ML20077N568

Startup Test Rept, Cycle 4

ML20077N568
Person / Time
Site:	Millstone
Issue date:	06/30/1991
From:	Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-91-642, NUDOCS 9108150015
Download: ML20077N568 (15)

Text

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I$7[a:I$t rIE'Eany HARTFORD. CoNNEOTIOUT 06414-0270 l Nortteast twes* t re c< comp *"r (2031666-5000 August 6, 1991 MP-91-642 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 hiillstone Nuclear Power Station Unit No. 3 Transmittal of Startun Report in accordance with hiillstone Unit No. 3 Technical Specifications Section 6.9.1.1, hereby submits the Startup Report for Northeast Cycle 4 of operationNuclear Energy within 90 daysCompany of complet (NNECo) ion of the Cycle 4 startup test progr If you have am questions related to this submittal, please contact hir. Jeffry Langan at (2D3) 444-5544 directly.

Very truly yours, NORTHEAST NUCLEAR ENERGY COh1PANY

, i

/-Steph6n

} tllN E. ~Scace lf Mc Director, hiillstone Station SES

cle Attachment cc: T. T. h1artin. Region 1 Administrator W. J. Raymond, Senior Resident ins Sector, hiillstone Unit Nos.1, 2 and 3 D. H. Jaffe, NRC Project hianager. Afillstone Unit Nos.1 and 3

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08/Op/91, MP-91-642

, , s Docket No. 50-423 MILLSTONE NUCLEAll POWElt STATION UNIT NO. 3 STAllTUP TEST ItEl'OltT CYCLE 4 JUNE 1991 _

,' Page 2 of 14 INDEX

1. SUhth1ARY

2. INTRODUCTION

3. LOW POWER PHYSICS TESTING RESULTS 3.1 Critical Boron Concentrations 3.2 hioderator Temperature Coefficients 3.3 Control Rod Reactivity Worths

4. POWER ASCENSION TESTING RESULTS 4.1 Power Peaking, and Tilt hieasurements 4.2 Boron hieasurements 4.3 Doppler Only Power Coefficient Ratio-4.4 RCS Flow 4.5 Power Distributions

5. REFERENCES-0

Pape 3 of 14

1. SUM $1 Ald' Low power l'hysics Testing and Power Ascension Testing for h1illstone 3, Cycle 4 identified no unusual situations or anomalies. One parameter was determined to  !

be outside its acceptance etiteria. This is discussed in Section 3.1. All Technical Specification limits were met. ,

2. INTRQ11L'fDDE The hiillstone 3. Cycle 4 fuel loading was completed on hiarch 8,1991. The attached core map (Figure 1) shows the final core configuration. Eighty-eight (86) new fuel assemblies were inserted into the core. h1ajor changes from the hiillstone 3 Cycle 3 core design are:

• Incorporation of intermediate flow mixing prids.  ;

Deletion of 90 thimble plugs.

• Changeout of 35 Hafnium control rods to Silver-Indium-Cadmium control rods.

Subsequent operation / testing milestones were completed as follows:

initial Criticality April 13,1991 Low Power Physics Testing Completed April 15,1991 '

hiain Turbine On-Line April 16,1991 309 Power Testing Completed April 18,1991 75G Power Testing Completed April 20,1991 1009 Power Testing Completed hiay 08,1991 Cycle 4 operation is with 193 Westinghouse manufactured fuel assemblies. The Safety Analysis is supplied by Westinghouse.  :

3. LOW POWER PHYSICS TESTING RESULTS_

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 Boron ConeentrEinth Critical Boron hieasurements ' vere taken at two different Rod Control Cluster Assembly (RCCA) configurations; at All Rods Out (ARO) and with RCCA Control Banks D C, B, and A inserted.

.. _ .___ ._. ~ ,_ _,_.. _._-_ _ _ _ _ _ -_

,- Page 4 of 14 The Critical Boron Concentration (CBC) measured with RCCA Bank D at 208 steps was 2207 ppm. Adjusted to A!! Rods Out, the CBC is 2208 ppm. Therefore, Measured CBC at EOL-llZP-ARO = 2208 ppm Boron Predicted CBC at BOL-HZP-ARO = 2315 onm A = -107 ppm The Acceptance Criteria is 150 ppm.

Acceptance Criteria met? No The design review criteria for this parameter indicates agreement would be expected to be within 150 ppm of the predicted value. The safety review criteria for this parameter requires agreement within 1G AK/K of predicted reactivity, Using a predicted boron worth of 6.46 pcm/ ppm,.this equates to -

155 ppm. Review of other Low Power Physics Testing results indicated all acceptance criteria were met. Since all other acceptance criteria were met,-

and the safety. review criteria of 155 ppm was met. it was determined that the rneasured ARO critical Boron Concentration did not violate the safety analysis assumptions. Westinghouse also reviewed this discrepancy prior to completion of Low Power Physics Testing and determined that the condition did not violate safety criteria Power operation to 30% power, where a flux map would be performed to further verify pov r distribution, was acceptable.

The Critical Boron Concentration (CBC) measured with Control Banks D, C. B & A inserted (ARI) was 1717.7 ppm.

Measured CBC at BOL-HZP-ARI = 1717.7 ppm Boron -

Measured CBC at BOL-HZP-ARO -- 2208 ppm Difference in ARI and ARO CBC A (CB) = -490.3 The Acceptance Criteria is -531 ppm 50 ppm.

Acceptance Criteria mct? Yes 3.2 1sothermal/ Moderator Temnerature Coefficients g The isothermal Temperature Coefficients (lTC) was measured at two different RCCA configurations; at All Rods Out and with Control Bank D, C, B & A inserted. Values for the Moderator Temperature Coefficient (MTC) were then calculated.

All Rods Out ITC Meesurement The measured ITC value with Control Bank D at 207 steps, an average RCS temperature of 554*F, and an RCS Boron Concentration of 2217 ppm was .056 x 10" AK/K/*F.

i Page 5 of 14 Comparing the measured ITC value to the predicted value yields:  !

hieasured ITC at BOL, ARO = .056 x 10-d AK/K/*F q Predicted ITC at DOL, ARO = .061 x 10'! AK/K/* F A= .005 x 10 AK/K/'F i

The Acceptance Criteria is A0.2 x 10-d AK/K/*F.

Acceptance Criteria met? Yes All Rods Out h1TC Determinq11on The h1TC was calculated by subtracting the design Doppler Temperature Coefficient from the ARO ITC. In addition to comparing the measured h1TC value to the predicted value, it was also required to verify that the ,

Technical Specification h1TC limit of ( 4.5x10'dAK/K/*F at ARO, HZP was r m et. 1 Comparing the measured h1TC value to the predicted value yields:  :

Calculated h1TC at BOL, ARO = .225 x 10-d AK/K/* F Predicted h1TC at BOL, ARO - , 230 x 10-d AK/K/'F 5

Technical Specification Acceptance Criteria < +.5x10-dAK/K/*F.

Acceptance Criteria met? Yes Control Banks D. C. B. and A Inserted ITC Measurement The measured ITC value with Control Banks D, C, B & A inserted at an '

average RCS temperature.of 555'F and RCS Boron Concentration of 1718 ppm was ,740 x 10-d AK/K/*F Comparing the measured ITC value to the predicted value yields:

hieasured ITC at BOL, ARI ,740 x 10-d AK/K/'F Fredicted ITC at BOL, ARI = .705 x 10-d AK/K/'F A= ,035 x 10-d AK/K/*F The Acceptance Criteria is 1.2 0 x 10-d AK/K/'F.

Acceptance Criteria met? Yes 3.3 Control Rod Reactivity Worths Reactivity worth measurements were performed twice on Control Banks D, i C, B & A. The first measurement involved measuring the reactivity-worth ,

of each Bank individually. The second measurement involved measuring the reactivity worth of Control Banks A, B, C and D in their sequenced oserlap mode of operation.

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Pape 6 of 14 e

The results of the measurements were:

Individual Bank hieasuremeQE (by dilution) hieasured Piedicted Delta G Difference Sank M'Qtth( (AK/K1 3'orthe ( AK/K) Sj-fi fihi-P1'P1 Control D 48.5 x 10-' 50 x 10 d - 1. 5 -3Q Control C 84.5 x 10-' 94.S x 10-d -10.3 -10.8G Control B 109.1 x 10 8 116.4 x 10-' - 7.3 -6.3G Control A 76.7 x 10-8 87.4 x 10 -10.7 -12.2Q Total 318.8 x 10'd 348.4 x 10'd -29.8 -8.5G Dmian hicasurements (by boration)

Control Bank hieasured Worths (AK/K) in a Seauenced OverInn 316.6 x 10" The Acceptance Criteria for the Total Worth of the Control Banks inserted is A10G of the predicted total worth. The Acceptance Criteria for any individual Control Bank is the greater of either 110 x 10-d AK/K or 115%

- of the predicted group worth.

Subsequent to completion of physics testing, Westinghouse reviewed the assumptions used to generate the predicted rod worths. This review revealed several differences between the control rod _ loading assumed in the model and the actual installed control rod loading. Specifically, significantly more Ap-In-Cd control rods were inserted than originally

- expected. After the model was changed to reflect the as-loaded control rod configuration, the following results were obtained. -

hieasured Predicted Delta  % Difference l} mil; Worthe (AK/K) Worthe ( AK/K) fM-P) ((hi-P)/P)

Control D 48.5 x 10-4 48.9 x 10-d .40 -.,8 %

Control C 84.5 x 10-' 90.5 x 10-d -6.0 -6.6G Control B 109.1 x 10-' 112.3 x 10-4 -3.2 -2.8%

Control A 76.7 x 10-d 84.7 x 10-' -S.0 -9.4%

Total 318.8 x 10" 336.4 x 10-d -17.6 -5.2%

The revised predictions show a substantially improved comparison to the measured worths, hicasurement of. Control Rod Reactivity Worth also verified Technical Specification Surveillance requirements for SHUTDOWN htARGIN, Adequate _ SHUTDOWN h1ARGIN was verified to exist from the Hot Zero Power Rod Insertion Limit.

p i u .. . .. . . .

Page 7 of 14 There is no Acceptance Criteria for the worth of Control Banks measured in sequenced overlap.

Acceptance Criteria met on all Bants? Yes

4. POWEILASCENSION TESTING 1(ESUlfrS 4.1 Power Peakinc and Tilt hieasurementi Flux hiaps were performed to determine incore power distribution and tilt.

The measurements of these parameters, including uncertainty, were:

HEAT FLUX HOT CHANNEL FACTOR - FO(Z)

Abeve hiidooint Peak Below hildnoint Peal hieasured FO(Z) hieasured FO(Z) hiax Incore Power I.evel FO (7) limii FO (7) I imit Tilt 30G 2,19 3.93 2.26 4.83 1.008 50% 1.94 3.82 2.26 3.67 1.002 75G 1.86 2.65 2.18 2.43 1.000 100% 1.77 1.99 2,15 2.33 1.004 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - FNDH Power Level hieatured FNDH FNDH Limit >

30G 1.58 1.98 50Fc 1.57 1.89 75 9 1.50 1.76 100G 1.47 1.64 At 30% power, results were reviewed in light of the Low Power Physics Test CBC results, Contained power operation proceeded based on the acceptable results of the 30% testing.

4.2 Boron hieasurements At 100% power, 399 h1WD/MTU, Control Bank D at 217 steps and Equilibrium Xenon, the measured Boron Concentration was 1608.4 ppm.

Adjusted, hieasured Boron Concentration 1009 power = 1607,6 ppm.

399 MWD /h1TU, ARO, EO. Xenon Predicted Baron Concentration 1000 power = 1711 ppm.

212 h1WD/h1TU, ARO, EO. Xenon A= -103.4 ppm.

e_

l

,- Pape 8 of 14 Subsequent Horon measurements made at 663 MWD /h1TU yielded the l following results:  !

f Adjusted, hieasured lloron Concentration 100G power - 1607.7 ppm.  !

663 MWD /MTU, ARO, EO. Xenon Predicted Boron Concentration 1009 power = 1702 ppm.  ;

663 MWD /MTU, ARO. EO. Xenon l A= 94.3 ppm. .

The Acceptance Criterm is 1155 ppm Bcron (11% AK/K)  ;

Acceptance Criteria met? Yes 4.3 . Deppler Onh Power Coeffklent A Doppler Only Power Coefficient verification f actor (PCm) was calculated 1 at 1009 and compared to the predicted Doppler Only Power Coefficient verification f actor (PCp) Measurements were tal,en at an average power

-of 99.41ci,590.6'F and RCS Boron Concentration of 1602 ppm. l Measured Predicted PCm Average PCp

.9215'F/% 1.17'F/G i

Acceptance Criteria ,

The absolute difference between PCm and PCp is <0.5 'F/G l.9215 -1.17J = .25'F/G -

Acceptance Criteria met? Yes 4.4 -- RCS Flow The measured RCS flow at 75% power was 402,582 GPM.

The Acceptance Criteria, per Millstone 3 Technical Specifications, is that RCS flow must be greater than 387,480 GPM prior to exceeding 75G power.

Acceptance Criteria met? Yes -

RCS flow.was remeasured at 100% as further verification of acceptable ,

flow. Measured RCS flow at 100% power was 403,168 GPM. '

4.5 Power Distribution ,

Power Distribution Maps are shown for 30G, 50%, 75% and 1009 power conditions in Figures 2, 3, 4 and 5. The agreement between the measurements and the predictions is good.

The Acceptance Criteria is that all locations are within 110% of the predicted value.

Acceptance Criteria met? Yes.

. , _ , . . , _ _ . _ _ _ . ~ . _ _ _ . . . . _ . - _ _ . _ . , . _ . _ _ _ _ , . _ _ _ . - . - ~ . _ _ . . . _ _ . . _ , . . _ . _ . _ , . _ . , . _ _ , _ . . . ,

l'aye 9 of 14

5. 1EEEltENCES 5.1 In-Service Test 3-91-004, initial Criticality / Low Power Physics Test - Cycle 4.

5.2 in-Service Test 3-91-005, Cycle 4 Power Ascension Testing.

5.3 Westinghouse Nuclear Design Report - Cycle 4.

5.4 ANSI /ANS - 19.6.1 - 1985 Reload Startup Phpics Tests For Pressurized Water Reactors.

i 5

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Page 10 of 14

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