2 Cycle 9 Start-Up Test Report.

We trust you will find this information satisfactory.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY D.d, AcV) M_

E. J. Hroczka '

Senior Vice President

( 2L o vL By: C. F. Sears Vice President l Enclosure cc: W. T. Russell, Region I Administrator D. H. Jaffe, NRC Project Manager, Millstone Unit No. 2 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3 P. Habighorst, Resident Inspector, Millstone Unit No. 2 h