B13305, Startup Test Rept Cycle 10

Startup Test Rept Cycle 10

ML20247N700
Person / Time
Site:	Millstone
Issue date:	07/31/1989
From:	Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B13305, NUDOCS 8908030118
Download: ML20247N700 (11)

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- j NORTHEAST UTILETIES o.ners Ome.. . seiden street. Boriin. Connecticut 1 sty NEsI[cE[cc" P.O. BOX 270

.=.ome wma rowea u"" HARTFORD. CONNECTICUT 06141-0270 k k J C 7., ((C,"$~, (203) 665-5000 July 24, 1989 Docket No. 50-336 B13305 Re: Technical Specification 6.9 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Millstone Nuclear Power Station, Unit No. 2 Start-Un Test Report for Cycle 10 l

Millstone Unit No. 2 entet ed Mode 1 on April 30, 1989, and the Cycle 10  !

startup test program was completed on May 18, 1989, following its refueling outage. As required by the Millstone Unit No. 2 Technical Specifications, 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

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E.J.Yrgczka //

Senior Vice President Enclosure cc: W. R. Russell, Region I Admini:trator G. S. Vissing, 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

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Iy 6900030118 890731 PDR ADOCK 05000336 P PDC

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Docket No. 50-336 813305 Millstone Nuclear Power Station, Unit No. 2 Start-Up Test Report Cycle 10 July 1989

9 INDEX

1.

SUMMARY

2. INTRODUCTION

3. LOV POWER PHYSICS TESTING RESULTS - CYCLE 10 3.1 All Rods Out Critical boron Concentration 3.2 All Rods Out Moderator Temperature Coefficient 3.3 Control Element Assembly red Worth Parameters 3.4 Hot Rod Drops

4. POWER ASCENSION TESTING - CYCLE 10 4.1 Power Peaking, Linear Heat Rate, Incore Tilt 4.2 Critical boron Measurements 4.3 Moderator Temperature Coefficient 4.4 Doppler Only Power Coefficient 4.5 Reactor Coolant System Flow 4.6 Power Distributions 4.7 Reactor Coolant System Chemistry

5. REFERENCES

6. FIGURES Figure 1 - Cycle 10 Core Loading Plan Figure 2 - CEA Group Configuration Figure 3 - 100% Power Distribution Map l

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1.

SUMMARY

- Cycle 10 Startup The Cycle 10 startup and operation at Millstone 2 saw several significant changes as compared to previous operating cycles. These are:

(1) The vendor supplying the reload fuel assemblies and safety analyses was changed from Westinghouse to Advanced Nuclear Fuels, (2) The Cycle 10 core is a " low leakage" core design, and (3) The Lov Power Physics and Power Ascension Testing programs were revised in order to provide a more efficient test program, while performing the required testing of ANSI /ANS-19.6.1-1985, "Pels.d Startup Physics Tests for Pressurized Water Reactors."

During the Low Power Physics Testing program, it was observed that CEA Group 4 failed the Acceptance Criteria for its Rod Vorth Parameter.

This deviation was reviewed by Advanced Nuclear Fuels for its impact on the Cycle 10 Safety Analysis, and it was concluded that the measured results of the Group 4 Rod Worth Parameter are acceptable. All other Low Power Physics Testing results were acceptable.

All Power Ascension Testing results were acceptable.

At 100% power operation, RCS Hot Leg temperature stratification was observed to have increased relative to previous operating cycles. This increase is believed to be due to the lov leakage core.

2. INTRODUCTION Millstone 2, Cycle 10 fuel loading was completed on February 22, 1989.

The attached core map (Figure 1) shows the final core geometry. The subsequent operation / testing milestones were completed as follows:

Initial Criticality April 23, 1989 Low Power Physics Testing Completion April 25, 1989 Turbine On-Line April 30, 1989 Complete 55% Power Testing May 4, 1989 Complete 96% Power Testing May 10, 1989 Comolete 100% Power Testing May 16, 1989 l

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l Cycle 10 operation is.with approximately 157 Westinghouse manufactured fuel assemblies and 60 Advanced Nuclear Fuels manufactured fuel assemblies. The Safety Analysis is supplied by Advanced Nuclear Fuels.

3. LOV POVER PHYSICS TESTING RESULTS Low Power Physics Testing was conducted at a power level of l

approximately 10-2s power.

3.1 All Rods Out Critical Boron Concentration The Critical boron Concentration (CBC) measured with CEA Group 7 at 158 steps withdrawn was 1304 ppm. Adjusted to an All Rods Out condition, the CBC is 1310 ppm, CBC Measured at BOL-HZP-ARO = 1310 ppm CBC Predicted at BOL-HZP-ARO = 1291 ppm Difference = 19 ppm Acceptance Criteria is 50 ppm of the predicted CBC.

Acceptance Criteria met? Yes 3.2 All Rods Out Moderator Temperature Coefficient The Moderator Temperature coefficient (MTC) measurements were performed at a boron concentration of 1304 ppm, a temperature of 528.7'F and a CEA Group 7 position of 159 steps withdrawn.

The measured Moderator Temperature Coefficient at these conditions was +0.409 x 10-4 o K/K/'F. Adjusted to the prediction conditions, the measured MTC is 40.378 x 10-4 o K/K/*F.

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.MTC Measured at 532'F, 1291 ppm --+0.378 x 10-8oK/K/*F MTC Predicted at 532*F,'1291 ppm . +0.548 x 10-4oK/K/*F Difference . .0.170 x 10-4oK/K/'F Acceptance Criteria is i 0.2 x 10-4A K/K/*F of the predicted MTC.

. Acceptance Criteria met? Yes Additionally, per the Millstone 2 Technical specifications, the i

MTC must be less. positive than +0.7 x x 10-4 A K/K/*F for power levels less than 70% power.

Acceptance Criteria met? Yes 3.3 control Element Assembly Rod Worth Parameters Control Element Assembly (CEA) Rod Vorth Parameters were performed using the Rod Swap measurement technique. CEA Group A vas used as the Reference CEA Group. All of the remaining CEA groups vere

'then svapped with Group A. Figure 2 shows the CEA Group configuration. The results of the CEA measurements vere Group Measured Prediction Difference  % Difference A 1.107%8K/K 1.011%oK/K 0.096%oK/K 9.50%

B 0.540%oK/K 0.591%oK/K -0.051%oK/K -8.63%

1 1.015%oK/K 0.905%oK/K 0.110%oK/K 12.15%

2 0.797%oK/K 0.720%oK/K 0.077%oK/K 10.69%

3 0.403%oK/K 0.348%oK/K 0.055%oK/K 15.80%

4 0.619%oK/K 0.517%oK/K 0.102%6K/K 19.73%

5 0.402%oK/K 0.461%oK/K -0.059%oK/K -12.80%.

6 0.469%oK/K 0.447%oK/K 0.022%oK/K 4.92%

7 0.846%oK/K 0.800%oK/K. 0.046%oK/K 5.75%

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5.800%oK/K 0.398%oK/K 6.86%

Total 6.198%oK/K l

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m The' Acceptance Criteria is that the Reference Group.vorth should be within i 10% of the predicted value.

i Acceptance Criteria met for the' Reference Group? Yes The Total CEA Vorth should be within i 10% of the predicted value.

' Acceptance Criteria met for the Total ~CEA Worth? Yes The Acceptance Criteria for the remaining individual CEA Groups is.

that the Rod Vorth Parameter of the remaining individual CEA Groups should be within t15% or 1 0.1%oK/K (whichever is greater) of the predicted value.

Acceptance Criteria met for the individual CEA Groups? Yes, on all groups EXCEPT for CEA Group 4, which failed the 20.1%oK/K criteria.

.This deviation was reviewed by Advanced Nuclear Fuels for its i

impact on the Cycle 10 Safety Analysis, and it was concluded that the. measured results of the Group 4 Rod Worth Parameter are acceptable.

3.4 Hot Rod Drops Hot Rod Drops were performed on all 61 CEA drive mechanisms.

The drop times from 0 to 100% insertion ranged from 2.17 to 2.49 seconds.

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The Acceptance Criteria, per tiillstone 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. POVER ASCENSION TESTING RESULTS 4.1 Power Peaking, Linear Heat Rate and Incore Tilt Measurements The measurements of these parameters were Power Level F,7 haaimum Linear Heat Rate Incore Tilt 55% 1.669 7.8 KV/ft 0.007 96% 1.593 13.3 KV/ft 0.009 100% 1.576 13.5 KV/ft 0.009 l

The corresponding Technical Specification limits are:

Power Level F,7 Maximum Linear Heat Rate Incore Tilt 55% 1.749 15.1 KV/ft 0.02 96% 1.617 15.1 KV/ft 0.02 100% 1.611 15.1 KV/ft 0.02 Technical Specification limits met? Yes l

4.2 Critical Boron Hes-drements At 100% power, 425 HVD/HTU, CEA Group 7 at ARO and Equilibrium Xenon, the measured boron concentration was 889 ppm.

Adjusted, Heasured boron concentration at 100% power, 425 HVD/HTU, ARO, Eq. Xenon - 886 ppm Predicted, Heasured boron concentration at 100% power, 425 HVD/HTU, ARO, Eq. Xenon = 874 ppm Difference = 12 ppm l

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Acceptance Criteria is 1 50 ppm of the predicted CBC.

l Acceptance Criteria met? Yes

l 4.3 Moderator Temperature Coefficient The measured MTC value at 96% power, with CEA Group 7 at 150 steps, at an average RCS temperature of 567.81'F and an RCS boron concentration of 908 ppm was -0.468 x 10-8SK/K/'F.

Adjusting this measured value to the prediction conditions of 96%

power, 367.2'F and an RCS boron concentration of 880 ppm yields an MTC value of -0.431 x 10-8 oK/K/'F.

Comparing the Adjusted, Heasured MTC value to the predicted value yields:

Adjusted, Measured MTC at 96% power, 888 ppm horon, and Tave - 567.2'F - ~0.431 x 10-8oK/K/'F Fredicted MTC at 96% power, 888 ppm boron, and Tave - 567.2'F -0.351 x 10-4oK/K/'F Difference - -0.080 x 10-4oK/K/'F Acceptance Criteria is t 0.3 x 10-8GC/K/*F of the predicted MTC.

Acceptance Criteria met? Yes

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' 4.4 Doppler Only Povar Coefficient The measured Doppler only Power Coefficient.(DOPC) at 93.92%

power, an average RCS temperature of 571.6*F, and an RCS boron ecceentration of.908 ppm was -1.204 x 10-4$K/K/% Power.

Comparing the measured DOPC value to the predicted value yields:

Measured.DOPC at 93.92% power.

928 ppm boron, and Tave - 571.6'F - -1.204.x 10-4oK/K/'F

. Predicted DOPC at 93% power, 888 ppm boron, and Tave = $72*F - -0.990 x 10-4oK/K/*F Difference - -0.214 x 10-4AK/K/'F Acceptance Criteria is 1 0.3 x 10-4oK/K/*F of the predicted DOPC.

Acceptance Criteria' met? Yes 4.5 Reactor Coolant System Flow The measured Reactor Coolant system Flow Rate at 100% power vas.

356,280 GPM.

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When 13,000 GPM is' subtracted from the measured flow rate to account fot ~ measurement uncertainties, the Minimum Guaranteed Safety Analysis RCS Flow Rate is 343,280 GPM.

The measurement uncertainty value of 13,000 GPM is 4% of the Design Flow Rate valle of 324,800 GPM.

The Acceptance Criteria per Millstone 2 Technical Specifications, is that the RCS flow must be greater than 340,000 GPM or greater than 325,000 GPM vben' compensated for by reductions in the F,7 limit.

Acceptance Criteria met? Yes

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-4.6 . Power Distributions

'The Radial Power Distribution map for 100%' power, 495 MVD/MTU, All' Rods Out, Equilibrium Xenon conditions is shown in Figure 3. The agreement between the measurements and the predications is acceptable.

The' Acceptable Criteria is that all locations are within 2L10% of~

the predicted values.

Acceptance Criteria met? Yes 4.7. Reactor Coolant System Radiochemistry Reactor Coolant System radioch'emistry analyses during the power ascension testing program and subsequent power showed low activity

-levels in the RCS with Iodine-131 values of about 6 x 10-3 pCi/ml.

5. REFERENCES 5.1 In-Service Test T89-11, Initial Criticality / Low Povei Physics Test

- Oycle 10.

5.2 In-Service Test T89-12, Power Ascension Test - Cycle 10.

5.3 Advanced Nuclear Fuels Millstone Unit 2, Cycle 10, Startup and Operations Report.

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